The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton...

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Data Bank ISBN 92-64-02314-3 The JEFF-3.1 Nuclear Data Library JEFF Report 21 Edited by Arjan Koning Robin Forrest Mark Kellett Robert Mills Hans Henriksson Yolanda Rugama © OECD 2006 NEA No. 6190 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT

Transcript of The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton...

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Data Bank ISBN 92-64-02314-3

The JEFF-3.1 Nuclear Data Library

JEFF Report 21

Edited by

Arjan Koning Robin Forrest Mark Kellett Robert Mills

Hans Henriksson Yolanda Rugama

© OECD 2006 NEA No. 6190

NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT

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ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT

The OECD is a unique forum where the governments of 30 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies.

The OECD member countries are: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities takes part in the work of the OECD.

OECD Publishing disseminates widely the results of the Organisation’s statistics gathering and research on economic, social and environmental issues, as well as the conventions, guidelines and standards agreed by its members.

* * *

This work is published on the responsibility of the Secretary-General of the OECD. The opinions expressed and arguments employed herein do not necessarily reflect the official views of the Organisation or of the governments of its member countries.

NUCLEAR ENERGY AGENCY

The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the OEEC European Nuclear Energy Agency. It received its present designation on 20th April 1972, when Japan became its first non-European full member. NEA membership today consists of 28 OECD member countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg, Mexico, the Netherlands, Norway, Portugal, Republic of Korea, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities also takes part in the work of the Agency.

The mission of the NEA is:

� to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, as well as

� to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development.

Specific areas of competence of the NEA include safety and regulation of nuclear activities, radioactive waste management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle, nuclear law and liability, and public information. The NEA Data Bank provides nuclear data and computer program services for participating countries.

In these and related tasks, the NEA works in close collaboration with the International Atomic Energy Agency in Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the nuclear field.

© OECD 2006 No reproduction, copy, transmission or translation of this publication may be made without written permission. Applications should be sent to OECD Publishing: [email protected] or by fax (+33-1) 45 24 13 91. Permission to photocopy a portion of this work should be addressed to the Centre Français d’exploitation du droit de Copie, 20 rue des Grands-Augustins, 75006 Paris, France ([email protected]).

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FOREWORD

The Joint Evaluated Fission and Fusion (JEFF) Project is a collaborative effort among the member countries of the NEA Data Bank to develop a reference nuclear data library. The JEFF library contains sets of evaluated nuclear data, mainly for fission and fusion applications; it contains a number of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data and photo-atomic interaction data.

The latest version of the JEFF library, JEFF-3.1, was released by the NEA in May 2005. JEFF-3.1 combines the efforts of the JEFF and EFF/EAF (European Fusion File/European Activation File) working groups who have contributed to this combined fission and fusion library. The neutron general purpose library contains incident neutron data for 381 materials from 1H to 255Fm. The activation library (based on the European Activation File, EAF-2003) contains 774 different targets from 1H to 257Fm. The radioactive decay data library contains data for 3 852 isotopes, of which 226 are stable. The proton special purpose library contains incident proton data for 26 materials from 40Ca to 209Bi. The thermal scattering law library covers 9 materials, and the fission yield library covers 19 isotopes of neutron induced fission yield from 232Th to 245Cm and 3 isotopes with spontaneous fission yields (242Cm, 244Cm and 252Cf).

Acknowledgements

We acknowledge the support and dedication of many colleagues in the nuclear data community in Europe, Japan and the United States without whom this work would not have been possible, in particular: C. Chabert, J-P. Delaroche, H. Derrien, H. Duarte, B. Duchemin, I. Duhamel, A. Filatenkov, E. Fort, F. Froehner, J. Galy, C-S. Gil, W. Haeck, F-J. Hambsch, M. Herman, S. Hilaire, M. Honusek, T. Ivanova, D-H. Kim, N. Larson, P. de Leege, R. MacFarlane, A. Mengoni, L. Mercatali, C. Mihaelescu, W. Mannhart, M.C. Moxon, S. Pelloni, P. Ribon, D. Ridikas, G. Rimpault, J.L. Rowlands, E Simeckova, J. Tommasi, B. Zefran, M. Zmitko, and Harm Gruppelaar, who left us too soon to experience the impact of his work.

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TABLE OF CONTENTS

Foreword ............................................................................................................................................ 3

Introduction ........................................................................................................................................ 7

The general-purpose neutron data library........................................................................................... 8

The need for a new library.......................................................................................................... 8

New evaluations.......................................................................................................................... 8

Thermal scattering law library............................................................................................................ 8

Expected performance relative to JEF-2.2 ......................................................................................... 9

Benchmarking and quality assurance ................................................................................................. 9

Present status .............................................................................................................................. 9

The library format and contents.................................................................................................. 10

Outlook ....................................................................................................................................... 11

Activation library, JEFF-3.1/A........................................................................................................... 11

Summary..................................................................................................................................... 11

Background................................................................................................................................. 11

Library description...................................................................................................................... 11

Radioactive decay data library, JEFF-3.1/RDD ................................................................................. 12

Summary..................................................................................................................................... 12

Data sources available ................................................................................................................ 12

Fission yield libraries, JEFF-3.1/NFY and SFY................................................................................. 13

Proton special-purpose library............................................................................................................ 13

The JEFF Team .................................................................................................................................. 15

References .......................................................................................................................................... 17

Working papers from JEFF meetings 2002-2005............................................................................... 19

JEFF documents.......................................................................................................................... 19

EFF documents ........................................................................................................................... 26

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Tables ................................................................................................................................................. 33

Table 1. Origin of evaluations in the JEFF-3.1 general-purpose neutron data library .............. 35

Table 2. Origin of evaluations in the JEFF-3.1 thermal scattering law library.......................... 48

Table 3. Contents of the JEFF-3.1 general-purpose neutron data library. List of available reactions (MTs) in files MF=3 to MF=6 ...................................................... 49

Table 4. Contents of the JEFF-3.1 general-purpose neutron data library. List of available reactions (MTs) in photon production files MF=12 to MF=15.................... 65

Table 5. Contents of the JEFF-3.1 general-purpose neutron data library. List of covariance data (MF=33to MF=36)............................................................................. 69

Table 6. Resonance data in the JEFF-3.1 general-purpose neutron data library ....................... 71

Table 7. Contents of the JEFF-3.1 thermal scattering law library ............................................. 84

Table 8. Contents of the JEFF-3.1 proton special-purpose library. List of available reactions (MTs) in files MF=3 to MF=6...................................................................... 85

Table 9. Simple integral neutron cross-section data from JEFF-3.1 calculated with the INTER computer code........................................................................................... 86

Available on CD-ROM

Appendix 1. Selection of data for the JEFF-3.1 general-purpose neutron data file

Appendix 2. Performance reports on the JEFF-3.1 general-purpose neutron data library

�eff calculations using JEFF-3.1 nuclear data

Shielding benchmark calculations with MCNP-4c3 using JEFF-3.1 nuclear data

Criticality safety benchmark calculations with MCNP-4c3 using JEFF-3.1 nuclear data

Appendix 3. List of definitions to the ENDF-6 file format for JEFF-3.1

Table A3.1. Definitions of file types (MF)

Table A3.2. Definitions of reaction types (MT)

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Introduction

The objective of the OECD Nuclear Energy Agency (NEA) co-ordinated Joint Evaluated Fission and Fusion (JEFF) data project is to develop and promote the use of high quality evaluated nuclear data sets in standard formats for a wide range of scientific and technical applications. The JEFF project assesses the needs for nuclear data improvements and brings together experts in different areas such as experiments, data evaluations, verification and compilation of the data under strict quality assurance procedures, file processing and benchmarking.

JEFF is a collaborative effort among NEA Data Bank member countries. The project maintains close links with other similar international efforts and projects aimed at producing evaluated nuclear data, for example through active participation in the NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC). While the objective of the JEF-2.2 library (1992) was to achieve improved performance for existing reactors and fuel cycles, its successor, the JEFF-3 project, aims at providing users with a more extensive set of data for a wider range of applications. While existing reactors and fuel cycles remain the essential application areas of the nuclear data library, innovative reactor concepts (Gen-IV systems), transmutation of radioactive waste, fusion, medical applications, and various non-energy related industrial applications are now also envisaged as scientific application areas that will make use of the JEFF data. The European Fusion File (EFF) also contributes to the JEFF project through evaluations and data validation.

Figure 1 illustrates the evolution of the JEFF project, including the latest release of JEFF-3.1. The JEFF-3.1 release consists of the following libraries:

� neutron general-purpose library;

� thermal scattering library;

� neutron activation library;

� decay data library;

� fission yield data library;

� proton special-purpose library.

Figure 1: The evolution of the JEFF project

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The general-purpose neutron data library

The need for a new library

Following the release of the JEFF-3.0 library in April 2002, various benchmark tests have confirmed the expected performance improvements of this general-purpose neutron data library over JEF-2.2. However, they have also shown that the reactivity of small low-enriched uranium systems, relevant to LWR analyses, is underestimated by about 500 pcm when using JEFF-3.0 data. The 238U inelastic, scattering and capture cross-sections have been identified as the possible reasons for this underestimation. A new 238U evaluation has been assembled, resulting in appreciably improved keff values. Subgroup 22 of WPEC has contributed significantly to these improvements. Very extensive automated benchmark tests have been conducted, probing the current quality of the new data library. These benchmark tests include for example criticality calculations performed with MCNP, TRIPOLI and APOLLO for an unprecedented set of benchmark cases. Current-day computer power enables future revisions of the JEFF library to be quickly tested with such benchmarking schemes.

It was decided to adopt an eight-time group representation for delayed neutron data, as suggested by Subgroup 6 of WPEC. It is considered that this representation has two advantages – the longest lived, dominant precursors are explicitly represented and the calculation convenience of having the same set of time constants for all fissioning isotopes.

A final justification for releasing JEFF-3.1 is that there was a desire from the nuclear industry (in particular in France) to start validating the new JEFF library in the fall of 2005.

New evaluations

Another reason to develop the JEFF-3.1 general-purpose neutron data library is that a significant number of isotopes have undergone a major revision over the last few years. This holds both for the general-purpose and the special-purpose libraries. This report contains a table with the justification for the choice of the various isotopes for JEFF-3.1 (see Appendix 1). New evaluations are included for the Ti isotopes (IRK Vienna), the Ca, Sc, Fe, Ge, Pb and Bi isotopes (NRG Petten), 103Rh, 127I, 129I, the Hf isotopes, 236-238U, and 241Am (CEA). For other isotopes, more recent evaluations from other libraries were adopted.

Revised thermal scattering data have been produced for all important moderator and structural materials and this was included in JEFF-3.1.

Various experimental nuclear data activities have taken place during the development of JEFF-3.1. The programme at the nTOF facility at CERN comprised capture and fission cross-section measurements including isotopes of relevance to the thorium fuel cycle and several transuranic isotopes. The measurement programme at IRMM Geel mainly covered neutron data related to waste transmutation and other innovative concepts, as well as basic nuclear physics and standards data.

Thermal scattering law library

The thermal scattering law library contains the following nine evaluations: hydrogen bound in water, zirconium, polyethylene (CH2) and CaH2, deuterium bound on D2O, 9Be, graphite, 24Mg and finally calcium bound in CaH2. All files are new evaluations, except 9Be and hydrogen in polyethylene, which are from the JEFF-3.0 library. Many of the evaluations are the result of an IAEA co-ordinated project on thermal neutron scattering. Calculations for a variety of temperatures were made with the

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LEAPR module of NJOY to obtain thermal scattering data that are accurate over a wider range of energy and momentum transfer. To validate these files on a microscopic level, detailed comparisons with a significant number of measurements of differential and integral neutron cross-sections and other relevant data have been performed. The current models used for these files are able to describe the experimental data reasonably well. The generating and processing chain for the thermal neutron scattering files with NJOY was carefully investigated.

Expected performance relative to JEF-2.2

In the coming years, benchmarking studies will provide quantitative evidence of the JEFF-3.1 library performance with respect to the previous file versions, in particular JEF-2.2. The latter is a “natural” reference, as it has benefited from many years of validation and users’ feedback (see JEF Report 17). However, it is already possible to give some indications or trends concerning the JEFF-3.1 expected impact on fission reactor applications.

For LWR applications, the longstanding JEF-2.2 problem of 236U under-prediction in actinide inventory calculations has been corrected (increase of the 235U epithermal capture cross-section). Similarly, the underestimation of the 242Pu content and correlated 243Am build-up in spent fuel has been fixed (increase of 241Pu capture and decrease of fission near the 0.3 eV resonance). Reactivity predictions for fresh UOX-fuelled cores should be slightly lower than with JEF-2.2, in agreement with measurements. The reactivity of systems containing significant quantities of 27Al will also be improved (higher thermal capture). For MOX cores, however, JEFF-3.1 will yield larger values than JEF-2.2, thus over-predicting reactivity. Individual fission product poisoning effects should be better predicted with JEFF-3.1 as a result of improved capture cross-sections (103Rh, 133Cs, 95Mo, 143Nd, 154Eu, 155Eu, 149Sm). Important thermal fission product yields used for fission rate normalisation have been revised for a better agreement with measurements (increased 235U yield of 137Cs, decrease 239Pu yield of 148Nd).

For fast reactor applications, the reactivity of un-irradiated uranium systems should no longer be overestimated (larger 235U capture). On the other hand, the reactivity of plutonium-fuelled fast reactors should still be underestimated, being even lower than with JEF-2.2 as a result of the changes in the 238U inelastic scattering. 241Pu build-up should be improved (lower 240Pu capture cross-section above 100 eV), as well as the 238Pu, 242Pu, 242Cm and 242mAm produced from 241Am (branching ratio of 0.85, lower capture cross-section above 20 keV). Calculated sodium-void effects should no longer require a posteriori corrections (revised 23Na inelastic and elastic cross-sections). Finally, steel reflector effects should also be better predicted (improved 56Fe and 52Cr scattering cross-sections).

Compared with JEF-2.2, a better agreement between JEFF-3.1-based calculations and measurements is expected in neutron transmission applications containing the following materials: Fe, 16O, 9Be, W, Na.

Initial testing of the JEFF-3.1 file has also indicated that further improvements will be needed, in particular for 237Np capture, 239Pu fission and capture, 242Pu capture, 241Am capture, 56Fe scattering, fission product cross-sections (fast range), decay data and yields of short-lived fission products.

Benchmarking and quality assurance

Present status

Extensive benchmarking of the JEFF-3.1 data library is now under way for both the general-purpose and the special-purpose sub-libraries. In order to avoid further delays in the publication of the present

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report, only results from the extensive benchmarking effort on criticality, effective delayed neutron parameters, and shielding using a Monte Carlo approach (MCNP) are reported on here (see Appendix 2). At a later stage, a wider validation of benchmark results using different methods (deterministic and Monte Carlo), codes and for various integral quantities, can be expected.

A quality assurance procedure has been developed at NEA for the assembly, basic testing and loading of the JEFF-3.1 library into a database. Verifications performed at the loading stage include format checks (CHECKR), physics checks (FIZCON and PSYCHE), processing using different versions of NJOY and graphical comparisons with other data libraries. Specific tools were developed within this framework (e.g. the JANIS data display program and database loading programs) and existing programs (e.g. FIZCON, INTER) were extended to enable more stringent consistency checks.

The library format and contents

Each material in the JEFF-3.1 library is given in the ENDF-6 format. This format stores nuclear data in various sections or files (MF). Each file contains data for different reactions (MT). Appendix 3 gives the list of MF and MT numbers and their meaning in the ENDF-6 format.

Table 1 provides the list of materials in the neutron general-purpose library and the origin of the file. A material corresponds to a nucleus of a single isotope or to a nucleus of a natural element. A nucleus is either in its ground state or in an isomeric state. In the first column of Table 1, the material is represented as ZZZ-SY-AAA where AAA and ZZZ are the atomic charge and mass given as three-digit integers. SY is the symbol of the material represented with two characters. Note that AAA is equal to zero when the material represents a natural element. In addition, when the nucleus is in its first isomeric state, the letter “M” is appended to the end of the column (e.g. 95-Am-242M). The materials are classified in ascending atomic charge order. The second column provides the material number used to identify the isotope or the element in the library. The third column gives the source library from where the data originates. The forth to sixth columns specify the laboratory that performed the evaluation, the date of the evaluation and the authors.

Table 2 provides the same information as Table 1, for neutron thermal scattering data in JEFF-3.1. The following compounds are included: hydrogen bound in water, zirconium, polyethylene (CH2) and CaH2, deuterium bound on D2O, 9Be, graphite, 24Mg and finally calcium bound in CaH2.

Table 3 provides some details concerning the available cross-section data in the general-purpose neutron data library. The first two columns identify the material, and the third column lists the MTs found in file 1 (MF=1, general information). Reactions (MTs) for which cross-section data are available (MF=3, reaction cross-sections) are listed in the forth column. Columns 5 through 7 provide the list of reactions for which angular distributions, energy distributions or energy-angle distributions are given in MF=4, 5 and 6 respectively. Table 4 gives the list of materials for which photon production data is available (MF = 12 to 15) in the general-purpose neutron data library. Table 5 provides information on available covariance data in MF=31 to 36 in the general-purpose neutron data library, and Table 6 gives details on resonance data given in MF=2. The third column of Table 6 states whether resonance data is present, and the forth column gives the formalism used. The remaining columns give details on the resonance parameters in the resolved resonance range (RRR) and the unresolved resonance range (URR) with the energy of the first three s-wave resonances.

Table 7 lists the contents of MF=1 and MF=7 of the thermal scattering law library. Table 8 lists similarly the contents of the proton special purpose library, with information from MF=1, 3 and 6.

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Table 9, finally, gives simple integral neutron cross-section data from the neutron general-purpose library of JEFF-3.1 calculated with the INTER-7.0 computer code. All input parameters are listed as well.

Outlook

For the next release, JEFF-3.2, we foresee more efforts on fission product evaluations, minor actinide evaluations, and inclusion of more covariance data in the files.

Activation library, JEFF-3.1/A

Summary

The activation data library in ENDF-6 format, JEFF-3.1/A, is based on the European Activation File (EAF-2003). The JEFF-3.1/A library contains 12 617 excitation functions involving 774 different targets from 1H to 257Fm, atomic numbers Z=1 to Z=100, in the energy range 10–5 eV to 20 MeV. Uniquely, an uncertainty file is also provided that quantifies the degree of confidence placed in the data for each reaction channel.

Background

Calculations of the activation of materials, arising from the operation of fusion devices producing large fluxes of neutrons from the D-T reaction, play an important role in fusion technology studies. In order to have confidence in the results of such calculations, it is necessary that the inventory code and the data libraries be thoroughly validated. This is accomplished by comparing the predictions of the code system with activation measurements made on materials relevant to fusion technology in well-characterised neutron fields.

The European Activation File (EAF) project has been an ongoing process performed through European and world-wide co-operation, leading to the creation of successive EAF versions. The EAF-2003 release [1] has benefited from the generation and maintenance of comprehensive activation files and the development of the new processing code SAFEPAQ-II [2]. Therefore, the JEFF project has adopted this version of the activation files for the JEFF-3.1/A library.

Library description

The EAF nuclear data library has been developed as part of the European Fusion Development Agreement (EFDA) Fusion Technology Programme. A series of measurements on fusion-relevant materials in several complementary neutron fields have been carried out over the last few years. In addition, analyses of measurements, carried out outside Europe and outside the fusion programme, have been undertaken.

Cross-section validation exercises, performed against both experimental data and systematics, enable a comprehensive assessment of the data. The SAFEPAQ-II software is used to apply a series of modifications to the original source data. A very important set of modifications concerns re-normalisation and branching using experimental or systematic data. A total of 3 225 reactions (26% of all the reactions) have thus been changed. This is a challenging task as the source contains non-threshold reactions with an energy-dependent branching ratio.

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Validation using integral data has been performed by means of direct comparison with measurements of sample materials under fusion-relevant neutron spectra. Irradiations have been carried out at ENEA FNG, FZK Isochron-cyclotron, Sergiev Posad SNEG-13 and JAERI FNS and integral C/E comparisons made (C/E is the ratio of the library value to the experimental value). The results of these benchmark exercises, in concurrence with differential data, have indicated where modifications to the data should be applied.

The results from the experiments used to validate the activation data are presented in a series of tables in Ref. [3], including the pathways responsible for production of the various radionuclides. In cases where a single pathway dominates, it is possible to extract the effective cross-section for the reaction and compare this with the library value calculated in the same neutron spectrum. About 290 reactions from the JEFF-3.1/A library are plotted in the reference. The graphs include uncertainty estimates as well as experimental differential data from the EXFOR database. C/E graphs showing the available integral data are also given and, using these graphs, a statement is made indicating whether the EAF data are consistent with the experimental data or whether changes to data would be needed. It should be noted that most of the measurements were carried out with fusion-relevant materials, resulting in small uncertainties for activities produced in major nuclides, but larger uncertainties for activities produced in minor nuclides or impurities.

Radioactive decay data library, JEFF-3.1/RDD

Summary

Radioactive decay data forms an integral part of the nuclear data requirements for nuclear applications. The JEFF-3.1 decay data library contains 3 852 nuclides from neutron to 272Rg. The decay data sub-group of the JEFF Project decided that a completely new start should be made in the construction of this library compared to the previous versions. The JEFF-3.1/RDD library is described in detail in JEFF Report 20 [4]. Some background information concerning the evolution of the project is provided below.

Data sources available

The basis for the selection of isotopes were taken from the NUBASE-2003 file [5], which contains basic nuclear properties, hence all known isomers were identified from here. Three evaluated libraries, from within Europe, were used to replace individual NUBASE files, for almost 600 nuclei in all. Two libraries originated from the UK (UKPADD-6.4 and UKHEDD-2.4) [7] and the third from the Decay Data Evaluation Project (DDEP) [8] conducted by the Laboratoire National Henri Bequerel (LNHB) at Saclay, France.

Files were also selected from the ENSDF library [9] – these files contain decay data derived from basic nuclear structure data. Approximately 900 nuclei, containing sufficient data to allow calculation of their energy balance to a consistency of better than 1%, were selected from ENSDF.

The JEFF-3.1 library stores all data in the internationally-accepted ENDF-6 format [6]. Recent enhancements, allowing the storage of basic nuclear properties for stable nuclei (i.e. spin and parity), have been adopted in this library. The isotopic abundances for all appropriate nuclei (taken from NUBASE-2003) have been added as the last line in the comments section (MF=1, MT=451) whilst an unused field in the format is investigated.

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Throughout the compilation process the library has followed NEA quality assurance procedures and been checked with the standard ENDF utility codes STANEF, CHECKR and FIZCON [10]. Significant enhancements to the FIZCON code have been added for the verification of decay data [11] and minor corrections to the latest versions (7.00/7.01) have also been implemented following problems noted in checking this JEFF library, most notably the checking of the symbol field for meta-stable states and the inclusion of stable nuclei. Users should be warned that earlier versions of the checking codes, e.g. version 6.11, should not be used in testing this library.

Fission yield libraries, JEFF-3.1/NFY and SFY

The fission product yield libraries include independent and cumulative yields for neutron-induced fission of 232Th, 233,234,235,236,238U, 237,238Np, 238,239,240,241,242Pu, 241,242m,243Am, 243,244,245Cm and spontaneous fission of 242,244Cm and 252Cf. The data represent a development of the UKFY3 file described in Ref. [12], which was itself developed from earlier UK evaluations described in Refs. [13-15].

The principle changes from earlier libraries include an extended experimental database, calculation of the cumulative yields using the JEFF-3.1 decay data, improved calculation of uncertainties in the yields, improved adjustment to the physical constraints and the inclusion of new ternary yield data for 3H and 4He from Serot, Wagemans, et al. [16].

Proton special-purpose library

The proton special purpose library consists of 26 evaluated isotopes. The data are based primarily on a theoretical analysis with the nuclear model code TALYS [17]. The nuclear model parameters of TALYS have been adjusted to reproduce the existing experimental data. For several materials that are of key importance to transmutation programs (ADS), valuable experimental data was provided by the EU FP5 HINDAS project. Together, this results in data files that provide a complete representation of nuclear data needed for transport, damage, heating, radioactivity and shielding applications over the incident proton energy range from 1 to 200 MeV. This collection of isotopic evaluations is created by running TALYS with input parameters that do not, or only slightly, deviate from the default values.

These isotopic evaluations are thus of comparable quality. The same set of nuclear models is used and, equally important, the same ENDF-6 formatting procedures for each isotope. These data files are complete in their description of reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides are filed using a combination of MF=1, MF=3 and MF=6. This includes cross-sections, angular distributions, double-differential spectra, photon production cross-sections, and residual production (activation) cross-sections. These evaluations can thus be used as both transport and activation libraries.

The files have been checked by the BNL checking codes CHECKR, FIZCON and PSYCHE and have been successfully processed into an MCNP library by the processing code NJOY.

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THE JEFF TEAM

The following scientists and institutes have contributed to the successful release of the JEFF-3.1 nuclear data libraries.

Chairs

O. Bersillon (Decay Data), R.A. Forrest (EFF) and A.J. Koning (JEFF)

Evaluation

O. Bouland (CEA), A. Courcelle (CEA), M.C. Duijvestijn (NRG), E. Dupont (CEA), J. Kopecky (JUKO), D. Leichtle (FZK), F. Marie (CEA),

M. Mattes (Stutt), E. Menapace (ENEA), B. Morillon (CEA), C. Mounier (CEA), G. Noguerre (CEA), P. Pereslavtsev (FZK),

P. Romain (CEA), O. Serot (CEA), S. Simakov (FZK), S. Tagesen (IIK), H. Vonach (IIK)

Experimental nuclear data

P. Batistoni (ENEA), P. Bem (Rez), F. Gunsing (CEA), M. Pillon (ENEA), A. Plompen (IRMM), P. Rullhusen (IRMM), K. Seidel (TUD)

Nuclear modelling and theory

M. Avrigeanu (NIP), V, Avrigeanu (NIP), E. Bauge (CEA), H. Leeb (TUW), M.J. Lopez Jimenez (CEA)

Processing, benchmarking and validation

D. Bernard (CEA), A. Bidaud (CEN), R. Dagan (FZK), C. Dean (Serco), P. Dos-Santos-Uzarralde (CEA), U. Fischer (FZK), A. Hogenbirk (NRG), R. Jacqmin (CEA),

C. Jouanne (CEA), I. Kodeli (IAEA), J. Leppanen (VTT), S.C. van der Marck (NRG), R. Perel (RIP), R. Perry (Serco), M. Pescarini (ENEA), A. Santamarina (CEA), J-C. Sublet (CEA), A. Trkov (IAEA)

Decay data and fission yields

M.M. Be (CEA), T.D. Huynh (CEA), M.A. Kellett (IAEA), R. Mills (Nexia), A. Nichols (IAEA)

NEA Data Bank

H. Henriksson, C. Nordborg, A. Nouri, Y. Rugama, E. Sartori

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Participating institutions

Technische Universitaet Wien (TUW), Vienna, Austria Institut fuer Isotopenforschung und Kernphysik (IIK), Vienna, Austria

Nuclear Physics Institute Rez (Rez), Czech Republic VTT Processes (VTT), Finland

Commisariat à l’Énergie Atomique (CEA) Bruyères-le-Chatel, France Commisariat à l’Énergie Atomique (CEA) Cadarache, France

Commisariat à l’Énergie Atomique (CEA) Saclay, France CEN de Bordeaux (CEN), France

Forschungszentrum Karlsruhe (FZK), Germany Stuttgart University (Stutt), Germany

Technische Universitaet Dresden (TUD), Germany Racah Institute of Physics (RIP), Jerusalem, Israel

National Agency for New Technology, Energy and the Environment (ENEA), Italy Nuclear Research and Consultancy Group (NRG), Petten, the Netherlands

JUKO Research (JUKO), Alkmaar, the Netherlands National Institute of Physics and Nuclear Engineering (NIP), Bucharest, Romania

UK Atomic Energy Authority Fusion (UKAEA), Abingdon, United Kingdom Nexia Solutions Ltd., Seascale (Nexia), United Kingdom

Serco Assurance (Serco), Winfrith, United Kingdom

International organisations

Institute for Reference Materials and Measurements (JRC/IRMM) International Atomic Energy Agency (IAEA)

Nuclear Energy Agency (OECD/NEA) Data Bank

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REFERENCES

[1] Forrest, R.A., J. Kopecky, J-Ch. Sublet, The European Activation File: EAF-2003 Cross-section Library, UKAEA Report UKAEA FUS 486, Dec. 2002.

[2] Forrest, R.A., SAFEPAQ-II User Manual, UKAEA report UKAEA FUS 454, Issue 6, Jan. 2005.

[3] Forrest R.A., M. Pillon, U. von Möllendorff, K. Seidel, J. Kopecky, J-Ch. Sublet, Validation of EASY-2003 Using Integral Measurements, UKAEA report UKAEA FUS 500, Dec. 2003.

[4] JEFF Report 20, The JEFF-3.1 Decay Data and Fission Yields Libraries, OECD Nuclear Energy Agency, forthcoming.

[5] Audi, G., O. Bersillon, J. Blachot, A.H. Wapstra, “The NUBASE Evaluation of Nuclear and Decay Properties”, Nucl. Phys. A, 729, 3-128 (2003).

[6] McLane, V., ENDF-102: Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6, BNL-NCS-44945-01/04-Rev., April 2001.

[7] Nichols, A., UKHEDD-2.4 and UKPADD-6.4.

[8] Bé, M.M., E. Browne, V. Chechev, V. Chisté, R. Dersch, C. Dulieu, R.G. Helmer, N. Kuzmenco, A.L. Nichols, E. Schönfeld, Nucléide, Table de Radionucléides sur CD-Rom, Version 2-2004, http://www.nucleide.org/NucData.htm.

[9] Tuli, J.K., The Evaluated Nuclear Structure Data file (ENSDF), BNL-NCS-51655 Rev. 87, April 1987.

[10] Dunford, C., ENDF Utility Checking Codes, 7.01, Brookhaven National Laboratory, Upton, NY, USA.

[11] Perry, R., C.J. Dean, FIZCON Enhancements, UKNSF report.

[12] Mills, R.W., Fission Product Yield Evaluation, Thesis, University of Birmingham, UK (1995).

[13] James, M.F., R.W. Mills, D.R. Weaver, UKFY2 Part 1: Methods and Outline, AEAT report, AEA-TRS-1015 (1991).

[14] James, M.F., R.W. Mills, D.R. Weaver, UKFY2 Part 2: Tables of Measured Data, AEAT report, AEA-TRS-1018 (1991).

[15] James, M.F., R.W. Mills, D.R. Weaver, UKFY2 Part 3: Tables of Discrepant Data, AEAT report, AEA-TRS-1019 (1991).

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[16] Serot, O., C. Wagemans, Jan Heyse “New Results on Helium and Tritium Gas Production From Ternary Fission”, Proceedings of the International Conference on Nuclear Data for Science and Technology, R.C. Haight, M.B. Chadwick, T. Kawano, P. Talou (eds.), American Institute of Physics, ISBN 0-7354-0254-X/05, CP769, 857 (2005).

[17] Koning, A.J., S. Hilaire, M.C. Duijvestijn, “TALYS: Comprehensive Nuclear Reaction Modeling”, Proceedings of the International Conference on Nuclear Data for Science and Technology, R.C. Haight, M.B. Chadwick, T. Kawano, P. Talou (eds.), American Institute of Physics, ISBN 0-7354-0254-X/05, CP769, 857 (2005).

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WORKING PAPERS FROM JEFF MEETINGS 2002-2005

The papers listed below were presented at the JEFF working group meetings from April 2002 until November 2005. The papers are for internal use within the JEFF group, and can therefore only be requested from the NEA and distributed after permission from the authors. The papers are considered as non-official publications having draft status.

JEFF documents

JEF/DOC-1125 ALEPH-DLG 1.1.0 Creating Cross-section Libraries for MCNP(X) and ALEPH, W. Haeck, B. Verboomen

JEF/DOC-1124 Thermal Neutron Scattering Data at Low Temperatures, M. Mattes JEF/DOC-1123 Sensitivities of keff Calculated with Monte Carlo Methods: Theory and First Results,

R. Perel JEF/DOC-1122 Qualification of JEFF-3.1 Evaluations: LWR Reactivity and Fuel Inventory

Prediction, D. Bernard JEF/DOC-1121 Assessing Uncertainties in the Continuum Region with the Backward-forward

Monte Carlo Method: Example n+89Y Evaluation, E. Bauge JEF/DOC-1120 Documentation for the JEFF-3.1 Decay Data Library, M. Kellett JEF/DOC-1119 Recently Launched IAEA Nuclear Data Section Projects, M. Kellett JEF/DOC-1118 TRIPOLI-4.4 Benchmarks, C. Jouanne JEF/DOC-1117 Photonuclear Data Evaluation of Uranium-235, I. Raskinyte JEF/DOC-1116 Experimental Activities at n_TOF CERN, F. Gunsing JEF/DOC-1115 Fission Products for BUC Applications, L. Leal JEF/DOC-1114 Present Status of JEFF-3.1 Benchmarking with ERANOS-2.0, J. Tommasi JEF/DOC-1113 Status of 238U Resolved and Unresolved Evaluation and Impact of JEFF-3.1 in

Burn-up Calculation, A. Courcelle JEF/DOC-1112 TRIPOLI-4.4 – JEFF-3.1 & ENDB/B-VII b1 with the ICSBEP Criticality Models,

J-Ch. Sublet, C. Jouanne, Y. Peneliau, F-X. Hugot JEF/DOC-1111 ECCOLIB-JEFF-3.1 Libraries, J-Ch. Sublet, C.J. Dean, D. Plisson-Rieunier JEF/DOC-1110 Analysis of New Data for Hydrogen Bound in Zirconium Introduced in TRIGA

Cores, R. Dagan JEF/DOC-1109 Validation of the JEFF-3.1 Fission Yields and Decay Data by Decay Heat and

Fission Product Inventories, R. Mills JEF/DOC-1108 Benchmark Calculations for Fast Reactors Using JEFF-3.1, ENDF/B-VII and

JENDL-3.3, D-H. Kim JEF/DOC-1107 Criticality Safety Benchmark Calculations with MCNP-4C3 Using JEFF-3.1

Nuclear Data, S. Van der Marck JEF/DOC-1106 Shielding Benchmark Calculations with MCNP-4C3 Using JEFF-3.1 Nuclear Data,

S. Van der Marck JEF/DOC-1105 Beta-eff Calculations Using JEFF-3.1 Nuclear Data, S. Van der Marck JEF/DOC-1104 Experimental Activities at IRMM, P. Rullhusen

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JEF/DOC-1103* Review of Spectral Data for Important Nuclides in JEFF-3.1 Decay Data Files, C. Dean

JEF/DOC-1103 Review of Spectral Data for Important Nuclides in JEFF-3.1 Decay Data Files, C. Dean

JEF/DOC-1102 Proposal for an Optimized European Multigroup Mesh: The SHEM-281g Mesh, A. Santamarina

JEF/DOC-1101 The New OECD-NEA High Priority Request List for Nuclear Data, A. Plompen JEF/DOC-1100 Neutron (n,xn?) Cross-section Measurements for 52Cr, 209Bi and 206,207,208Pb from

Threshold Up to 20 MeV, C. Mihailescu JEF/DOC-1099 Verification and Validation of a Multi-temperature JEFF-3.1 Library for MCNP(X),

W. Haeck JEF/DOC-1098 Minutes of the Meeting of the Sub-group on Decay Data and Fission Yields,

May 2005, Y. Rugama JEF/DOC-1097 Minutes JEFF Meeting, May 2005, Y. Rugama JEF/DOC-1096 Impact of Nuclear Data Uncertainties on a GEN IV-Thorium-reactor at

Equilibrium. Proposition of an Update of the High Priority List, A. Bidaud JEF/DOC-1095 Analysis of MASURCA-1A�/-1B Experiments, J. Tommasi, R. Jacqmin JEF/DOC-1094 Recent Activities on Innovative Radionuclide Production for Metabolic

Radiotherapy and PET and on Relevant Experimental and Evaluated Nuclear Data, E. Menapace

JEF/DOC-1093 JEFF: The Next Twenty Years?, M. Salvatores JEF/DOC-1092 Some Questions Related to Data Accuracies and Covariances, H. Weigmann JEF/DOC-1091 The Development of Nuclear Data Libraries in Western Europe and the JEF Project,

J. Rowlands JEF/DOC-1090 JEFF-3.1 Decay Data and Pulse Fission calculations, Huynh T.D. JEF/DOC-1089 A New Neutron + 235U Evaluation from 2.25 keV Up to 30 MeV, P. Romain,

B. Morillon JEF/DOC-1088 A New Neutron-deuterium Data Evaluation, R. Lazaukas JEF/DOC-1087 JENDL-3.3 and JEFF-3.1 NJOY99.90 Deterministic Code Module Updates,

J-Ch. Sublet, K. Kosako JEF/DOC-1086 Revised Evaluation of the 241Am Isotope, O. Bouland, D. Bernard JEF/DOC-1085 Summary Record of the JEFF Scientific Co-ordination Group Meeting, NEA

Secretariat JEF/DOC-1084 TRIPOLI-4.4 & JEFF-3.1, ENDF/B-VII b0 and JENDl-3.3 with the ICSBEP

Criticality Models, J-Ch. Sublet, C. Jouanne, Y. Peneliau, F-X. Hugot JEF/DOC-1083 COGEND: A Code to Generate Nuclear Decay Scheme Data in ENDF-6 Format,

R.J. Perry, C.J. Dean JEF/DOC-1082 Update of Previous LWR Cross-section Library Comparison Calculations at VTT,

J. Leppanen JEF/DOC-1081 COGEND: Improvements to the Processing of Continuous Spectra, R.J. Perry JEF/DOC-1080 Comparisons Between JEFF31 and JEF-2, C. Mounier JEF/DOC-1079 Brief Report on 95Mo, 99Tc and 245Cm: JEFF-3.1 Status, O. Serot JEF/DOC-1078 Comparative Study of Certain Aspects of the JENDL3.3, JEF-2.2 (UKFY2) and

JEFF-3.1 (UKFY3.6) Fission Yields files, O. Serot JEF/DOC-1077 Low Neutron Cross-sections of the Hafnium Isotopes, G. Noguere JEF/DOC-1076 Neutron Data Evaluation of Iodine-127 and Iodine-129 Isotopes, E. Dupont,

G. Noguere, E. Bauge JEF/DOC-1075 ORNL-CEA Evaluation of 238U Resonance Parameters Up to 20 keV, A. Courcelle

* Presentation.

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JEF/DOC-1074 New Evaluation of 238U Cross-section in the Unresolved Range (20 keV-150 keV), A. Courcelle

JEF/DOC-1073 Delayed Neutron Yield and Relative Abundance Data for some Minor Isotopes, Missing from Current Compilations, J. Rowlands

JEF/DOC-1072 Assessment and Evaluation of Decay Data for EAF-2004/05, A.L. Nichols, R.J. Perry

JEF/DOC-1071 Comparison of Fission and Radiative Capture Cross-section Data for 235U and 238U, M. Venhart

JEF/DOC-1070 Initial Bechmarking of the JEFF-3.1 Fission Yields and Decay Data, R. Mills JEF/DOC-1069 Test of JEFF-3.1 with MCNP: Criticality and Beta-effective Benchmarks,

A. Hogenbirk JEF/DOC-1068 VALDUC with JEFF-3.1T4 235U and 238U, C. Dean, R.J. Perry JEF/DOC-1067 Status of the Photonuclear Activation File (PAF): Reaction Cross-sections, Fission

Fragments and Delayed Neutron, D. Ridikas JEF/DOC-1066 Recent Activities of the IAEA Nuclear Data Section, M. Kellett JEF/DOC-1065 The JEFF-3.1 Decay Data Library, M. Kellett JEF/DOC-1064 Experimental Activities at IRMM, P. Rullhusen JEF/DOC-1063 Proposal for Nuclear Data Dispersion Matrix, G. Palmiotti, M. Salvatores, Argonne

National Laboratory JEF/DOC-1062 Systematic Comparison of Evaluated Nuclear Data Files, J. Leppanen JEF/DOC-1061 Evaluation of the Resonance Region for 58Fe, M.C. Moxon JEF/DOC-1060 Theoretical Models and Relevant Calculations of Photon Production and

Photonuclear Reaction Data, E. Menapace, G. Maino, F. Groppi JEF/DOC-1059 Comparison Between Theoretical Calculation and Experimental Results of

Excitation Functions for Production of Relevant Biomedical Radionuclides, E. Menapace,C. Birattari, M.L. Bonardi, F. Groppi, S. Morzenti, C. Zona

JEF/DOC-1058 Sensitivity and Uncertainty Analysis of a Thorium Molten Salt Reactor, A. Bidaud JEF/DOC-1057 Current Projects of the IAEA-NDS, A. Trkov JEF/DOC-1056 Short comments on the resolved range of 166Er and 167Er in JEFF-3.0: Proposals for

JEFF-3.1, A. Courcelle, C. Chabert, O. Serot JEF/DOC-1055 Review of the Most Reactor Relevant Fission Product Cumulated Yields, O. Serot,

B. Roque, A. Santamarina JEF/DOC-1054 Progress on 99Tc Evaluation, F. Gunsing, O. Serot JEF/DOC-1053 Thermal Neutron Scattering Cross-section for H in CaH2 and Ca in CaH2, O. Serot JEF/DOC-1052 56Fe Benchmarking Results, R. Jacqmin JEF/DOC-1051 Benchmark Results for 233U and Thorium, S. van der Marck JEF/DOC-1050 Proposal for a Revised 241Am Evaluation in JEFF-3.1, O. Bouland, A. Santamarina JEF/DOC-1049 Proposal for General Purpose Library JEFF-3.1T, A. Koning, J-Ch. Sublet JEF/DOC-1048 Assembly and Feedback of the JEFF-3.0T3 Radioactive Decay Data File,

M. Kellett JEF/DOC-1047 A Survey on Nuclear Data Status and Needs for Special Purposes, Following Items

Discussed in Previous JEFF Meetings and NEA-NSC Workshop on “R&D Needs”, E. Menapace

JEF/DOC-1046 JEFF Meeting Presentation, I. Kodeli JEF/DOC-1045 VALDUC with JEFF-3.1 Hydrogen, C. Dean, S. Connolly JEF/DOC-1044 TRIPOLI4.3 Benchmarks, C. Jouanne JEF/DOC-1043 JEFF-3.0/JEF-2 Improvement on Fuel Inventory Prediction. Trends from Integral

Experiments and Proposal for JEFF-3.1 Evaluations, D. Bernard JEF/DOC-1042 Summary Record of the JEFF Scientific Co-ordination Group Meeting, NEA

Secretariat JEF/DOC-1041 Summary Record of the Joint JEFF/EFF/EAF Meeting, NEA Secretariat

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JEF/DOC-1040 Summary Record of the Decay Data and Fission Yields Meeting, NEA Secretariat JEF/DOC-1039 LWR Cross-section Library Comparison Calculations at VTT, J. Leppanen JEF/DOC-1038 From JEFF-3.0 to JEFF-3.1T: The Way Forward, A. Koning, J-Ch. Sublet JEF/DOC-1037 Report from the CSEWG Meeting, A. Koning JEF/DOC-1036 Overview of the 238U Evaluation in the Resolved Resonance Range, H. Derrien,

A. Courcelle, L. Leal, N. Larson JEF/DOC-1035 Experimental Activities at IRMM, P. Rullhusen JEF/DOC-1034 ICSBEP JEFF-3.1T Benchmarkings: Preliminary Results, J-Ch. Sublet, C. Jouanne,

Y. Peneliau JEF/DOC-1033 On the Use of S(�,�) Tables for Isotopes with Pronounced Resonances, R. Dagan JEF/DOC-1032 Benchmarking of Uranium-238 Evaluations Against Spherical Transmission and

(n,xn)-reaction Rxperimental Data, S. Simakov (presented at ND2004) JEF/DOC-1031 Status of the UKFY3 Fission Yield Evaluation December 2004, R. Mills JEF/DOC-1030 Use of JEFF-3T3 Decay Data with FISPACT-2003, R. Forrest JEF/DOC-1029 Status of UK Decay Data Evaluations, C. Dean JEF/DOC-1028 Comparison of Evaluated Data Libraries: “Chosen Physical Constants of Chosen

Nuclides in Spent Fuel”, M. Venhart, V. Chrapciak, Comenius University Bratislava, Department of Nuclear Physics and Biophysics, Study in Diploma Thesis

JEF/DOC-1027 The Testing of Recent JEF(F) Decay Data and Fission Product Yields Files for Irradiated Nuclear Fuel Decay Heat Calculations, Drs. R.W. Mills, D.R. Parker, BNFL Sellafield

JEF/DOC-1026 Experimental Validation of the APOLLO2 Code for High Burn-up MOX Fuels. JEF-2.2 Results and JEFF-3.0 Improvements, D. Bernard, et al.

JEF/DOC-1025 Summary Record of the Joint JEFF/EFF/EAF Meeting, 11-12 May 2004, A. Nouri JEF/DOC-1024 Summary Record of JEFF Scientific Co-ordination Group Meeting, 12 May 2004,

A. Nouri JEF/DOC-1023 Recent Nuclear Data Activities at the IAEA Nuclear Data Section, A. Trkov JEF/DOC-1022 Summary Record of the Decay Data and Fission Yields Meeting, 10 May 2004,

A. Nouri JEF/DOC-1021 Thermal Neutron Scattering Data, M. Mattes, J. Keinert JEF/DOC-1020 Working Group Experimental Activities, P. Rullhusen JEF/DOC-1019 Experimental Activities at IRMM, Activity Report May 2004, P. Rullhusen JEF/DOC-1018 Implementation of the Delayed Neutron Data Recommendation, A. Nouri JEF/DOC-1017 Benchmarking pre-JEFF-3.1 238U, S.C. van der Marck JEF/DOC-1016 New Evaluations for All Ca and Ge Isotopes, M.C. Duijvestijn, A.J. Koning JEF/DOC-1015 New Data Evaluations for the Fe isotopes, A.J. Koning, M.C. Duijvestijn JEF/DOC-1014 Evaluation of 238U Resonance Parameters from 0 to 20 keV, H. Derrien,

A. Courcelle, et al. JEF/DOC-1013 238U Effective Capture Integral Calculations Using Recent Resonance Parameters

Sets, A. Courcelle JEF/DOC-1012 JEFF-3.0 Based APOLL02 Library – Processing and Validation, S. Mengelle JEF/DOC-1011 JEFF-3.0 Feedbacks – Pre-JEFF-3.1 Proposals, J-Ch. Sublet, B. Roque, F. Laugier,

J. Tommasi JEF/DOC-1010 TRIPOLI-4.3 JEFF-3.0, Pre-JEFF-3.1 Benchmarkings, J-Ch. Sublet, C. Jouanne,

Y. Peneliau JEF/DOC-1009 Testing of BRC 238U Evaluations with Fast Benchmarks, E. Dupont, B. Morillon,

P. Romain, J-Ch. Sublet JEF/DOC-1008 JEF-2.2 and JEFF-3.0 Comparison: Prediction of Isotopic Concentrations and

Reactivity for Thermal Lattices Configurations, A. Courcelle, D. Bernard, A. Santamarina

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JEF/DOC-1007 First Conclusions of the WPEC/Subgroup-22 Nuclear Data for Improved LEU-LWR Reactivity Predictions, A. Courcelle, et al.

JEF/DOC-1006 Mg Thermal Neutron Scattering Cross-sections, C. Mounier JEF/DOC-1005 CaHx Thermal Neutron Scattering Cross-sections, O. Serot JEF/DOC-1004 Neutron Data Evaluation of Rhodium, E. Dupont, E. Bauge, S. Hilaire, A. Koning JEF/DOC-1003 On the Importance of the New Formula for the Double Differential Scattering

Kernel, R. Dagan JEF/DOC-1002 Final results of the Evaluation of All Important Neutron Induced Reactions on

46,47,48,49,50Ti Including Full Covariance Information, S. Tagesen, H. Vonach JEF/DOC-1001 Motivation for New Measurements on Am Isotopes, O. Bouland JEF/DOC-1000 Comparative Study of the Independent Fission Yields in JEF-2.2 (UKFY2) and

JEFF3T2 (UKFY 3.4), O. Serot, R. Mills JEF/DOC-999 Progress on the Production of UKFY3.5, R. Mills JEF/DOC-998 Modifications to COGEND to Process �-n and �-� Decay Data, R. Perry JEF/DOC-997 COGEND: A Code to Generate Nuclear Decay Scheme Data in ENDF-6 Format,

R. Perry, C. Dean JEF/DOC-996 JEFF-3.0/DD T3 Library – Assembly and First Verification, M.A. Kellett,

O. Bersillon JEF/DOC-995 Summary Record of the JEFF Scientific Co-ordination Group, 19 Nov. 2003,

A. Nouri JEF/DOC-994 Summary Record of the Joint JEFF/EFF/EAF Meeting, 18-19 Nov. 2003, A. Nouri JEF/DOC-993 Summary Record of the JEFF Experimentalist Sub-group Meeting, 17 Nov. 2003,

A. Nouri JEF/DOC-992 Summary Record of the Sub-group on Decay Data and Fission Yields,

17 Nov. 2003, A. Nouri JEFDOC-991 Status of Decay Data Evaluations, M.A. Kellett, C.J. Dean JEFDOC-990 Status of UK Decay Data Evaluations, C.J. Dean JEFDOC-989 Measurement Needs for Thermal Reactor Applications: A Short List, Nov. 2003,

A. Courcelle JEFDOC-988 New Nuclear Data Libraries for Pb and Bi, November 2003, A.J. Koning,

M.C. Duijvestijn, R. Klein Meulekamp, S. van der Marck, A. Hogenbirk JEFDOC-987 First Validation of the New BRC 238U Evaluated File, November 2003,

M.J. Lopez Jimenez. JEFDOC-986 Iodine-127 and Iodine-129 Neutron Capture and Total Cross-sections from 0.5 eV

to 100 keV for Nuclear Waste Transmutation Studies, New version from Jan. 2005, G. Noguère, A. Brusegan, A. Leprêtre, N. Hérault, E. Macavero, O. Bouland, G. Rudolf

JEFDOC-985 Experimental Activities at IRMM, Nov. 2003, P. Rullhusen JEFDOC-984 Impressions from the CSEWG Meeting, Nov. 2003, A. Koning JEFDOC-983 ENDF-6 Formatted Neutron Activation File Improvements, November 2003,

P. Dos-Santos-Uzarralde, J-Ch. Sublet JEFDOC-982 The JEFF-3.0/A Neutron Activation File, Nov. 2003, J-Ch. Sublet, A.J. Koning,

R.A. Forrest, J. Kopecky JEFDOC-981 Milestones for the Development of the JEFF-3 Decay Data File, Nov. 2003,

O. Bersillon JEFDOC-980 Experimental Test of the Crystal Lattice Model of the R-Matrix Code SAMMY,

Nov. 2003, A. Courcelle, et al. JEFDOC-979 Summary Report of the WPEC/Subgroup-22 “Nuclear Data for LEU-LWR

Reactivity Prediction”, Nov. 2003, A Courcelle, et al. JEFDOC-978 Improvements of Isotopic Ratios Prediction Through Takahama-3 Chemical

Assays with the JEFF-3.0 Nuclear Data Library, Nov. 2003, A. Courcelle, et al.

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JEFDOC-977 JEF-2.2 Nuclear Data Statistical Adjustment Using Post-irradiation Experiments, Nov. 2003, A. Courcelle, et al.

JEFDOC-976 Delayed Neutron Data in 8 Time Groups, Nov. 2003, J.L. Rowlands JEFDOC-975 Spectral Index Calculations for Dimple, TRX, Proteus, Godiva, Jezebel and Skidoo,

Nov. 2003, S.C. van der Marck, A. Hogenbirk JEFDOC-974 Criticality Results for Many Benchmark Cases – The Releases JEFF-3.0, ENDF-B/

VI.8, JENDL-3.3, and ENDF-B/VII-prelim, Nov. 2003, S.C. van der Marck, A. Hogenbirk

JEFDOC-973 Benchmark Results for the Effective Delayed Neutron Fraction, Nov. 2003, S.C. van der Marck, R. Klein Meulekamp

JEFDOC-972 The Thermal Activation Cross-section of 58Fe, May 2003, M. Moxon JEFDOC-971 Summary Record of the April 2003 JEFF SCG Meeting, A. Nouri JEFDOC-970 Summary Record of the April 2003 JEFF Meeting, A. Nouri JEFDOC-969 Summary Content of the JEFF-3.0 General Purpose Library, April 2003, A. Nouri JEFDOC-968 235U Evaluations Used in Molten Salt Project (MOST), April 2003, Kophazi,

Szieberth, Fehér, de Leege JEFDOC-967 JEFF-3.0 Feedback: Status April 2003, A. Nouri JEFDOC-966 Comparison of Thermal Cross-sections and Resonance Integrals for Dosimetry

Reactions, April 2003, A. Trkov JEFDOC-965 Investigation of 238U Inelastic Data from JEF-2.2, JEFF-3.0, ENDF/B-VI.2 and

ENDF/B-VI.8, April 2003, O. Litaize, O. Serot, E. Dupont JEFDOC-964 Brief Report on 99Tc: Status and Recommendation, April 2003, O. Serot,

F. Gunsing JEFDOC-963 Progress on 52Cr Inelastic Scattering and Zr Activation Cross-sections, April 2003,

A. Plompen JEFDOC-962 Modifications to COGEND, April 2003, R. Perry JEFDOC-961 Further Analysis of JEFF-3T2 Decay Data Using FIZCON, April 2003, R. Perry,

C. Dean JEFDOC-960 Installation and Testing of FIZCON6.13, April 2003, R. Perry JEFDOC-959 Specification and Maintenance Document for Decay Data Checking in FIZCON,

April 2003, M. Grimstone, R. Perry, C. Dean JEFDOC-958 Preliminary Testing of the JEFF-3T2RDD Decay Data Starter File, April 2003,

R. Forrest JEFDOC-957 Nuclides of Importance to Decay Heat Calculations, April 2003, R. Mills JEFDOC-956 Preliminary Analysis of JEFF-3.0 vs. JEF-2 Trends in Fast Spectrum Experiments,

April 2003, E. Dupont JEFDOC-955 Criticality Benchmark Results – The New Releases JEFF-3.0, ENDF/B-VI.8 and

JENDL-3.3, April 2003, S. van der Marck, A. Hogenbirk JEFDOC-954 Needs for 238U Cross-section Measurements to Improve LWR Reactivity Prediction,

April 2003, A. Courcelle JEFDOC-953 Analysis of Hellstrand Experimental Correlations, April 2003, A. Courcelle, et al. JEFDOC-952 Summary Report of the WPEC/Subgroup 22, Nuclear Data for Improved

LEU-LWR Reactivity Prediction, April 2003, A. Courcelle JEFDOC-951 Microscopic Evaluation of Eu Isotopes, April 2003, E. Bauge JEFDOC-950 MONK8B Analysis of the Hellstrand Experiment, April 2003, D. Hanlon,

C.J. Dean JEF/DOC-949 The Generation of Beta Spectra from ENDF6 Evaluations, April 2003, C.J. Dean JEF/DOC-948 Measurements of Thermal Neutron Capture Cross-sections of 241Am, 242gsAm,

243Am and 242Pu, April 2003, F. Marie JEFDOC-947 Comparison of 133Cs and 153Eu Neutron Capture from New Evaluations to JEF-2.2

for a Range of Thermal Reactors, April 2003, R. Mills

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JEFDOC-946 Evaluation of the Neutron Cross-section for 153Eu, April 2003, M.C. Moxon JEFDOC-945 Evaluation of the Neutron Cross-section for 133Cs, April 2003, M.C. Moxon JEFDOC-944 Summary Records of the JEFF Meeting, December 2002, A. Nouri JEFDOC-943 Calculation of the VALDUC Lattices with Revised 235U Data, April 2003,

D. Hanlon JEFDOC-942 Nuclear Data Networking: Minutes of the Informal Meeting Between OECD/NEA

Data Bank and EC/DG Research, 17 February 2003 JEFDOC-941 Summary Records of the JEFF/SCG Meeting, December 2002, A. Nouri JEFDOC-940 Cross-section Covariance Data Available in Recent Evaluated Nuclear Data

Libraries, I. Kodeli JEFDOC-939 Status of IRDF-2002 Development, A. Nichols JEFDOC-938 Cross-section Evaluation for the System n + 238U, M.J. Lopez JEFDOC-937 Status of the CERN-nTOF Facility, H. Leeb JEFDOC-936 Status of 99Tc Evaluation, F. Gunsing JEFDOC-935 Nuclear Data Status and Needs for Medical Applications, E. Menapace JEFDOC-934 JEFF-3.0: NJOY99 and CALENDF-2002 Processing – Viewpoint, Prospect and

Solutions, J-Ch. Sublet, P. Ribon JEFDOC-933 Validation of Depletion Calculation Through Takahama-3 Chemical Assays with

JEFF-3.0, A. Courcelle, A. Santamarina JEFDOC-932 Brief Progress Report of the WPEC-SG22, A. Courcelle JEFDOC-931 Motivation for New 241Am Measurements, O. Bouland JEFDOC-930 Status of the JANIS Software, December 2002, A. Nouri JEFDOC-929 SAMQUA – A Program for Generating All Possible Combinations of Quantum

Numbers Leading to the Same Compound Nucleus State in the Framework of the R-matrix Code SAMMY, O. Bouland, R. Babut, N.M. Larson

JEFDOC-928 MYRRHA: A European Multipurpose ADS for R&D. Pre-design Phase Completion, April 2002, N. Messaoudi

JEFDOC-927 HINDAS, A European Project on High- and Intermediate-energy Nuclear Data for Accelerator-driven Systems, April 2002, F. Haddad

JEFDOC-926 Light-charged Particle Emission in Fast Neutron-induced Reactions, April 2002, J.P. Meulders, et al.

JEFDOC-925 JEFF Proposals for ENDF-7 Format, P. Ribon, et al. (not available) JEFDOC-924 Current Status and Proposals Concerning Hf Evaluation in JEFF-3, April 2002,

J-M. Palau JEFDOC-923 FP6 Integrated Projects: Networks of Excellence and Expression of Interest,

April 2002 JEFDOC-922 The Difference Between Thermal and Fast Spectrum Values of Fission Product

Yields – The Information Obtained in Measurements of Delayed Neutron Yields, April 2002, A. D’Angelo, J. Rowlands

JEFDOC-921 JEFF-3.0 Trends Derived from the PROFIL Fast Spectrum Experiments, April 2002, E. Dupont, et al.

JEFDOC-920 Conclusions Concerning the Delayed Neutron Data for the Major Actinides, April 2002, A. d’Angelo, J.L. Rowlands

JEFDOC-919 New Evaluation of 239Pu Data, April 2002, P. Romain, et al. JEFDOC-918 Integral Validation of the 239Pu CEA Evaluation Adopted in JEFF-3.0, April 2002,

E. Dupont, et al. JEFDOC-917 Re-evaluation of the 240Pu Cross-sections in the Unresolved Resonance Energy

Range, April 2002, O. Bouland JEFDOC-916 Re-evaluation and Validation of the 241Pu Resonance Parameters in the Energy

Range Thermal to 20 eV, April 2002, H. Derrien A. Courcelle A. Santamarina

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26

JEFDOC-915 JEFF-3.0 235U and 238U Trends in Fast Spectrum Experiments, April 2002, E. Dupont, et al.

JEFDOC-914 238U JEFF-3.0 Benchmarking, April 2002, A. Courcelle, E. Dupont, O. Litaize JEFDOC-913 Aluminium Data Measurements and Evaluation for Criticality Safety Applications,

April 2002, L.C. Leal, et al. JEFDOC-912 Progress Report on Main Fission Products: Recommendations for 103Rh, 152Eu and

153Eu, April 2002, O. Serot, et al. JEFDOC-911 Comparative Validation Results of JEFF-3T2, JEF-2.2, ENDF/B-VI.5 and

JENDL-3.2, April 2002, A. Hogenbirk JEFDOC-910 Data Sensitivity of Design Calculations for High Conversion D2O Reactors,

April 2002, S. Pelloni JEFDOC-909 The UKFY3.4 Fission Product Yield Evaluation, April 2002, R.W. Mills JEFDOC-908 Possible Re-evaluations of Decay Data for JEFF (UK Sponsorship), April 2002,

A. Nichols JEFDOC-907 Spectral Data in JEF-2.2 and JEFF-3T2, April 2002, R.J. Perry, C.J. Dean JEFDOC-906 Analysis of JEFF-3T2 Decay Data Using FIZCON, April 2002, R. Perrey, et al. JEFDOC-905 Experimental Activities at IRMM, April 2002, P. Rullhusen JEFDOC-904 Status of the nTOF Facility at CERN, April 2002, F. Gunsing JEFDOC-903 Measurement of the 232Th Cross-section in the Unresolved Region, April 2002,

G. Lobo JEFDOC-902 Reserved to A. Nouri (JEFF minutes), April 2002 JEFDOC-901 Reserved to A. Nouri (JEFF/SCG minutes), April 2002 JEFDOC-900 Energy Release in 239Pu Fission, April 2002, O. Serot, et al.

EFF documents

EFFDOC-959 Requirements for Nuclear Data Development and Neutronic Analysis Efforts in the EU Fusion Technology Program 2007-2013 (FP7), P. Batistoni, U. Fischer, R. Forrest

EFFDOC-958 Report of the IAEA TC Meeting on Nuclear Data for IFMIF, Karlsruhe, 4 October 2005, U. Fischer, R. Forrest, A. Mengoni

EFFDOC-957 Theoretical Calculations of Covariance Matrices for Li Isotopes, H. Leeb, M.T. Pigni EFFDOC-956 Measurement of Tritium Production Rates and of Neutron and Gamma-ray Flux

Spectra in the TBM Mock-up, K. Seidel EFFDOC-955 Validation Experiment of Gamma-activities of Tantalum Irradiated in Fusion Peak

Neutron Field, K. Seidel EFFDOC-954 Monte-Carlo-based Transport and Sensitivity/Uncertainty Analyses of the Tritium

Production in the HCPB Breeder Blanket Mock-up Experiment, U. Fischer, D. Leichtle, R. Perel

EFFDOC-953 Evaluation of 181Ta Cross-sections for the EFF Data Library Up to 150 MeV, P. Pereslavtsev

EFFDOC-952 First Benchmark Analyses of Ta Evaluated Data for Fusion Neutron Transport Calculations, S.P. Simakov, U. Fischer

EFFDOC-951 Analyses of the NPI/Rez Validation Experiment for Ta Activation Cross-sections in an IFMIF-like Neutron Spectrum, S.P. Simakov, et al.

EFFDOC-950 Deterministic 3-D Analysis of HCPB Breeder Blanket Mock-up Experiment, I. Kodeli

EFFDOC-949 Comparison of Covariance Matrices Calculated by A. Koning (2005) and Covariance Matrices from Evaluation of Experimental Data for 56Fe, S. Tagesen, H. Vonach

EFFDOC-948 Nuclear Decay Heat in Molybdenum Measurements and Analysis, M. Pillon

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EFFDOC-947 Validation Report for EAF-2005 and Deuteron Data, R. Forrest EFFDOC-946 Validation Experiment on Tantalum Activation in the NPI p-D2O Neutron Field of

IFMIF-like Spectrum, M. Honusek EFFDOC-945 Validation Experiment on Tungsten Activation in the NPI p-D2O Neutron Field of

IFMIF-like Spectrum, E. Simeckova EFFDOC-944 Experimental Determination of the NPI p-D2O Neutron Source Spectrum for

Activation Benchmark Tests, P. Bém EFFDOC-943 Comparison of new 48Ti Measurements with 2002 Evaluation, S. Tagesen EFFDOC-942 Evaluation of 182,183,184,186W Neutron Cross-sections Up to 20 MeV for Combination

with the FZK Theoretical 150 MeV Evaluation, S. Tagesen EFFDOC-941 Progress on Deuteron-induced Activation Cross-section Evaluation by Means of

Optical Model Potential Analysis, M. Avrigeanu EFFDOC-940 Progress on Calculation of the Activation Cross-sections for Ta and Hf up to

60 MeV, V. Avrigeanu EFFDOC-939 Release of EAF-2005.1 Library, J. Kopecky EFFDOC-938 Status of the TBM Neutronics Experiment, P. Batistoni EFFDOC-937 Summary Record of the EFF/EAF Monitor Group Meeting, May 2005,

H. Henriksson EFFDOC-936 Evaluation of All Important Neutron Cross-sections for 184W Including Full

Covariance Information, S. Tagesen EFFDOC-935 New Evaluation of d+Li Data Up to 50 MeV for IFMIF, P. Pereslavtsev EFFDOC-934 Progress Report of TU Dresden, K. Seidel EFFDOC-933 HCPB Breeder Blanket Mock-up Experiment Pre-analysis Using TORT Code,

I. Kodeli EFFDOC-932 Benchmark Analyses of 9Be JEFF-3.1T Data for Fusion Applications, D. Leichtle EFFDOC-931 Testing of New W Data Evaluations for EFF-3, U. Fischer EFFDOC-930 Benchmark Analyses of Ti JEFF-3.1T Data for Fusion Applications, U. Fischer EFFDOC-929 Benchmark Analyses of Pb JEFF-3.1T Data for Fusion Applications, S. Simakov EFFDOC-928 Activation Cross-sections of the Hf and Ta Stable Isotopes and their Sensitivity

to Nuclear Reaction Mechanisms, M. Avrigeanu, V. Avrigeanu, R.A. Forrest, F.L. Roman

EFFDOC-927 The Release of EASY-2005 and Current Work, R.A. Forrest EFFDOC-926 Testing MCSEN Track-length Sensitivity Calculations for the TBM Mock-up

Experiment, R. Perel EFFDOC-925 Status of Test Blanket Module (TBM) Neutronics Experiment, P. Batistoni EFFDOC-924 Validation of EAF-2005 – New Tools, J. Kopecky EFFDOC-923 Summary Record of the EFF/EAF Monitor Group Meeting, November 2004,

H. Henriksson EFFDOC-922 Validation Analyses of IEAF-2001 Activation Cross-section Data for SS-316

and F82H Steels Irradiated in a White d-Li Neutron Field, S.P. Simakov, et al. (Presented at the ND2004 in Santa Fe, USA)

EFFDOC-921 Evaluation of n+W Cross-section Data Up to 150 MeV Neutron Energy, P. Pereslavtsev, U. Fischer (Presented at the ND2004 in Santa Fe, USA)

EFFDOC-920 Nuclear Data for Fusion Energy Technologies: Requests, Status and Development Needs, U. Fischer, et al. (Presented at the ND2004 in Santa Fe, USA)

EFFDOC-919 TALYS, Monte Carlo and Covariances, A.J. Koning EFFDOC-918 HCPB Breeder Blanket Mock-up Experiment Analysis Using DORT and SUSD3D

Codes, I. Kodeli EFFDOC-917 Nuclear Decay Heat in Tantalum – Measurements and Analysis, M. Pillon (presented

by P. Batistoni)

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EFFDOC-916 Validation Experiment of Gamma Activities of Pb Irradiated in Fusion Peak Neutron Field, R. Eichin, R.A. Forrest, H. Freiesleben, K. Seidel, S. Unholzer

EFFDOC-915 Implementation and Testing of Sensitivity Calculations of Monte Carlo Track Length Estimators in MCSEN, R. Perel (presented by U. Fischer)

EFFDOC-914 Analysis of Rez Data for Dosimetry Foils Using EAF-2004, R. Forrest EFFDOC-913 Analysis of the NPI Validation Experiment for Tungsten Activation Cross-sections

in an IFMIF-like Neutron Spectrum, S. Simakov, et al. EFFDOC-912 Evaluation of n + 182,183,184,186W Cross-sections for EFF Up to 150 MeV,

P. Pereslavtsev, U. Fischer EFFDOC-911 First Benchmark Analyses for Ti Data Evaluations, U. Fischer, S. Simakov EFFDOC-910 Activation Benchmark Tests at the NPI Fast Neutron Facility, P. Bém EFFDOC-909 Status of EAF-2005, J. Kopecky EFFDOC-908 Status of Neutronics Experiment on a Mock-up of a Test Blanket Module (TBM),

P. Batistoni EFFDOC-907 Calculation of D-Li Cross-sections for Energies Up to 50 MeV Using Realistic

Nucleon-nucleon Interactions, M. Avrigeanu EFFDOC-906 Development of Theoretical Tools and Their Use to Calculate Cross-sections

Relevant to the EAF and EFF Files, V. Avrigeanu EFFDOC-905 Summary Record of the EFF/EAF Monitor Group Meeting 10 May 2004,

R. Forrest EFFDOC-904 Radiation Shielding and Dosimetry Experiments Updates in the SINBAD Database,

I. Kodeli, H. Hunter, E. Sartori EFFDOC-903 Nuclear Decay Heat in Yttrium, Revised Measurements and Analysis, M. Pillon EFFDOC-902 Decay Heat Estimate Based on EAF-2003 and FENDL/A-2 Nuclear Data Libraries

for Fusion Relevant Materials in Comparison with FNS-JAERI Experiments, 10 May 2004, D. Cepraga, G. Cambi, M. Frisoni, E. Menapace

EFFDOC-901 Coupled Channels Calculations for d + 6Li, M. Avrigeanu EFFDOC-900 Post-analysis of the NPI Irradiation Experiment on Eurofer Up to 35 MeV Using

IEAF-2001 Activation Cross-sections, S. Simakov, et al. EFFDOC-899 Status of n + W Cross-section Evaluations for EFF Up to 150 MeV, P. Pereslavtsev,

U. Fischer EFFDOC-898 Monte-Carlo-based Pre-analysis of the HCPB Breeder Blanket Mock-up Experiment:

Neutron Spectra, Tritium Production and Sensitivities to Cross-sections, U. Fischer, R. Perel

EFFDOC-897 Re-analysis of TUD Benchmark Experiment on Tungsten Using JENDL-3.3 Data, U. Fischer

EFFDOC-896 Status of TBM Neutronics Experiment, 10 May 2004, P. Batistoni EFFDOC-895 International Benchmark Comparison on Tritium Measurements, 10 May 2004,

P. Batistoni EFFDOC-894 Progress Report of TU Dresden, 10 May 2004, K. Seidel EFFDOC-893 Progress Report on Fast-neutron Reaction Analysis for Fusion Low-activation

Materials, 10 May 2004, V. Avrigeanu EFFDOC-892 New Actions for EAF-2005, 10 May 2004, J. Kopecky EFFDOC-891 Summary Record of the EFF/EAF Monitor Group Meeting, 17 November 2003,

M.A. Kellett EFFDOC-890 High Priority Request List: Fusion, A.J. Koning EFFDOC-889 Inelastic Scattering on 52Cr with the n,n�g Technique, A.J.M. Plompen EFFDOC-888 Covariance Determination for Evaluations Including Extensive Modelling, H. Leeb EFFDOC-887 Calculation of Deuterium-lithium Cross-sections for Energies Up to 50 MeV Using

Realistic Nucleon-nucleon Interactions, M. Avrigeanu EFFDOC-886 Pre-analysis of TBM Experiment Using DORT and SUSD3D Codes, I. Kodeli

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EFFDOC-885 Tungsten Benchmark Experiments: Re-analysis Using JENDL-3.3, I. Kodeli EFFDOC-884 TBM Neutronics Experiment: Design of the Measurements of Tritium Production

and of Neutron and Gamma-ray Flux Spectra, K. Seidel EFFDOC-883 Validation Experiment of Gamma Activities of Yttrium Irradiated in Fusion Peak

Neutron Field, K. Seidel EFFDOC-882 Validation of EASY-2003, R.A. Forrest EFFDOC-881 EASY-2004, R.A. Forrest, J. Kopecky EFFDOC-880 Progress Report on Fast-neutron Reaction Analysis for Fusion Low-activation

Materials, V. Avrigeanu EFFDOC-879 Status of the Evaluation of all Ti Isotopes, S. Tagesen, H. Vonach EFFDOC-878 Modification to GLUCS to Avoid a Systematic Underestimation of Cross-sections

(In Particular with Inconsistent and Highly Correlated Experimental Data), S. Tagesen, H. Vonach

EFFDOC-877 Design of TBM Neutronics Experiment, P. Batistoni EFFDOC-876 IEAF-2001 Cross-section Data Library for Activation and Transmutation Analyses

of Intermediate Energy Systems with the FISPACT Inventory Code, U. Fischer, et al. EFFDOC-875 Pre-analysis of the Validation Experiment on Eurofer Up to 55 MeV in an IFMIF-

like Neutron Spectrum Benchmark, S. Simakov EFFDOC-874 Benchmark Analysis of the EFF-3.03 52Cr Data Evaluation, U. Fischer, S. Simakov,

I. Schmuck EFFDOC-873 Sensitivity Calculation of Monte-Carlo Track-length Estimators for Cross-section

Sensitivity and Uncertainty Analyses, R. Perel EFFDOC-872 Evaluation of n + 184W Cross-section Data for EFF Up to 150 MeV, P. Pereslavtsev EFFDOC-871 Measurement and Analysis of Nuclear Decay Heat in Yttrium, M. Pillon EFFDOC-870 IEAF-2001 Cross-section Data Libraries for Activation and Transmutation Analyses

of Intermediate-energy Systems, U. Fischer, et al. (presented at the TRAMU Workshop, Darmstadt, 2-5 Sept. 2003)

EFFDOC-869 Production of 62mCo in Copper Irradiated in the Karlsruhe d-Be Neutron Field, U. von Möllendorff, S. Simakov

EFFDOC-868 Summary Record of the EFF/EAF Monitor Group Meeting, 29 April 2003, M.A. Kellett

EFFDOC-867 Analysis of FNG Benchmark Experiment on Tungsten Using DORT, TWODANT and SUSD3D Deterministic Codes, I. Kodeli

EFFDOC-866 Recent Progress in the SINBAD Project, I. Kodeli EFFDOC-865 Progress Towards EASY-2004, R.A. Forrest EFFDOC-864 Design of TBM Neutronics Experiment (2003), P. Batistoni EFFDOC-863 Final Report on the Tungsten Experiment (2002), P. Batistoni, M. Angelone,

L. Petrizzi, M. Pillon EFFDOC-862 Preliminary Measurements and Analysis of Nuclear Decay Heat in Sc, Sm, Gd and

Dy, M. Pillon EFFDOC-861 EAF-2003 Versus 252Cf Integral Data, J. Kopecky EFFDOC-860 Monte Carlo Transport and Sensitivity Analyses for the TUD Neutron Transport

Benchmark Experiment on Tungsten, U. Fischer, et al. EFFDOC-859 Validation Analyses of IEAF-2001 Activation Cross-section Data for SS-316 Steel,

S. Simakov, et al. EFFDOC-858 Measurement and Analysis of Induced Activation in CuCrZr Irradiated in Fusion

Peak Neutron Field, R. Eichin, R.A. Forrest, H. Freiesleben, S.A. Goncharov, V.D. Kovalchuk, D.V. Markovskij, D.V. Maximov, K. Seidel, S. Unholzer

EFFDOC-857 Measurement and Analysis of Neutron and Gamma-ray Flux Spectra in Tungsten, H. Freiesleben, C. Negoita, K. Seidel, S. Unholzer, U. Fischer, D. Leichtle, M Angelone, P. Batistoni, M. Pillon

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EFFDOC-856 Comparison of Different Existing Cross-section Calculations for 46,47,49,50Ti, H. Vonach, S. Tagesen

EFFDOC-855 Results of Inclusion of New Geel Data for 58Ni into the Recent Evaluation, H. Vonach, S. Tagesen

EFFDOC-854 Progress Report on Fast-neutron Analysis for Fusion Low-activation Materials, V. Avrigeanu

EFFDOC-853 Progress Report on Calculation of D-Li Cross-sections for Energies Up to 50 MeV, M. Avrigeanu

EFFDOC-852 Nuclear Data for Design Analyses of the Test Blanket Modules in ITER: Review and Recommendations for EFF/JEFF Evaluations, U. Fischer

EFFDOC-851 Summary Record of the EFF/EAF Monitor Group Meeting, 5-6 December 2002, M.A. Kellett

EFFDOC-850 Neutronics and Nuclear Data: Status and Perspectives for Fusion Technology Applications (presented at the Dresden Workshop on Fast Neutron Physics in September 2002), U. Fischer

EFFDOC-849 EFDA, G. Le Marois EFFDOC-848 Processed Covariance Matrices for 28Si, Evaluation EFF-3.0, I. Kodeli EFFDOC-847 Processed Covariance Matrices for 56Fe, Evaluation JEFF-3.0/EFF-3.1, I. Kodeli EFFDOC-846 ALARA/IEAF-2001: Validation and Application for IFMIF Activation and

Transmutation Analyses, S. Simakov EFFDOC-845 Monte Carlo Sensitivity Analysis of FNS and KANT Be Experiments Using the

9Be EFF3.0/NMOD=5 Evaluation, R. Perel EFFDOC-844 Benchmark Analysis of EFF and FENDL Carbon Cross-section Data, D. Leichtle EFFDOC-843 Integral Data for EAF-2003, J. Kopecky EFFDOC-842 Status of EAF libraries, R.A. Forrest EFFDOC-841 A Complementary Report on Decay Heat Estimate for Fusion-relevant Materials

Based on EAF-99 and FENDL/A-2 Libraries in Comparison with FNS-JAERI Experiments, E. Menapace

EFFDOC-840 FNS Experimental Validation of the Decay Power Calculation Code and Nuclear Databases – FISPACT-2001 and EAF-99 & EAF-2001 & EAF-2001 Decay Libraries – 7 Hours Irradiation, J-Ch. Sublet, F. Maekawa

EFFDOC-839 New FNS Experimental Validation of the Decay Power Calculation Code and Nuclear Databases – FISPACT-2001 and EAF-99 & EAF-2001 & EAF-2001 Decay Libraries – 5 Minutes Irradiation, J-Ch. Sublet, F. Maekawa

EFFDOC-838 Measurement and Analysis of Nuclear Decay Heat in CuCrZr, M. Pillon EFFDOC-837 ZZ-VITAMIN-J/COVA/EFF-3 Cross-section Covariance Matrix Library, I. Kodeli EFFDOC-836 Progress Report of TUD, K. Seidel EFFDOC-835 Completion of Model Calculation of Fast Neutron Reaction Cross-sections for all

Stable Isotopes of Ni and Mo, V. Avrigeanu, M. Avrigeanu, T. Glodariu EFFDOC-834 Inelastic Scattering of 58Ni and Progress with Activation Measurements, paper

from PHYSOR’2002 supplied, A. Plompen EFFDOC-833 Status of the Complete Evaluation of all Important Neutron Reactions on 48Ti

Including Full Covariance Information, H. Vonach, S. Tagesen EFFDOC-832 Final Full Documentation of the Evaluations of 58Ni, 60Ni and 28Si, H. Vonach,

S. Tagesen EFFDOC-831 Progress Report on W Experiment at FNG, P. Batistoni EFFDOC-830 A Brief Overview of the European Fusion File (EFF) Project (presented at IAEA

FEC 2002, Lyon), M.A. Kellett, R.A. Forrest, P. Batistoni, on behalf of the EFF Project members

EFFDOC-829 Summary Record of the EFF/EAF Monitor Group Meeting, 25 April 2002, M.A. Kellett

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EFFDOC-828 Needs for Nuclear Data Development and Improvement in the Fusion Technology Program in 2003-2006 and Beyond, P. Batistoni, U. Fischer, R.A. Forrest

EFFDOC-827 Measurements on Neutron-irradiated Chromium (report sent to EFDA), M. Pillon, M. Angelone

EFFDOC-826 Neutronics and Nuclear Data for the IFMIF Neutron Source (ISFNT-6 paper), U. Fischer, S.P. Simakov, A. Konobeev, P. Pereslavtsev, P. Wilson

EFFDOC-825 Nuclear Data for the IFMIF Neutron Source – Status and Future Plans (presented to the JEFF IE group), U. Fischer

EFFDOC-824 Status of the New Evaluation of Neutron Cross-sections for 12C and 16O, A. Mengoni

EFFDOC-823 Progress with Ni Cross-section Measurements, A. Plompen EFFDOC-822 Measurement and Analysis of Neutron and Gamma-ray Flux Spectra in SiC,

H. Freiesleben, C. Negoita, K. Seidel, S. Unholzer, Y. Chen, U. Fischer, M. Angelone, P. Batistoni, M. Pillon

EFFDOC-821 Activation Experiment with Tungsten in Fusion Peak Neutron Field, K. Seidel, R.A. Forrest, H. Freiesleben, S.A. Goncharov, V.D. Kovalchuk, D.V. Markovskij, D.V. Maximovich, S. Unholzer, R. Weigel

EFFDOC-820 Validation of the EASY-2001 Activation System (ISFNT-6 paper), R.A. Forrest, M. Pillon, U. von Möllendorff, K. Seidel

EFFDOC-819 EAF-2001 Validation Against Integral Experiments, J. Kopecky EFFDOC-818 Deterministic Transport, Sensitivity and Uncertainty Analysis of SiC Benchmark

Experiment Using EFF-3 and FENDL-2 Evaluations, I. Kodeli EFFDOC-817 First Results from Monte Carlo Sensitivity Calculations Using the 9Be EFF3.05

Evaluation, D. Leichtle EFFDOC-816 EAF-2001 in ENDF-6 Format and NJOY99-68 Processing, J-Ch. Sublet,

A.J. Koning, R.E. MacFarlane EFFDOC-815 Monte Carlo Transport, Sensitivity and Uncertainty Analyses for the TUD

Benchmark Experiment on SiC, U. Fischer, R. Perel, Y. Chen EFFDOC-814 Analysis of the Shutdown Dose Rate Experiment: Comparison of Results with

EFF/EAF, JENDL and FENDL Libraries, P. Batistoni EFFDOC-813 Final Results of the Analysis of Benchmark Experiment on SiC, P. Batistoni EFFDOC-812 Measurements of Decay Heat and Validation of the European Activation Code

System for Fusion Power Plant Applications, M. Pillon EFFDOC-811 Measurements on Neutron-irradiated Chromium, M. Pillon EFFDOC-810 Summary Record of the EFF/EAF Monitor Group Meeting, 20 November 2001,

M.A. Kellett

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TABLES

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Page 35: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

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G.M

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328

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K

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. Kit

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1525

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ND

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VA

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87

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ND

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87

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akam

ura

35

Page 36: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

ory

Eva

luat

ion

Aut

hor(

s)

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l-35

17

25

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EN

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VA

L-O

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03

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ayer

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uber

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eal,

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17-C

l-37

17

31

Pre-

EN

DF/

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II

OR

NL

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VA

L-O

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03

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ayer

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20-C

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31

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JEFF

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onin

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36

Page 37: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

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sour

ce

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luat

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37

Page 38: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

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eria

l M

AT

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sour

ce

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ion

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37

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)

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25

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89

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28

JEN

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VA

L-A

UG

89

JND

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40-Z

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31

JEN

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JN

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JND

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WG

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34

JEFF

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N

EA

R

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M-J

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82

H. G

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40-Z

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40

37

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JN

DC

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L-A

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89

JND

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40

JEFF

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N

EA

R

CO

M-J

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83

H. G

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43

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UG

89

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P N

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WG

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41

25

EN

DF/

B-V

I.8

LA

NL

, AN

L

EV

AL

-DE

C97

M

. Cha

dwic

k, P

. You

ng, D

.L. S

mit

h

41-N

b-94

41

28

JEN

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-3.3

JN

DC

E

VA

L-M

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90

JND

C F

P N

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31

JEN

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DC

E

VA

L-M

AR

90

JND

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P N

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ata

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42-M

o-92

42

25

JEN

DL

-3.3

JN

DC

E

VA

L-A

UG

89

JND

C F

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WG

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31

JEN

DL

-3.3

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DC

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VA

L-A

UG

89

JND

C F

P N

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WG

42-M

o-95

42

34

Pre-

EN

DF/

B-V

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BN

L, K

AE

RI

EV

AL

-OC

T03

L

ee, O

h, M

ugha

bgha

b, O

bloz

insk

y

38

Page 39: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

ory

Eva

luat

ion

Aut

hor(

s)

42-M

o-96

42

37

JEN

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89

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42-M

o-97

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40

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JN

DC

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L-A

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89

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43

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DC

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49

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VA

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31

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JEFF

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JEFF

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52

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JEFF

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JEFF

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A, A

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abe,

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. Sm

ith, +

39

Page 40: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

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Eva

luat

ion

Aut

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31

JEFF

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U

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abe,

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37

JEFF

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A, A

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VA

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94

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JEFF

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JEFF

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JEFF

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up

40

Page 41: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

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sour

ce

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H. G

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Scie

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55-C

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3 55

25

JEFF

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B

NL

, KA

ER

I, +

E

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L-A

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99

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JEFF

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N

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82

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55-C

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JEFF

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41

Page 42: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

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sour

ce

Lab

orat

ory

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ion

Aut

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s)

56-B

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61-P

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6149

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FF-3

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NE

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42

Page 43: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

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sour

ce

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orat

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luat

ion

Aut

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61-P

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43

Page 44: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

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eria

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AN

L

EV

AL

-MA

R90

L

.W. W

esto

n, P

.G. Y

oung

75-R

e-18

7 75

31

JEFF

-3.0

O

RN

L, L

AN

L

EV

AL

-MA

R90

L

.W. W

esto

n, P

.G. Y

oung

76-O

s-0

7600

JE

FF-3

.0 +

Cor

rect

ions

FE

I E

VA

L-J

AN

90

M.N

. Nik

olae

v

77-I

r-19

1 77

25

EN

DF/

B-V

I.8

OR

NL

E

VA

L-M

AR

95

R.Q

. Wri

ght,

R.R

. Spe

ncer

77-I

r-19

3 77

31

EN

DF/

B-V

I.8

OR

NL

E

VA

L-M

AR

95

R.Q

. Wri

ght,

R.R

. Spe

ncer

78-P

t-0

7800

JE

FF-3

.0 +

Cor

rect

ions

N

EA

, LL

NL

E

VA

L-O

CT

83

R.J

. How

erto

n

79-A

u-19

7 79

25

JEFF

-3.0

L

AN

L

EV

AL

-JA

N84

P.

G. Y

oung

44

Page 45: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

ory

Eva

luat

ion

Aut

hor(

s)

80-H

g-19

6 80

25

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

80-H

g-19

8 80

31

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

80-H

g-19

9 80

34

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

80-H

g-20

0 80

37

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

80-H

g-20

1 80

40

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

80-H

g-20

2 80

43

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

80-H

g-20

4 80

49

JEN

DL

-3.3

JN

DC

E

VA

L-S

EP9

7 K

. Shi

bata

, T. F

ukah

ori,

S. C

hiba

, +

81-T

l-0

8100

JE

FF-3

.0

SIU

E

VA

L-D

EC

93

Zho

u Y

imin

g, M

a G

ongg

ui

82-P

b-20

4 82

25

New

eva

l. N

RG

E

VA

L-D

EC

04

A.J

. Kon

ing

82-P

b-20

6 82

31

New

eva

l. N

RG

E

VA

L-D

EC

04

A.J

. Kon

ing

82-P

b-20

7 82

34

New

eva

l. N

RG

E

VA

L-D

EC

04

A.J

. Kon

ing

82-P

b-20

8 82

37

New

eva

l. N

RG

E

VA

L-D

EC

04

A.J

. Kon

ing

83-B

i-20

9 83

25

New

eva

l. N

RG

E

VA

L-D

EC

04

A.J

. Kon

ing

88-R

a-22

3 88

25

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

88-R

a-22

4 88

28

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

88-R

a-22

5 88

31

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

88-R

a-22

6 88

34

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

89-A

c-22

5 89

25

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

89-A

c-22

6 89

28

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

89-A

c-22

7 89

31

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

90-T

h-22

7 90

25

JEN

DL

-3.3

T

IT

EV

AL

-AU

G88

N

. Tak

agi

90-T

h-22

8 90

28

JEN

DL

-3.3

K

INK

I U

. E

VA

L-J

UN

87

T. O

hsaw

a

90-T

h-22

9 90

31

JEFF

-3.0

T

IT, N

EA

E

VA

L-A

UG

88

N. T

akag

i

90-T

h-23

0 90

34

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

90-T

h-23

2 90

40

EN

DF/

B-V

I.8 +

New

eva

l. M

INS

K

EV

AL

-JU

N01

V

.M. M

aslo

v, e

t al.

90-T

h-23

3 90

43

JEN

DL

-3.3

K

INK

I U

. E

VA

L-J

UL

87

T. O

hsaw

a

90-T

h-23

4 90

46

JEN

DL

-3.3

K

INK

I U

. E

VA

L-J

UL

87

T. O

hsaw

a

91-P

a-23

1 91

31

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

91-P

a-23

2 91

34

EN

DF/

B-V

I.8

OR

NL

, TIT

E

VA

L-D

EC

99

R.Q

. Wri

ght,

N. T

akag

i

91-P

a-23

3 91

37

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

45

Page 46: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

ory

Eva

luat

ion

Aut

hor(

s)

92-U

-232

92

19

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

92-U

-233

92

22

ND

L 3

.3 +

EN

DF/

B-V

I.4

SAE

I, +

E

val-

MA

R00

T

. Mut

suno

bu, T

. Kaw

ano

92-U

-234

92

25

New

eva

l. M

INS

K, +

E

VA

L-S

EP0

2 V

.M. M

aslo

v, e

t al.

92-U

-235

92

28

JEFF

-3.0

O

RN

L, L

AN

L, +

E

VA

L-N

OV

89

Wes

ton,

You

ng, P

oeni

tz, L

ubit

z

92-U

-236

92

31

New

eva

l. B

RC

, +

EV

AL

-NO

V04

L

opez

, Jim

enez

, Mor

illon

, Rom

ain

92-U

-237

92

34

New

eva

l. B

RC

,+

EV

AL

-NO

V04

L

opez

, Jim

enez

, Mor

illon

, Rom

ain

92-U

-238

92

37

New

eva

l. B

RC

, OR

NL

, +

EV

AL

-OC

T04

L

opez

, Jim

enez

, Mor

illon

, Rom

ain

93-N

p-23

5 93

40

JEN

DL

-3.3

JA

ER

I E

VA

L-M

AR

95

T. N

akag

awa

93-N

p-23

6 93

43

JEN

DL

-3.3

JA

ER

I E

VA

L-M

AR

93

T. N

akag

awa

93-N

p-23

7 93

46

JEN

DL

3.3

JA

ER

I E

VA

L-J

an01

T

. Nak

agaw

a, O

. Iw

amot

o

93-N

p-23

8 93

49

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

93-N

p-23

9 93

52

JEFF

-3.0

O

RN

L

EV

AL

-DE

C88

R

.Q. W

righ

t

94-P

u-23

6 94

28

JEN

DL

-3.3

JA

ER

I E

VA

L-F

EB

02

O. I

wam

oto

94-P

u-23

7 94

31

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

94-P

u-23

8 94

34

JEFF

-3.0

M

AP

I, JA

ER

I E

VA

L-M

AR

89

T. K

awak

ita,

T. N

akag

awa

94-P

u-23

9 94

37

JEFF

-3.0

B

RC

, CA

D, +

E

VA

L: R

OM

A

In, M

orill

on, D

os S

anto

s, U

zarr

alde

94-P

u-24

0 94

40

JEFF

-3.0

+ N

ew e

val.

BR

C, C

AD

E

VA

L-J

UL

04

Bou

land

, Der

rien

, Mor

illon

, Rom

ain

94-P

u-24

1 94

43

JEFF

-3.0

JA

ER

I E

VA

L-O

CT

87

Y. K

ikuc

hi, N

. Sek

ine,

T. N

akag

awa

94-P

u-24

2 94

46

JEFF

-3.0

E

NE

A, I

JS

EV

AL

-OC

T98

A

. Ven

tura

, S. M

aset

ti, A

. Trk

ov

94-P

u-24

3 94

49

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

94-P

u-24

4 94

52

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

94-P

u-24

6 94

58

JEN

DL

-3.3

JA

ER

I E

VA

L-M

AR

95

T. N

akag

awa

95-A

m-2

41

9543

V

AL

UA

TIO

N

CA

D, N

EA

, +

EV

AL

-APR

05

Bou

land

, Ber

nard

, Rug

ama,

et a

l.

95-A

m-2

42g

9546

JE

ND

L-3

.3

MIN

SK

, +

EV

AL

-FE

B97

V

.M. M

aslo

v, e

t al.

95-A

m-2

42m

95

47

JEN

DL

-3.3

M

INS

K, B

YE

L

EV

AL

-DE

C96

V

.M. M

aslo

v, e

t al.

95-A

m-2

43

9549

JE

ND

L-3

.3

MIN

SK

, JA

ER

I E

VA

L-J

AN

02

V.M

. Mas

lov,

+, T

. Nak

agaw

a

95-A

m-2

44

9552

JE

ND

L-3

.3

JAE

RI

EV

AL

-MA

R88

T

. Nak

agaw

a

95-A

m-2

44m

95

53

JEN

DL

-3.3

JA

ER

I E

VA

L-M

AR

88

T. N

akag

awa

96-C

m-2

40

9625

JE

ND

L-3

.3

JAE

RI

EV

AL

-OC

T95

T

. Nak

agaw

a, T

. Liu

96-C

m-2

41

9628

JE

FF-3

.0

NE

A

RC

OM

-JU

N82

Sc

ient

ific

Co-

ordi

nati

on G

roup

46

Page 47: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 1

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

(co

nt.)

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

ory

Eva

luat

ion

Aut

hor(

s)

96-C

m-2

42

9631

JE

FF-3

.0

NE

A

RC

OM

-JU

N82

E

. Men

apac

e

96-C

m-2

43

9634

JE

FF-3

.0

JAE

RI

EV

AL

-MA

R89

T

. Nak

agaw

a

96-C

m-2

44

9637

E

ND

F/B

-VI.8

H

ED

L, S

RL

, +

EV

AL

-APR

78

Man

n, B

enja

min

, How

erto

n, e

t al.

96-C

m-2

45

9640

JE

ND

L-3

.3

MIN

SK

,BY

EL

E

VA

L-N

OV

95

V.M

. Mas

lov,

et a

l.

96-C

m-2

46

9643

JE

FF-3

.0

MIN

SK

BY

EL

E

VA

L-F

EB

96

96-C

m-2

47

9646

JE

FF-3

.0

JAE

RI

EV

AL

-MA

R89

T

. Nak

agaw

a, Y

. Kik

uchi

96-C

m-2

48

9649

JE

FF-3

.0

JAE

RI

EV

AL

-MA

R84

Y

. Kik

uchi

, T. N

akag

awa

96-C

m-2

49

9652

JE

ND

L-3

.3

JAE

RI

EV

AL

-OC

T95

T

. Nak

agaw

a, T

. Liu

96-C

m-2

50

9655

JE

ND

L-3

.3

JAE

RI

EV

AL

-OC

T95

T

. Nak

agaw

a, T

. Liu

97-B

k-24

7 97

46

JEN

DL

-3.3

JA

ER

I E

VA

L-J

UN

95

T. N

akag

awa,

T. L

iu

97-B

k-24

9 97

52

JEN

DL

-3.3

JA

ER

I E

VA

L-M

AR

85

Y. K

ikuc

hi, T

. Nak

agaw

a

97-B

k-25

0 97

55

JEFF

-3.0

JA

ER

I E

VA

L-M

AR

87

T. N

akag

awa

98-C

f-24

9 98

52

JEN

DL

-3.3

JA

ER

I E

VA

L-J

UL

95

T. N

akag

awa,

T. L

iu

98-C

f-25

0 98

55

JEN

DL

-3.3

JA

ER

I E

VA

L-M

AR

86

T. N

akag

awa

98-C

f-25

1 98

58

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

98-C

f-25

2 98

61

JEFF

-3.0

N

EA

R

CO

M-J

UN

82

Scie

ntif

ic C

o-or

dina

tion

Gro

up

98-C

f-25

4 98

67

JEFF

-3.0

T

IT

EV

AL

-AU

G87

N

. Tak

agi

99-E

s-25

3 99

13

JEF-

2.2

NE

A

RC

OM

-JU

N82

Sc

ient

ific

Co-

ordi

nati

on G

roup

99-E

s-25

4 99

14

JEN

DL

-3.3

T

IT

EV

AL

-AU

G87

N

. Tak

agi

99-E

s-25

5 99

16

JEN

DL

-3.3

T

IT

EV

AL

-AU

G87

N

. Tak

agi

100-

Fm-2

55

9936

JE

ND

L-3

.3

TIT

E

VA

L-A

UG

87

N. T

akag

i

47

Page 48: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 2

. Ori

gin

of e

valu

atio

ns in

the

JE

FF

-3.1

the

rmal

sca

tter

ing

law

libr

ary

Mat

eria

l M

AT

D

ata

sour

ce

Lab

orat

ory

Eva

luat

ion

Aut

hor(

s)

H(H

2O)

1 N

ew e

val.

IKE

E

VA

L-J

AN

04

J. K

eine

rt, M

. Mat

tes

H(Z

rH)

7 N

ew e

val.

IKE

E

VA

L-J

AN

05

J. K

eine

rt

H(C

aH2)

8

New

eva

l. C

EA

, IL

L

EV

AL

-OC

T04

O

. Ser

ot (

CE

A C

adar

ache

)

D(D

2O)

11

New

eva

l. IK

E

EV

AL

-FE

B04

J.

Kei

nert

, Mat

tes

4 Be

26

JEFF

-3.0

IK

E

EV

AL

-DE

C89

J.

Kei

nert

, M. M

atte

s

Gra

phit

e 31

N

ew e

val.

IKE

E

VA

L-J

AN

05

J. K

eine

rt, M

. Mat

tes

H(C

H2)

37

JE

FF-3

.0

IKE

E

VA

L-S

EP8

1 J.

Kei

nert

, M. M

atte

s 24

Mg

52

New

eva

l. C

EA

E

VA

L-S

EP0

3 C

. Mou

nier

Ca(

CaH

2)

59

New

eva

l. C

EA

, IL

L

EV

AL

-OC

T04

O

. Ser

ot (

CE

A C

adar

ache

)

48

Page 49: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

1 1 H

45

1 1,

2, 1

02

2

1 2 H

45

1 1-

3, 1

6, 1

02

2

16

1 3 H

45

1 1,

2, 1

6, 1

7 2,

16

16

17

2 3 H

e 45

1 1,

2, 1

02-1

04

2

2 4 H

e 45

1 1,

2

2

3 6 L

i 45

1 1,

2, 4

, 24,

51-

81, 1

02, 1

03, 1

05

2, 2

4, 5

1-81

, 105

24

3 7 L

i 45

1 1,

2, 4

, 16,

24,

25,

28,

51-

53, 9

1, 1

02, 1

04

2, 5

1, 5

2

16, 2

4, 2

5, 2

8, 5

3, 9

1

4 9 B

e 45

1 1,

2, 1

02-1

05, 1

07, 8

75-8

90

2

107,

875

-890

5 10

B

451

1, 2

, 4, 5

1-85

, 102

-104

, 107

, 113

, 600

-605

, 800

, 80

1 2,

51-

85

5 11

B

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-60

, 91,

102

, 103

, 105

, 107

2,

51-

60

16

, 22,

28,

91,

103

, 107

6 na

t C

451

1-5,

28,

51-

62, 9

1, 1

02-1

04, 1

07

2, 2

8, 5

1-62

, 91

28, 9

1 5

7 14

N

451

1, 2

, 4, 5

, 16,

51-

77, 1

02-1

05, 1

07, 1

08, 6

00-6

06,

650-

653,

700

, 701

, 800

-810

2,

51-

77

5,

16

7 15

N

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-57

, 91,

102

-105

, 107

2,

16,

22,

28,

51-

57, 9

1 16

, 22,

28,

91

8 16

O

451

1-5,

16,

22,

23,

28,

32,

41,

44,

45,

51-

57, 9

1,

102-

105,

107

, 108

, 112

, 600

-603

, 650

-669

, 70

0-70

9, 7

49, 8

00-8

03

2, 5

1-57

, 600

-603

, 650

-669

, 70

0-70

9, 8

00-8

03

5,

16,

22,

23,

28,

32,

41,

44,

45,

91,

108

, 11

2, 7

49

8 17

O

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-62

, 91,

102

-104

, 107

2,

16,

22,

28,

51-

62, 9

1 16

, 22,

28,

91

9 19

F 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-71

, 91,

102

-105

, 107

2,

51-

71

16

, 22,

28,

91,

103

, 107

11

22N

a 45

1 1,

2, 4

, 16,

22,

28,

51-

61, 9

1, 1

02-1

04, 1

07, 1

08,

251

2, 1

6, 2

2, 2

8, 5

1-61

, 91

16, 2

2, 2

8, 9

1

11

23N

a 45

1 1,

2, 4

, 16,

22,

28,

51-

77, 9

1, 1

02, 1

03, 1

07, 2

51

2, 1

6, 2

2, 2

8, 5

1-77

, 91

16, 2

2, 2

8, 9

1

12

24M

g 45

1 1,

2, 4

, 16,

22,

28,

51-

61, 9

1, 1

02, 1

03, 1

07

2, 1

6, 2

2, 2

8, 5

1-61

, 91

16, 2

2, 2

8, 9

1

12

25M

g 45

1 1,

2, 4

, 16,

22,

28,

51-

67, 9

1, 1

02, 1

03, 1

07

2, 1

6, 2

2, 2

8, 5

1-67

, 91

16, 2

2, 2

8, 9

1

12

26M

g 45

1 1,

2, 4

, 16,

22,

28,

51-

63, 9

1, 1

02, 1

03, 1

07

2, 1

6, 2

2, 2

8, 5

1-63

, 91

16, 2

2, 2

8, 9

1

13

27A

l 45

1 1-

5, 1

6, 2

2, 2

8, 3

2, 3

3, 4

5, 5

1-89

, 91,

102

-105

, 10

7, 1

08, 1

11, 1

12, 1

17, 6

00-6

19, 6

49-6

69,

699-

710,

749

, 800

-819

, 849

2

5, 1

6, 2

2, 2

8, 3

2, 3

3, 4

5, 5

1-89

, 91,

108

, 111

, 11

2, 1

17, 6

00-6

19, 6

49-6

69, 6

99-7

10, 7

49,

800-

819,

849

14

28

Si

451

1-4,

16,

22,

28,

51-

67, 9

1, 1

02-1

07, 1

11, 6

00-6

13,

649,

800

-815

, 849

2

16

, 22,

28,

51-

67, 9

1, 6

00-6

13, 6

49,

800-

815,

849

14

29

Si

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-79

, 91,

102

, 103

, 107

, 111

, 20

3, 2

07

2, 5

1-79

16, 2

2, 2

8, 9

1, 2

03, 2

07

14

30Si

45

1 1,

2, 4

, 16,

22,

28,

51-

69, 9

1, 1

02, 1

03, 1

07, 1

11,

203,

207

2,

51-

69

16

, 22,

28,

91,

203

, 207

49

Page 50: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

15

31P

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-56

, 91,

102

, 103

, 107

2,

16,

22,

28,

51-

56, 9

1 16

, 22,

28,

91

16

32S

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-56

, 91,

102

, 103

, 107

2,

16,

22,

28,

51-

56, 9

1 16

, 22,

28,

91

16

33S

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-57

, 91,

102

, 103

, 107

2,

16,

22,

28,

51-

57, 9

1 16

, 22,

28,

91

16

34S

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

2,

16,

22,

28,

51-

55, 9

1 16

, 22,

28,

91

16

36S

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

2,

16,

22,

28,

51-

55, 9

1 16

, 22,

28,

91

17

35C

l 45

1 1,

2, 4

, 16,

22,

28,

32,

51-

80, 9

1, 1

02-1

05, 1

07,

111,

112

, 600

-629

, 649

-680

, 699

-730

, 749

, 80

0-82

0, 8

49

2

16, 2

2, 2

8, 3

2, 5

1-80

, 91,

111

, 112

, 600

-629

, 64

9-68

0, 6

99-7

30, 7

49, 8

00-8

20, 8

49

17

37C

l 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

77, 9

1, 1

02-1

05, 1

07,

649-

661,

699

-715

, 749

, 800

-805

, 849

2

16

, 17,

22,

28,

32,

51-

77, 9

1, 6

49-6

61,

699-

715,

749

, 800

-805

, 849

18

36

Ar

451

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-71

, 91,

102

-104

, 107

, 108

, 25

1, 2

52

2, 1

6, 2

2, 2

8, 5

1-71

, 91

16, 2

2, 2

8, 9

1

18

38A

r 45

1 1,

2, 4

, 16,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07, 1

08,

251,

252

2,

16,

22,

28,

51-

69, 9

1 16

, 22,

28,

91

18

40A

r 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

75, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-75

, 91

16, 1

7, 2

2, 2

8, 9

1

19

39K

45

1 1,

2, 4

, 16,

22,

28,

51-

54, 9

1, 1

02, 1

03, 1

07

2, 1

6, 2

2, 2

8, 5

1-54

, 91

16, 2

2, 2

8, 9

1

19

40K

45

1 1,

2, 4

, 16,

22,

28,

51-

55, 9

1, 1

02, 1

03, 1

07

2, 1

6, 2

2, 2

8, 5

1-55

, 91

16, 2

2, 2

8, 9

1

19

41K

45

1 1,

2, 4

, 16,

22,

28,

51,

52,

91,

102

, 103

, 107

2,

16,

22,

28,

51,

52,

91

16, 2

2, 2

8, 9

1

20

40C

a 45

1 1-

5, 1

6, 2

2, 2

8, 2

9, 4

4, 4

5, 5

1-70

, 91,

102

-108

, 11

1, 1

12, 1

15, 1

17, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

2

5, 1

6, 2

2, 2

8, 2

9, 4

4, 4

5, 5

1-70

, 91,

102

, 108

, 11

1, 1

12, 1

15, 1

17, 6

00-6

10, 6

49-6

55,

699-

705,

749

-755

, 799

-810

, 849

, 20

42

Ca

451

1-5,

16,

22,

28,

29,

32,

51-

70, 9

1, 1

02-1

08, 1

11,

112,

115

, 117

, 600

-610

, 649

-655

, 699

-705

, 74

9-75

5, 7

99-8

10, 8

49

2

5, 1

6, 2

2, 2

8, 2

9, 3

2, 5

1-70

, 91,

102

, 108

, 11

1, 1

12, 1

15, 1

17, 6

00-6

10, 6

49-6

55,

699-

705,

749

-755

, 799

-810

, 849

20

43

Ca

451

1-5,

16,

17,

22,

24,

28,

32,

41,

51-

70, 9

1, 1

02-1

08,

111,

112

, 600

-610

, 649

-655

, 699

-705

, 749

-755

, 79

9-81

0, 8

49

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 4

1, 5

1-70

, 91,

102

, 10

8, 1

11, 1

12, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

20

44

Ca

451

1-5,

16,

17,

22,

28,

51-

70, 9

1, 1

02-1

08, 1

11,

600-

610,

649

-655

, 699

-705

, 749

-752

, 800

-810

, 84

9

2

5, 1

6, 1

7, 2

2, 2

8, 5

1-70

, 91,

102

, 108

, 111

, 60

0-61

0, 6

49-6

55, 6

99-7

05, 7

49-7

52,

800-

810,

849

20

46

Ca

451

1-5,

16,

17,

22,

28,

51-

70, 9

1, 1

02-1

05, 1

07,

600-

610,

649

-655

, 699

-705

, 749

, 800

-804

, 849

2

5,

16,

17,

22,

28,

51-

70, 9

1, 1

02, 6

00-6

10,

649-

655,

699

-705

, 749

, 800

-804

, 849

20

48

Ca

451

1-5,

16,

17,

22,

28,

51-

70, 9

1, 1

02-1

05, 1

07,

600-

604,

649

-655

, 699

-705

, 749

, 800

-803

, 849

2

5,

16,

17,

22,

28,

51-

70, 9

1, 1

02, 6

00-6

04,

649-

655,

699

-705

, 749

, 800

-803

, 849

21

45

Sc

451

1-5,

16,

22,

28,

32,

33,

41,

51-

70, 9

1, 1

02-1

08,

111,

112

, 117

, 600

-610

, 649

-655

, 699

-705

, 74

9-75

5, 7

99-8

10, 8

49

2

5, 1

6, 2

2, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

102

, 108

, 11

1, 1

12, 1

17, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

50

Page 51: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

22

46T

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

55, 7

99-8

10, 8

49

2

16, 2

2, 2

8, 5

1-70

, 91,

102

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

55, 7

99-8

10, 8

49

22

47T

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

55, 7

99-8

10, 8

49

2

16, 2

2, 2

8, 5

1-70

, 91,

102

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

55, 7

99-8

10, 8

49

22

48T

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

55, 7

99-8

10, 8

49

2

16, 2

2, 2

8, 5

1-70

, 91,

102

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

55, 7

99-8

10, 8

49

22

49T

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

53, 7

99-8

10, 8

49

2

16, 2

2, 2

8, 5

1-70

, 91,

102

, 111

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

53, 7

99-8

10, 8

49

22

50T

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

51, 8

00-8

10, 8

49

2

16, 2

2, 2

8, 5

1-70

, 91,

102

, 600

-610

, 64

9-65

5, 6

99-7

05, 7

49-7

51, 8

00-8

10, 8

49

23

nat V

45

1 1,

2, 4

, 16,

22,

28,

32,

51-

74, 9

1, 1

02-1

07, 1

11,

112

2, 3

2, 5

1-74

32

16

, 22,

28,

91,

103

, 107

24

50C

r 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-56

, 91,

102

-104

, 107

2

16

, 22,

28,

51-

56, 9

1, 1

03, 1

07

24

52C

r 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-60

, 91,

102

-107

2

16

, 22,

28,

51-

60, 9

1, 1

03, 1

07

24

53C

r 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-63

, 91,

102

, 103

, 107

2

16

, 22,

28,

51-

63, 9

1, 1

03, 1

07

24

54C

r 45

1 1-

4, 1

6, 5

1-54

, 91,

102

, 103

, 107

2

16

, 51-

54, 9

1, 1

03, 1

07

25

55M

n 45

1 1,

2, 4

, 16,

22,

28,

51-

66, 9

1, 1

02-1

07, 2

03-2

07

2, 5

1-66

16, 2

2, 2

8, 9

1, 2

03-2

07

26

54Fe

45

1 1-

5, 1

6, 2

2, 2

8, 4

4, 5

1-70

, 91,

102

-108

, 111

, 112

, 11

5, 6

00-6

10, 6

49-6

55, 6

99-7

05, 7

49-7

55,

799-

810,

849

2

5, 1

6, 2

2, 2

8, 4

4, 5

1-70

, 91,

102

, 108

, 111

, 11

2, 1

15, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

26

56

Fe

451

1-5,

16,

22,

28,

51-

82, 9

1, 1

02-1

07, 6

00-6

13, 6

49,

800-

810,

849

2,

51-

82, 6

00-6

13, 8

00-8

10

5,

16,

22,

28,

91,

649

, 849

26

57Fe

45

1 1-

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 4

1, 5

1-70

, 91,

102

-108

, 11

1, 1

12, 6

00-6

10, 6

49-6

55, 6

99-7

05, 7

49-7

55,

799-

810,

849

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 4

1, 5

1-70

, 91,

102

, 10

8, 1

11, 1

12, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

26

58

Fe

451

1-5,

16,

17,

22,

28,

51-

70, 9

1, 1

02-1

08, 6

00-6

10,

649-

655,

699

-705

, 749

-752

, 800

-810

, 849

2

5,

16,

17,

22,

28,

51-

70, 9

1, 1

02, 1

08,

600-

610,

649

-655

, 699

-705

, 749

-752

, 80

0-81

0, 8

49

27

58C

o 45

1 1,

2, 4

, 16,

22,

28,

51-

62, 9

1, 1

02-1

04, 1

07, 2

51

2, 1

6, 2

2, 2

8, 5

1-62

, 91

16, 2

2, 2

8, 9

1

27

58mC

o 45

1 1,

2, 4

, 16,

22,

28,

51-

62, 9

1, 1

02-1

04, 1

07, 2

51

2, 1

6, 2

2, 2

8, 5

1-62

, 91

16, 2

2, 2

8, 9

1

27

59C

o 45

1 1,

2, 4

, 16,

22,

28,

32,

33,

51-

69, 9

1, 1

02-1

08, 1

11,

112

2, 1

6, 2

2, 2

8, 3

2, 3

3, 5

1-69

, 91

16, 2

2, 2

8, 3

2, 3

3, 9

1

28

58N

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-58

, 91,

102

-107

, 112

2

16

, 22,

28,

51-

58, 9

1, 1

03, 1

07

28

59N

i 45

1 1-

3, 1

6, 2

2, 2

8, 3

2, 3

4, 1

02-1

07, 1

11

2, 1

6, 2

2, 2

8, 3

2, 3

4 16

, 22,

28,

32,

34

28

60N

i 45

1 1-

4, 1

6, 2

2, 2

8, 5

1-61

, 91,

102

-107

2

16

, 22,

28,

51-

61, 9

1, 1

03, 1

07

28

61N

i 45

1 1-

5, 1

6, 2

8, 5

1-58

, 91,

102

, 103

, 107

, 111

2

5,

16,

28,

51-

58, 9

1, 1

03, 1

07

28

62N

i 45

1 1-

5, 1

6, 2

2, 2

8, 5

1-54

, 91,

102

-104

, 107

2

5,

16,

22,

28,

51-

54, 9

1, 1

03, 1

07

51

Page 52: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

28

64N

i 45

1 1-

5, 1

6, 2

2, 2

8, 5

1, 5

2, 9

1, 1

02-1

04, 1

07

2

5, 1

6, 2

2, 2

8, 5

1, 5

2, 9

1, 1

03, 1

07

29

63C

u 45

1 1-

5, 1

6, 2

2, 2

8, 5

1-72

, 91,

102

-104

, 106

, 107

2

5,

16,

22,

28,

51-

72, 9

1, 1

03, 1

07

29

65C

u 45

1 1-

5, 1

6, 2

2, 2

8, 5

1-63

, 91,

102

-107

2

5,

16,

22,

28,

51-

63, 9

1, 1

03, 1

07

30

nat Z

n 45

1 1,

2, 4

, 16,

17,

22,

28,

51,

91,

102

, 103

, 105

, 107

, 25

1-25

3 2,

16,

17,

22,

28,

51,

91

16, 1

7, 2

2, 2

8, 9

1

31

nat G

a 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

88, 9

1, 1

02-1

07, 1

11,

251

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-88

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

32

70G

e 45

1 1-

5, 1

6, 2

2, 2

4, 2

8, 2

9, 3

2, 4

4, 4

5, 5

1-70

, 91,

10

2-10

8, 1

11, 1

12, 1

15, 1

17, 6

00-6

10, 6

49-6

55,

699-

705,

749

-755

, 799

-810

, 849

2

5, 1

6, 2

2, 2

4, 2

8, 2

9, 3

2, 4

4, 4

5, 5

1-70

, 91,

10

2, 1

08, 1

11, 1

12, 1

15, 1

17, 6

00-6

10,

649-

655,

699

-705

, 749

-755

, 799

-810

, 849

32

72

Ge

451

1-5,

16,

17,

22,

24,

28,

32,

51-

70, 9

1, 1

02-1

08,

111,

112

, 600

-610

, 649

-655

, 699

-705

, 749

-755

, 79

9-81

0, 8

49

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 5

1-70

, 91,

102

, 108

, 11

1, 1

12, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

32

73

Ge

451

1-5,

16,

17,

22,

24,

28,

32,

33,

41,

51-

70, 9

1,

102-

108,

111

, 112

, 600

-610

, 649

-655

, 699

-705

, 74

9-75

5, 7

99-8

10, 8

49

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2, 1

08, 1

11, 1

12, 6

00-6

10, 6

49-6

55,

699-

705,

749

-755

, 799

-810

, 849

32

74

Ge

451

1-5,

16,

17,

22,

28,

32,

51-

70, 9

1, 1

02-1

07, 1

11,

600-

610,

649

-655

, 699

-705

, 749

-754

, 800

-810

, 84

9

2

5, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-70

, 91,

102

, 111

, 60

0-61

0, 6

49-6

55, 6

99-7

05, 7

49-7

54,

800-

810,

849

32

76

Ge

451

1-5,

16,

17,

22,

28,

51-

70, 9

1, 1

02-1

05, 1

07,

600-

610,

649

-655

, 699

-705

, 749

, 800

-804

, 849

2

5,

16,

17,

22,

28,

51-

70, 9

1, 1

02, 6

00-6

10,

649-

655,

699

-705

, 749

, 800

-804

, 849

33

75

As

451

1, 2

, 4, 5

1-63

, 91,

102

-107

, 111

, 251

-253

2,

51-

63, 9

1 91

34

74Se

45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

34

76Se

45

1 1,

2, 4

, 51-

54, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-54

, 91

91

34

77Se

45

1 1,

2, 4

, 51-

60, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-60

, 91

91

34

78Se

45

1 1,

2, 4

, 51-

59, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-59

, 91

91

34

79Se

45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

79, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-79

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

34

80Se

45

1 1,

2, 4

, 51-

58, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-58

, 91

91

34

82Se

45

1 1,

2, 4

, 51-

53, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-53

, 91

91

35

79B

r 45

1 1,

2, 4

, 51-

61, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-61

, 91

91

35

81B

r 45

1 1,

2, 4

, 51-

54, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-54

, 91

91

36

78K

r 45

1 1,

2, 4

, 16,

51-

53, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 5

1-53

, 91

16, 9

1

36

80K

r 45

1 1,

2, 4

, 16,

51-

56, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 5

1-56

, 91

16, 9

1

36

82K

r 45

1 1,

2, 4

, 16,

51-

59, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 5

1-59

, 91

16, 9

1

36

83K

r 45

1 1,

2, 4

, 16,

17,

51-

56, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 1

7, 5

1-56

, 91

16, 1

7, 9

1

52

Page 53: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

36

84K

r 45

1 1,

2, 4

, 16,

51-

63, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 5

1-63

, 91

16, 9

1

36

85K

r 45

1 1,

2, 4

, 51,

91,

102

-107

, 111

2,

51,

91

91

36

86K

r 45

1 1,

2, 4

, 16,

17,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 1

7, 5

1-64

, 91

16, 1

7, 9

1

37

85R

b 45

1 1,

2, 4

, 51-

53, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-53

, 91

91

37

86R

b 45

1 1,

2, 4

, 51,

91,

102

-107

, 111

2,

51,

91

91

37

87R

b 45

1 1,

2, 4

, 51,

52,

91,

102

-107

, 111

, 251

-253

2,

51,

52,

91

91

38

84Sr

45

1 1,

2, 4

, 91,

102

-107

, 111

2,

91

91

38

86Sr

45

1 1,

2, 4

, 51-

57, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-57

, 91

91

38

87Sr

45

1 1,

2, 4

, 51-

57, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-57

, 91

91

38

88Sr

45

1 1,

2, 4

, 51-

55, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-55

, 91

91

38

89Sr

45

1 1,

2, 4

, 51-

62, 9

1, 1

02-1

07, 1

11

2, 5

1-62

, 91

91

38

90Sr

45

1 1,

2, 4

, 51-

54, 9

1, 1

02-1

07, 1

11

2, 5

1-54

, 91

91

39

89Y

45

1 1,

2, 4

, 16,

22,

28,

51-

62, 9

1, 1

02-1

07

2, 1

6, 2

2, 2

8, 5

1-62

, 91

16, 2

2, 2

8, 9

1

39

90Y

45

1 1,

2, 4

, 51,

52,

91,

102

-107

, 111

2,

51,

52,

91

91

39

91Y

45

1 1,

2, 4

, 51-

58, 9

1, 1

02, 1

04-1

07, 1

11

2, 5

1-58

, 91

91

40

90Z

r 45

1 1-

4, 1

6, 2

2, 2

8, 3

2, 5

1-57

, 91,

102

-107

, 111

, 20

3-20

7 2,

51-

57

16

, 22,

28,

32,

91,

203

-207

40

91Z

r 45

1 1-

4, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-64

, 91,

102

-107

, 20

3-20

7 2,

51-

64

16

, 17,

22,

28,

32,

91,

203

-207

40

92Z

r 45

1 1-

4, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-67

, 91,

102

-105

, 10

7, 2

03-2

05, 2

07

2, 5

1-67

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1, 2

03-2

05, 2

07

40

93Z

r 45

1 1,

2, 4

, 16,

22,

28,

51-

62, 9

1, 1

02-1

07, 1

11, 2

51,

252

2, 1

6, 2

2, 2

8, 5

1-62

, 91

16, 2

2, 2

8, 9

1

40

94Z

r 45

1 1-

4, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-64

, 91,

102

-105

, 107

, 20

3-20

5, 2

07

2, 5

1-64

16, 1

7, 2

2, 2

8, 3

2, 9

1, 2

03-2

05, 2

07

40

95Z

r 45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-64

, 91

16, 9

1

40

96Z

r 45

1 1-

4, 1

6, 1

7, 2

2, 2

8, 5

1-57

, 91,

102

-105

, 107

, 20

3-20

5, 2

07

2, 5

1-57

16, 1

7, 2

2, 2

8, 9

1, 2

03-2

05, 2

07

41

93N

b 45

1 1,

2, 4

, 5, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-73

, 91,

10

2-10

5, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-73

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1 5

41

94N

b 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

79, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-79

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

41

95N

b 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

70, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-70

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

42

100 M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

54, 9

1, 1

02-1

05, 1

07,

203-

205,

207

2,

51-

54

16

, 17,

22,

28,

91,

203

-205

, 207

53

Page 54: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

42

92M

o 45

1 1,

2, 4

, 16,

22,

28,

51-

66, 9

1, 1

02-1

07, 1

11,

203-

207

2, 5

1-66

16, 2

2, 2

8, 9

1, 2

03-2

07

42

94M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

69, 9

1, 1

02-1

07, 1

11,

203-

207

2, 5

1-69

16, 1

7, 2

2, 2

8, 9

1, 2

03-2

07

42

95M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

54, 9

1, 1

02, 1

03, 1

07,

112,

600

, 601

, 649

, 800

-805

, 849

2,

51-

54, 6

00, 6

01, 8

00-8

05

16

, 17,

22,

28,

91,

102

, 649

, 849

42

96M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

67, 9

1, 1

02-1

05, 1

07,

203-

205,

207

2,

51-

67

16

, 17,

22,

28,

91,

203

-205

, 207

42

97M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

63, 9

1, 1

02-1

07, 2

03-2

07

2, 5

1-63

16, 1

7, 2

2, 2

8, 9

1, 2

03-2

07

42

98M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

64, 9

1, 1

02-1

05, 1

07,

203-

205,

207

2,

51-

64

16

, 17,

22,

28,

91,

203

-205

, 207

42

99M

o 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

66, 9

1, 1

02-1

05,

107

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-66

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

43

99T

c 45

1 1-

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2-10

8, 1

11, 1

12, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

755,

799

-810

, 849

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2, 1

08, 1

11, 1

12, 6

00-6

10, 6

49-6

55,

699-

705,

749

-755

, 799

-810

, 849

44

10

0 Ru

451

1, 2

, 4, 5

1-57

, 91,

102

-107

, 111

, 251

-253

2,

51-

57, 9

1 91

44

101 R

u 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

65, 9

1, 1

02, 1

03, 1

07,

251-

253

2, 1

6, 1

7, 2

2, 2

8, 5

1-65

, 91

16, 1

7, 2

2, 2

8, 9

1

44

102 R

u 45

1 1,

2, 4

, 51-

69, 9

1, 1

02-1

07, 1

11

2, 5

1-69

, 91

91

44

103 R

u 45

1 1,

2, 4

, 16,

51-

89, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-89

, 91

16, 9

1

44

104 R

u 45

1 1,

2, 4

, 51,

52,

91,

102

-107

, 111

, 251

-253

2,

51,

52,

91

91

44

105 R

u 45

1 1,

2, 4

, 51-

59, 9

1, 1

02-1

07, 1

11

2, 5

1-59

, 91

91

44

106 R

u 45

1 1,

2, 4

, 51-

54, 9

1, 1

02-1

07, 1

11

2, 5

1-54

, 91

91

44

96R

u 45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

44

98R

u 45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

44

99R

u 45

1 1,

2, 4

, 51-

62, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-62

, 91

91

45

103 R

h 45

1 1-

5, 1

1, 1

6, 1

7, 2

2, 2

4, 2

5, 2

8, 2

9, 3

2-34

, 37,

41,

42

, 44,

45,

51-

65, 9

1, 1

02-1

08, 1

11, 1

12, 1

15-1

17,

600-

615,

649

-665

, 699

-715

, 749

-765

, 799

-815

, 84

9

2

5, 1

1, 1

6, 1

7, 2

2, 2

4, 2

5, 2

8, 2

9, 3

2-34

, 37,

41

, 42,

44,

45,

51-

65, 9

1, 1

08, 1

11, 1

12,

115-

117,

600

-615

, 649

-665

, 699

-715

, 74

9-76

5, 7

99-8

15, 8

49

45

105 R

h 45

1 1,

2, 4

, 51-

53, 9

1, 1

02

2, 5

1-53

, 91

91

46

102 Pd

45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

46

104 Pd

45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-64

, 91

16, 9

1

46

105 Pd

45

1 1,

2, 4

, 16,

51-

91, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-91

16

, 91

46

106 Pd

45

1 1,

2, 4

, 16,

51-

70, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-70

, 91

16, 9

1

54

Page 55: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

46

107 Pd

45

1 1,

2, 4

, 16,

51-

67, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-67

, 91

16, 9

1

46

108 Pd

45

1 1,

2, 4

, 16,

51-

60, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-60

, 91

16, 9

1

46

110 Pd

45

1 1,

2, 4

, 16,

51-

60, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-60

, 91

16, 9

1

47

107 A

g 45

1 1,

2, 4

, 16,

51-

56, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 5

1-56

, 91

16, 9

1

47

109 A

g 45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-64

, 91

16, 9

1

47

110m

Ag

451

1, 2

, 4, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-79

, 91,

102

-107

2,

16,

17,

22,

28,

32,

33,

51-

79, 9

1 16

, 17,

22,

28,

32,

33,

91

47

111 A

g 45

1 1,

2, 4

, 51-

60, 9

1, 1

02-1

07, 1

11

2, 5

1-60

, 91

91

48

106 C

d 45

1 1,

2, 4

, 16,

22,

28,

32,

33,

51-

55, 9

1, 1

02-1

07

2, 1

6, 2

2, 2

8, 3

2, 3

3, 5

1-55

, 91

16, 2

2, 2

8, 3

2, 3

3, 9

1

48

108 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

60, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-60

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

48

110 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

64, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-64

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

48

111 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

61, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-61

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

48

112 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

58, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-58

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

48

113 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

62, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-62

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

48

114 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

60, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-60

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

48

115m

Cd

451

1, 2

, 4, 9

1, 1

02-1

07, 1

11

2, 9

1 91

48

116 C

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

56, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-56

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

49

113 In

45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

74, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-74

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

49

115 In

45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

63, 9

1, 1

02-1

05,

107

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-63

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

50

112 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

73, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 2

2, 2

8, 5

1-73

, 91

16, 1

7, 2

2, 2

8, 9

1

50

114 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

76, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-76

, 91

16, 1

7, 2

2, 2

8, 9

1

50

115 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

66, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-66

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

50

116 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

60, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-60

, 91

16, 1

7, 2

2, 2

8, 9

1

50

117 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

62, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-62

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

50

118 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

57, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-57

, 91

16, 1

7, 2

2, 2

8, 9

1

50

119 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

70, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-70

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

50

120 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

66, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-66

, 91

16, 1

7, 2

2, 2

8, 9

1

50

122 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

59, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-59

, 91

16, 1

7, 2

2, 2

8, 9

1

50

123 Sn

45

1 1,

2, 4

, 51-

59, 9

1, 1

02-1

07, 1

11

2, 5

1-59

, 91

91

50

124 Sn

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

70, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-70

, 91

16, 1

7, 2

2, 2

8, 9

1

50

125 Sn

45

1 1,

2, 4

, 51-

53, 9

1, 1

02-1

07, 1

11

2, 5

1-53

, 91

91

55

Page 56: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

50

126 Sn

45

1 1,

2, 4

, 51-

60, 9

1, 1

02-1

07, 1

11

2, 5

1-60

, 91

91

51

121 Sb

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

63, 9

1, 1

02-1

05, 1

07,

203-

205,

207

2,

51-

63

16

, 17,

22,

28,

91,

203

-205

, 207

51

123 Sb

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

58, 9

1, 1

02-1

05, 1

07,

203-

205,

207

2,

51-

58

16

, 17,

22,

28,

91,

203

-205

, 207

51

124 Sb

45

1 1,

2, 4

, 51-

58, 9

1, 1

02-1

05, 1

07, 1

11

2, 5

1-58

, 91

91

51

125 Sb

45

1 1,

2, 4

, 51-

69, 9

1, 1

02-1

07, 1

11

2, 5

1-69

, 91

91

51

126 Sb

45

1 1,

2, 4

, 51-

55, 9

1, 1

02-1

07, 1

11

2, 5

1-55

, 91

91

52

120 T

e 45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

52

122 T

e 45

1 1,

2, 4

, 51-

54, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-54

, 91

91

52

123 T

e 45

1 1,

2, 4

, 51-

58, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-58

, 91

91

52

124 T

e 45

1 1,

2, 4

, 51-

61, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-61

, 91

91

52

125 T

e 45

1 1,

2, 4

, 51-

56, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-56

, 91

91

52

126 T

e 45

1 1,

2, 4

, 51-

63, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-63

, 91

91

52

127m

Te

451

1, 2

, 4, 9

1, 1

02

2, 9

1 91

52

128 T

e 45

1 1,

2, 4

, 51-

59, 9

1, 1

02-1

07, 1

11, 2

51

2, 5

1-59

, 91

91

52

129m

Te

451

1, 2

, 4, 9

1, 1

02-1

07, 1

11

2, 9

1 91

52

130 T

e 45

1 1,

2, 4

, 51-

60, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-60

, 91

91

52

132 T

e 45

1 1,

2, 4

, 51-

56, 9

1, 1

02-1

07, 1

11

2, 5

1-56

, 91

91

53

127 I

451

1-5,

11,

16,

17,

22,

24,

25,

28,

32-

34, 3

7, 4

1, 4

2,

44, 4

5, 5

1-65

, 91,

102

-108

, 111

, 112

, 115

-117

, 60

0-61

5, 6

49-6

65, 6

99-7

15, 7

49-7

65, 7

99-8

15,

849

2

5, 1

1, 1

6, 1

7, 2

2, 2

4, 2

5, 2

8, 3

2-34

, 37,

41,

42

, 44,

45,

51-

65, 9

1, 1

08, 1

11, 1

12,

115-

117,

600

-615

, 649

-665

, 699

-715

, 74

9-76

5, 7

99-8

15, 8

49

53

129 I

451

1-5,

11,

16,

17,

22,

24,

25,

28,

32-

34, 3

7, 4

1, 4

2,

44, 4

5, 5

1-65

, 91,

102

-107

, 111

, 112

, 115

-117

, 60

0-61

5, 6

49-6

65, 6

99-7

15, 7

49-7

65, 7

99-8

05,

849

2

5, 1

1, 1

6, 1

7, 2

2, 2

4, 2

5, 2

8, 3

2-34

, 37,

41,

42

, 44,

45,

51-

65, 9

1, 1

11, 1

12, 1

15-1

17,

600-

615,

649

-665

, 699

-715

, 749

-765

, 79

9-80

5, 8

49

53

130 I

451

1, 2

, 4, 9

1, 1

02-1

07, 1

11

2, 9

1 91

53

131 I

451

1, 2

, 4, 5

1-54

, 91,

102

-107

, 111

2,

51-

54, 9

1 91

53

135 I

451

1, 2

, 4, 9

1, 1

02

2, 9

1 91

54

124 X

e 45

1 1,

2, 4

, 16,

17,

51-

54, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 5

1-54

, 91

16, 1

7, 9

1

54

126 X

e 45

1 1,

2, 4

, 16,

17,

51-

54, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 5

1-54

, 91

16, 1

7, 9

1

54

128 X

e 45

1 1,

2, 4

, 16,

17,

51-

53, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 5

1-53

, 91

16, 1

7, 9

1

54

129 X

e 45

1 1,

2, 4

, 16,

17,

51-

56, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 5

1-56

, 91

16, 1

7, 9

1

56

Page 57: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

54

130 X

e 45

1 1,

2, 4

, 16,

17,

51-

56, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 5

1-56

, 91

16, 1

7, 9

1

54

131 X

e 45

1 1,

2, 4

, 16,

17,

51-

56, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 1

7, 5

1-56

, 91

16, 1

7, 9

1

54

132 X

e 45

1 1,

2, 4

, 16,

17,

51-

54, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 1

7, 5

1-54

, 91

16, 1

7, 9

1

54

133 X

e 45

1 1,

2, 4

, 51,

91,

102

-107

, 111

2,

51,

91

91

54

134 X

e 45

1 1,

2, 4

, 16,

17,

51-

53, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 1

6, 1

7, 5

1-53

, 91

16, 1

7, 9

1

54

135 X

e 45

1 1,

2, 4

, 51,

91,

102

2,

51,

91

91

54

136 X

e 45

1 1,

2, 4

, 16,

17,

51-

53, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 5

1-53

, 91

16, 1

7, 9

1

55

133 C

s 45

1 1,

2, 4

, 16,

51-

55, 9

1, 1

02, 1

03, 1

07

2, 1

6, 5

1-55

, 91

16, 9

1

55

134 C

s 45

1 1,

2, 4

, 51-

55, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-55

, 91

91

55

135 C

s 45

1 1,

2, 4

, 16,

51-

68, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-68

, 91

16, 9

1

55

136 C

s 45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

55

137 C

s 45

1 1,

2, 4

, 16,

51-

60, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-60

, 91

16, 9

1

56

130 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

57, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-57

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

56

132 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

60, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-60

, 91

16, 1

7, 2

2, 2

8, 9

1

56

134 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

63, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-63

, 91

16, 1

7, 2

2, 2

8, 9

1

56

135 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

57, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-57

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

56

136 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

60, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-60

, 91

16, 1

7, 2

2, 2

8, 9

1

56

137 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

58, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-58

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

56

138 B

a 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

69, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-69

, 91

16, 1

7, 2

2, 2

8, 9

1

56

140 B

a 45

1 1,

2, 4

, 16,

17,

91,

102

-107

, 111

, 251

, 252

2,

16,

17,

91

16, 1

7, 9

1

57

138 L

a 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

65, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-65

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

57

139 L

a 45

1 1,

2, 4

, 16,

51-

73, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-73

, 91

16, 9

1

57

140 L

a 45

1 1,

2, 4

, 51-

56, 9

1, 1

02, 1

04-1

07, 1

11

2, 5

1-56

, 91

91

58

140 C

e 45

1 1,

2, 4

, 51-

58, 9

1, 1

02-1

07, 1

11

2, 5

1-58

, 91

91

58

141 C

e 45

1 1,

2, 4

, 16,

51-

62, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-62

, 91

16, 9

1

58

142 C

e 45

1 1,

2, 4

, 16,

17,

51-

56, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 1

7, 5

1-56

, 91

16, 1

7, 9

1

58

143 C

e 45

1 1,

2, 4

, 91,

102

-107

, 111

2,

91

91

58

144 C

e 45

1 1,

2, 4

, 16,

17,

51-

68, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 1

7, 5

1-68

, 91

16, 1

7, 9

1

59

141 Pr

45

1 1,

2, 4

, 16,

51-

74, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-74

, 91

16, 9

1

59

142 Pr

45

1 1,

2, 4

, 91,

102

-107

, 111

2,

91

91

57

Page 58: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

59

143 Pr

45

1 1,

2, 4

, 51-

56, 9

1, 1

02-1

07, 1

11

2, 5

1-56

, 91

91

60

142 N

d 45

1 1,

2, 4

, 51-

58, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-58

, 91

91

60

143 N

d 45

1 1,

2, 4

, 16,

51-

76, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-76

, 91

16, 9

1

60

144 N

d 45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-64

, 91

16, 9

1

60

145 N

d 45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-64

, 91

16, 9

1

60

146 N

d 45

1 1,

2, 4

, 16,

51-

63, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-63

, 91

16, 9

1

60

147 N

d 45

1 1,

2, 4

, 51-

53, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-53

, 91

91

60

148 N

d 45

1 1,

2, 4

, 16,

51-

57, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-57

, 91

16, 9

1

60

150 N

d 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

59, 9

1, 1

02-1

07, 1

11,

251-

253

2, 1

6, 1

7, 2

2, 2

8, 5

1-59

, 91

16, 1

7, 2

2, 2

8, 9

1

61

147 Pm

45

1 1,

2, 4

, 16,

51-

61, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-61

, 91

16, 9

1

61

148 Pm

45

1 1,

2, 4

, 91,

102

2,

91

91

61

148m

Pm

451

1, 2

, 4, 9

1, 1

02, 2

51-2

53

2, 9

1 91

61

149 Pm

45

1 1,

2, 4

, 51-

56, 9

1, 1

02-1

07, 1

11

2, 5

1-56

, 91

91

61

151 Pm

45

1 1,

2, 4

, 51-

56, 9

1, 1

02-1

07, 1

11

2, 5

1-56

, 91

91

62

144 Sm

45

1 1,

2, 4

, 91,

102

-107

, 111

, 251

-253

2,

91

91

62

147 Sm

45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-64

, 91

16, 9

1

62

148 Sm

45

1 1,

2, 4

, 51-

66, 9

1, 1

02-1

07, 1

11

2, 5

1-66

, 91

91

62

149 Sm

45

1 1,

2, 4

, 16,

17,

51-

60, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-60

, 91

16, 1

7, 9

1

62

150 Sm

45

1 1,

2, 4

, 51-

66, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-66

, 91

91

62

151 Sm

45

1 1,

2, 4

, 16,

51-

91, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-91

16

, 91

62

152 Sm

45

1 1,

2, 4

, 16,

51-

63, 9

1, 1

02-1

07, 1

11, 2

51, 2

52

2, 1

6, 5

1-63

, 91

16, 9

1

62

153 Sm

45

1 1,

2, 4

, 51-

62, 9

1, 1

02-1

07, 1

11

2, 5

1-62

, 91

91

62

154 Sm

45

1 1,

2, 4

, 51-

69, 9

1, 1

02-1

07, 1

11, 2

51-2

53

2, 5

1-69

, 91

91

63

151 E

u 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

59, 9

1, 1

02-1

07, 1

11

2, 1

6, 1

7, 2

2, 2

8, 5

1-59

, 91

16, 1

7, 2

2, 2

8, 9

1

63

152 E

u 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

61, 9

1, 1

02-1

07,

251

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-61

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

63

153 E

u 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

61, 9

1, 1

02, 1

03, 1

07,

251

2, 1

6, 1

7, 2

2, 2

8, 5

1-61

, 91

16, 1

7, 2

2, 2

8, 9

1

63

154 E

u 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

55, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-55

, 91

16, 1

7, 2

2, 2

8, 9

1

63

155 E

u 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

59, 9

1, 1

02-1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-59

, 91

16, 1

7, 2

2, 2

8, 9

1

63

156 E

u 45

1 1,

2, 4

, 51-

55, 9

1, 1

02-1

07, 1

11

2, 5

1-55

, 91

91

58

Page 59: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

63

157 E

u 45

1 1,

2, 4

, 91,

102

2,

91

91

64

152 G

d 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

33,

51-

79, 9

1, 1

02-1

07,

251

2, 1

6, 1

7, 2

2, 2

8, 3

2, 3

3, 5

1-79

, 91

16, 1

7, 2

2, 2

8, 3

2, 3

3, 9

1

64

154 G

d 45

1 1,

2, 4

, 51-

65, 9

1, 1

02-1

07, 1

11

2, 5

1-65

, 91

91

64

155 G

d 45

1 1,

2, 4

, 51-

79, 9

1, 1

02-1

07, 1

11, 2

51

2, 5

1-79

, 91

91

64

156 G

d 45

1 1,

2, 4

, 16,

51-

64, 9

1, 1

02-1

07, 1

11

2, 1

6, 5

1-64

, 91

16, 9

1

64

157 G

d 45

1 1,

2, 4

, 51-

78, 9

1, 1

02-1

07, 1

11, 2

51

2, 5

1-78

, 91

91

64

158 G

d 45

1 1,

2, 4

, 51-

61, 9

1, 1

02-1

07, 1

11

2, 5

1-61

, 91

91

64

160 G

d 45

1 1,

2, 4

, 51-

56, 9

1, 1

02-1

05, 1

07

2, 5

1-56

, 91

91

65

159 T

b 45

1 1,

2, 4

, 16,

51-

66, 9

1, 1

02, 2

51, 2

52

2, 1

6, 5

1-66

, 91

16, 9

1

65

160 T

b 45

1 1,

2, 4

, 91,

102

, 251

-253

2,

91

91

66

160 D

y 45

1 1,

2, 4

, 51-

64, 9

1, 1

02, 2

51-2

53

2, 5

1-64

, 91

91

66

161 D

y 45

1 1,

2, 4

, 51-

57, 9

1, 1

02

2, 5

1-57

, 91

91

66

162 D

y 45

1 1,

2, 4

, 51-

56, 9

1, 1

02

2, 5

1-56

, 91

91

66

163 D

y 45

1 1,

2, 4

, 51-

56, 9

1, 1

02

2, 5

1-56

, 91

91

66

164 D

y 45

1 1,

2, 4

, 16,

17,

51-

62, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-62

, 91

16, 1

7, 9

1

67

165 H

o 45

1 1,

2, 4

, 16,

17,

37,

51-

63, 9

1, 1

02

2, 1

6, 1

7, 3

7, 5

1-63

, 91

16, 1

7, 3

7, 9

1

68

162 E

r 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

67, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-67

, 91

16, 1

7, 2

2, 2

8, 9

1

68

164 E

r 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

66, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-66

, 91

16, 1

7, 2

2, 2

8, 9

1

68

166 E

r 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

74, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-74

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

68

167 E

r 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

73, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-73

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

68

168 E

r 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

79, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-79

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

68

170 E

r 45

1 1,

2, 4

, 16,

17,

22,

28,

32,

51-

64, 9

1, 1

02-1

05, 1

07

2, 1

6, 1

7, 2

2, 2

8, 3

2, 5

1-64

, 91

16, 1

7, 2

2, 2

8, 3

2, 9

1

71

175 L

u 45

1 1,

2, 4

, 16,

17,

51-

58, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-58

, 91

16, 1

7, 9

1

71

176 L

u 45

1 1,

2, 4

, 16,

17,

51-

58, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-58

, 91

16, 1

7, 9

1

72

174 H

f 45

1 1,

2, 4

, 16,

17,

51-

68, 9

1, 1

02

2, 1

6, 1

7, 5

1-68

, 91

16, 1

7, 9

1

72

176 H

f 45

1 1,

2, 4

, 16,

17,

51-

73, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-73

, 91

16, 1

7, 9

1

72

177 H

f 45

1 1,

2, 4

, 16,

17,

51-

66, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-66

, 91

16, 1

7, 9

1

72

178 H

f 45

1 1,

2, 4

, 16,

17,

51-

71, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-71

, 91

16, 1

7, 9

1

72

179 H

f 45

1 1,

2, 4

, 16,

17,

51-

62, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-62

, 91

16, 1

7, 9

1

72

180 H

f 45

1 1,

2, 4

, 16,

17,

51-

61, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 5

1-61

, 91

16, 1

7, 9

1

59

Page 60: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

73

181 T

a 45

1 1,

2, 4

, 16,

17,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 2

8, 5

1-64

, 91

16, 1

7, 2

8, 9

1

73

182 T

a 45

1 1,

2, 4

, 16,

17,

51-

58, 9

1, 1

02, 1

07, 2

51-2

53

2, 1

6, 1

7, 5

1-58

, 91

16, 1

7, 9

1

74

182 W

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

70, 9

1, 1

02-1

04, 1

07,

203,

204

, 207

2,

51-

70

16

, 17,

22,

28,

91,

203

, 204

, 207

74

183 W

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

60, 9

1, 1

02-1

04, 1

07,

203,

204

, 207

2,

51-

60

16

, 17,

22,

28,

91,

203

, 204

, 207

74

184 W

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

60, 9

1, 1

02-1

04, 1

07,

203,

204

, 207

2,

51-

60

16

, 17,

22,

28,

91,

203

, 204

, 207

74

186 W

45

1 1,

2, 4

, 16,

17,

22,

28,

51-

62, 9

1, 1

02-1

04, 1

07,

203,

204

, 207

2,

51-

62

16

, 17,

22,

28,

91,

203

, 204

, 207

75

185 R

e 45

1 1,

2, 4

, 16,

17,

51-

59, 9

1, 1

02

2, 1

6, 1

7, 5

1-59

, 91

16, 1

7, 9

1

75

187 R

e 45

1 1,

2, 4

, 16,

17,

51-

66, 9

1, 1

02

2, 1

6, 1

7, 5

1-66

, 91

16, 1

7, 9

1

76

nat O

s 45

1 1,

2, 4

, 16,

17,

51-

67, 9

1, 1

02, 1

03, 1

07, 2

51-2

53

2, 1

6, 1

7, 5

1-67

, 91

16, 1

7, 9

1

77

191 Ir

45

1 1,

2, 4

, 16,

17,

51-

54, 9

1, 1

02, 1

03, 1

07, 2

51-2

53

2, 1

6, 1

7, 5

1-54

, 91

16, 1

7, 9

1

77

193 Ir

45

1 1,

2, 4

, 16,

17,

51-

54, 9

1, 1

02, 1

03, 1

07, 2

51-2

53

2, 1

6, 1

7, 5

1-54

, 91

16, 1

7, 9

1

78

nat Pt

45

1 1,

2, 4

, 16,

17,

91,

102

, 251

-253

2,

16,

17,

91

16, 1

7, 9

1

79

197 A

u 45

1 1,

2, 4

, 16,

17,

37,

51-

63, 9

1, 1

02, 1

03, 1

07

2, 1

6, 1

7, 3

7, 5

1-63

, 91

16, 1

7, 3

7, 9

1

80

196 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

70, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-70

, 91

16, 1

7, 2

2, 2

8, 9

1

80

198 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-69

, 91

16, 1

7, 2

2, 2

8, 9

1

80

199 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

63, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-63

, 91

16, 1

7, 2

2, 2

8, 9

1

80

200 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

84, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-84

, 91

16, 1

7, 2

2, 2

8, 9

1

80

201 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

63, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-63

, 91

16, 1

7, 2

2, 2

8, 9

1

80

202 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-69

, 91

16, 1

7, 2

2, 2

8, 9

1

80

204 H

g 45

1 1,

2, 4

, 16,

17,

22,

28,

51-

68, 9

1, 1

02-1

04, 1

07

2, 1

6, 1

7, 2

2, 2

8, 5

1-68

, 91

16, 1

7, 2

2, 2

8, 9

1

81

nat T

l 45

1 1-

4, 1

6, 1

7, 2

2, 2

8, 5

1-66

, 91,

102

-105

, 107

2,

51-

66

16

, 17,

22,

28,

91

82

204 Pb

45

1 1-

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-71

, 91,

10

2-10

7, 1

11, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

753,

799

-810

, 849

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-71

, 91,

10

2, 1

11, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

753,

799

-810

, 849

82

20

6 Pb

451

1-5,

16,

17,

22,

24,

28,

32,

33,

41,

51-

75, 9

1,

102-

105,

107

, 108

, 600

-610

, 649

-655

, 699

-705

, 74

9, 8

00-8

10, 8

49

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-75

, 91,

10

2, 1

08, 6

00-6

10, 6

49-6

55, 6

99-7

05, 7

49,

800-

810,

849

82

20

7 Pb

451

1-5,

16,

17,

22,

24,

28,

32,

33,

41,

51-

70, 9

1,

102-

105,

107

, 600

-610

, 649

-655

, 699

-705

, 749

, 80

0-81

0, 8

49

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2, 6

00-6

10, 6

49-6

55, 6

99-7

05, 7

49,

800-

810,

849

60

Page 61: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

82

208 Pb

45

1 1-

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2-10

5, 1

07, 6

00-6

07, 6

49-6

55, 6

99-7

05, 7

49,

800-

810,

849

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2, 6

00-6

07, 6

49-6

55, 6

99-7

05, 7

49,

800-

810,

849

83

20

9 Bi

451

1-5,

16,

17,

22,

24,

28,

32,

33,

41,

51-

70, 9

1,

102-

108,

112

, 600

-610

, 649

-655

, 699

-705

, 74

9-75

4, 7

99-8

10, 8

49

2

5, 1

6, 1

7, 2

2, 2

4, 2

8, 3

2, 3

3, 4

1, 5

1-70

, 91,

10

2, 1

08, 1

12, 6

00-6

10, 6

49-6

55, 6

99-7

05,

749-

754,

799

-810

, 849

88

22

3 Ra

451,

452

1,

2, 4

, 16-

18, 3

7, 5

1-64

, 91,

102

2,

16-

18, 3

7, 5

1-64

, 91

16-1

8, 3

7, 9

1

88

224 R

a 45

1 1,

2, 4

, 16,

17,

37,

51-

61, 9

1, 1

02

2, 1

6, 1

7, 3

7, 5

1-61

, 91

16, 1

7, 3

7, 9

1

88

225 R

a 45

1 1,

2, 4

, 16,

17,

37,

51-

56, 9

1, 1

02

2, 1

6, 1

7, 3

7, 5

1-56

, 91

16, 1

7, 3

7, 9

1

88

226 R

a 45

1, 4

52

1, 2

, 4, 1

6-18

, 37,

51-

66, 9

1, 1

02

2, 1

6-18

, 37,

51-

66, 9

1 16

-18,

37,

91

89

225 A

c 45

1 1,

2, 4

, 16,

17,

37,

51,

91,

102

2,

16,

17,

37,

51,

91

16, 1

7, 3

7, 9

1

89

226 A

c 45

1 1,

2, 4

, 16,

17,

37,

91,

102

2,

16,

17,

37,

91

16, 1

7, 3

7, 9

1 ,

89

227 A

c 45

1, 4

52

1, 2

, 4, 1

6-18

, 37,

51-

59, 9

1, 1

02

2, 1

6-18

, 37,

51-

59, 9

1 16

-18,

37,

91

90

227 T

h 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

91,

102

2,

16-

18, 3

7, 9

1 16

-18,

37,

91,

455

90

228 T

h 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

62, 9

1, 1

02

2, 1

6-18

, 51-

62, 9

1 16

-18,

91

90

229 T

h 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51-

54, 9

1, 1

02, 2

51

2, 1

6-18

, 37,

51-

54, 9

1 16

-18,

37,

91,

455

90

230 T

h 45

1, 4

52, 4

58

1, 2

, 4, 1

6-18

, 51-

67, 9

1, 1

02, 2

51-2

53

2, 1

6-18

, 51-

67, 9

1 16

-18,

91

90

232 T

h 45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

21, 3

7, 3

8, 5

1-81

, 91,

102

2,

16-

21, 3

7, 3

8, 5

1-81

, 91

16-2

1, 3

7, 3

8, 9

1, 4

55

90

233 T

h 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

65, 9

1, 1

02

2, 1

6-18

, 51-

65, 9

1 16

-18,

91

90

234 T

h 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

67, 9

1, 1

02

2, 1

6-18

, 51-

67, 9

1 16

-18,

91

91

231 Pa

45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

62, 9

1, 1

02, 2

51-2

53

2, 1

6-18

, 51-

62, 9

1 16

-18,

91,

455

91

232 Pa

45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

91,

102

2,

16-

18, 3

7, 9

1 16

-18,

37,

91

91

233 Pa

45

1, 4

52, 4

58

1, 2

, 4, 1

6-18

, 51-

55, 9

1, 1

02, 2

51-2

53

2, 1

6-18

, 51-

55, 9

1 16

-18,

91

92

232 U

45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

63, 9

1, 1

02, 2

51-2

53

2, 1

6-18

, 51-

63, 9

1 16

-18,

91,

455

92

233 U

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 5

1-69

, 91,

102

2,

16-

18, 5

1-69

, 91

16-1

8, 9

1, 4

55

92

234 U

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

21, 3

8, 5

1-86

, 91,

102

2,

16-

21, 3

8, 5

1-86

, 91

16-2

1, 3

8, 9

1, 4

55

61

Page 62: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

92

235 U

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

21, 3

7, 3

8, 5

1-84

, 91,

102

2,

18,

51-

84

18, 4

55

16, 1

7, 3

7, 9

1

92

236 U

45

1, 4

52, 4

55,

456,

458

1-

4, 1

6-21

, 37,

38,

51-

81, 9

1, 1

02

2, 1

8, 5

1-81

18

, 455

16

, 17,

37,

91

92

237 U

45

1, 4

52, 4

55,

456

1-4,

16-

21, 3

7, 3

8, 5

1-84

, 91,

102

2,

18,

51-

84

18, 4

55

16, 1

7, 3

7, 9

1

92

238 U

45

1, 4

52, 4

55,

456,

458

1-

4, 1

6-21

, 37,

38,

51-

91, 1

02

2, 1

8, 5

1-90

18

, 455

16

, 17,

37,

91

93

235 N

p 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

66, 9

1, 1

02

2, 1

6-18

, 51-

66, 9

1 16

-18,

91

93

236 N

p 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

54, 9

1, 1

02

2, 1

6-18

, 51-

54, 9

1 16

-18,

91

93

237 N

p 45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 3

7, 5

1-82

, 91,

102

2,

18,

51-

82

18, 4

55

16, 1

7, 3

7, 9

1

93

238 N

p 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 91,

102

2,

16-

18, 9

1 16

-18,

91,

455

93

239 N

p 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

58, 9

1, 1

02

2, 1

6-18

, 51-

58, 9

1 16

-18,

91

94

236 Pu

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 5

1-54

, 91,

102

2,

16-

18, 5

1-54

, 91

16-1

8, 9

1

94

237 Pu

45

1, 4

52, 4

58

1, 2

, 4, 1

6-20

, 51-

60, 9

1, 1

02, 2

51-2

53

2, 1

6-20

, 51-

60, 9

1 16

-20,

91

94

238 Pu

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 5

1-78

, 91,

102

, 251

2,

16-

18, 5

1-78

, 91

16-1

8, 9

1, 4

55

94

239 Pu

45

1, 4

52, 4

55,

456,

458

1-

4, 1

6-18

, 37,

51-

77, 9

1, 1

02

2, 1

6-18

, 37,

51-

77, 9

1 16

-18,

37,

91,

455

94

240 Pu

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 3

7, 5

1-74

, 91,

102

2,

16-

18, 3

7, 5

1-74

, 91

16-1

8, 3

7, 9

1, 4

55

94

241 Pu

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 3

7, 5

1-61

, 91,

102

, 251

2,

16-

18, 3

7, 5

1-61

, 91

16-1

8, 3

7, 9

1, 4

55

94

242 Pu

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 3

7, 5

1-70

, 91,

102

, 251

2,

16-

18, 3

7, 5

1-70

, 91

16-1

8, 3

7, 9

1, 4

55

94

243 Pu

45

1, 4

52

1, 2

, 4, 1

6-18

, 37,

91,

102

, 251

-253

2,

16-

18, 3

7, 9

1 16

-18,

37,

91

94

244 Pu

45

1, 4

52, 4

58

1, 2

, 4, 1

6-20

, 37,

51-

55, 9

1, 1

02, 2

51-2

53

2, 1

6-20

, 37,

51-

55, 9

1 16

-20,

37,

91

94

246 Pu

45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51,

52,

91,

102

2,

16-

18, 5

1, 5

2, 9

1 16

-18,

91

95

241 A

m

451,

452

, 455

, 45

6, 4

58

1, 2

, 4, 1

6-18

, 51-

60, 9

1, 1

02

2, 1

6-18

, 51-

60, 9

1 16

-18,

91,

455

95

242 A

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

21, 5

1-75

, 91,

102

2,

16-

21, 5

1-75

, 91

16-2

1, 9

1

62

Page 63: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

95

242m

Am

45

1, 4

52, 4

55,

456,

458

1,

2, 4

, 16-

18, 5

1-75

, 91,

102

2,

16-

18, 5

1-75

, 91

16-1

8, 9

1, 4

55

95

243 A

m

451,

452

, 455

, 45

6, 4

58

1, 2

, 4, 1

6-18

, 51-

60, 9

1, 1

02

2, 1

6-18

, 51-

60, 9

1 16

-18,

91,

455

95

244 A

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

18, 3

7, 5

1-75

, 91,

102

2,

16-

18, 3

7, 5

1-75

, 91

16-1

8, 3

7, 9

1

95

244m

Am

45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51-

75, 9

1, 1

02

2, 1

6-18

, 37,

51-

75, 9

1 16

-18,

37,

91

96

240 C

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

18, 5

1, 9

1, 1

02

2, 1

6-18

, 51,

91

16-1

8, 9

1

96

241 C

m

451,

452

, 458

1,

2, 4

, 16-

20, 5

1-54

, 91,

102

, 251

-253

2,

16-

20, 5

1-54

, 91

16-2

0, 9

1

96

242 C

m

451,

452

, 455

, 45

6, 4

58

1, 2

, 4, 1

6-18

, 51-

53, 9

1, 1

02, 2

51

2, 1

6-18

, 51-

53, 9

1 16

-18,

91,

455

96

243 C

m

451,

452

, 455

, 45

6, 4

58

1, 2

, 4, 1

6-18

, 37,

51-

62, 9

1, 1

02, 2

51

2, 1

6-18

, 37,

51-

62, 9

1 16

-18,

37,

91,

455

96

244 C

m

451,

452

, 455

, 45

6, 4

58

1, 2

, 4, 1

6-20

, 51-

53, 9

1, 1

02

2, 1

6-20

, 51-

53, 9

1 16

-20,

91,

455

96

245 C

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

18, 5

1-67

, 91,

102

2,

16-

18, 5

1-67

, 91

16-1

8, 9

1, 4

55

96

246 C

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

21, 5

1-70

, 91,

102

2,

16-

21, 5

1-70

, 91

16-2

1, 9

1, 4

55

96

247 C

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

18, 3

7, 5

1-65

, 91,

102

, 251

2,

16-

18, 3

7, 5

1-65

, 91

16-1

8, 3

7, 9

1

96

248 C

m

451,

452

, 455

, 45

6, 4

58

1, 2

, 4, 1

6-18

, 37,

51-

58, 9

1, 1

02, 2

51

2, 1

6-18

, 37,

51-

58, 9

1 16

-18,

37,

91,

455

96

249 C

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

18, 5

1-69

, 91,

102

2,

16-

18, 5

1-69

, 91

16-1

8, 9

1

96

250 C

m

451,

452

, 455

, 45

6 1,

2, 4

, 16-

18, 5

1, 5

2, 9

1, 1

02

2, 1

6-18

, 51,

52,

91

16-1

8, 9

1

97

247 B

k 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

71, 9

1, 1

02

2, 1

6-18

, 51-

71, 9

1 16

-18,

91

97

249 B

k 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51-

68, 9

1, 1

02

2, 1

6-18

, 37,

51-

68, 9

1 16

-18,

37,

91

97

250 B

k 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51-

68, 9

1, 1

02, 2

51

2, 1

6-18

, 37,

51-

68, 9

1 16

-18,

37,

91

98

249 C

f 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

78, 9

1, 1

02

2, 1

6-18

, 51-

78, 9

1 16

-18,

91,

455

98

250 C

f 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 51-

79, 9

1, 1

02

2, 1

6-18

, 51-

79, 9

1 16

-18,

91

98

251 C

f 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

91,

102

, 251

-253

2,

16-

18, 3

7, 9

1 16

-18,

37,

91,

455

63

Page 64: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 3

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

avai

labl

e re

acti

ons

(MT

s) in

file

s M

F=3

to M

F=6

(co

nt.)

.

Z

Sym

-A

MF

=1

MF

=3

MF

=4

MF

=5

MF

=6

98

252 C

f 45

1, 4

52

1, 2

, 4, 1

6-18

, 37,

91,

102

, 251

-253

2,

16-

18, 3

7, 9

1 16

-18,

37,

91

98

254 C

f 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51,

91,

102

, 251

2,

16-

18, 3

7, 5

1, 9

1 16

-18,

37,

91

99

253 E

s 45

1 1,

2, 1

02, 2

51-2

53

99

254 E

s 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51,

91,

102

2,

16-

18, 3

7, 5

1, 9

1 16

-18,

37,

91,

455

99

255 E

s 45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51-

53, 9

1, 1

02

2, 1

6-18

, 37,

51-

53, 9

1 16

-18,

37,

91

100

255 Fm

45

1, 4

52, 4

55,

456

1, 2

, 4, 1

6-18

, 37,

51,

91,

102

2,

16-

18, 3

7, 5

1, 9

1 16

-18,

37,

91

64

Page 65: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 4

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. L

ist

of a

vaila

ble

reac

tion

s (M

Ts)

in p

hoto

n pr

oduc

tion

file

s M

F=1

2 to

MF

=15.

Z

Sym

-A

MF

=12

MF

=13

MF

=14

MF

=15

1 1 H

10

2

102

1 2 H

10

2

102

3 6 L

i 57

, 102

57, 1

02

3 7 L

i 51

, 102

51, 1

02

4 9 B

e 10

2

102

5 10

B

102,

801

4,

103

4,

102

, 103

, 801

5 11

B

102

4 4,

102

6 na

t C

51, 1

02

51

, 102

7 14

N

102

4, 2

8, 3

2, 1

03-1

05, 1

07

4, 2

8, 3

2, 1

02-1

05, 1

07

102

7 15

N

4,

16,

22,

28,

103

-105

, 107

4,

16,

22,

28,

103

-105

, 107

4,

16,

22,

28,

103

-105

, 107

8 16

O

102

4, 1

6, 2

2, 1

03-1

05, 1

07

4, 1

6, 2

2, 1

02-1

05, 1

07

9 19

F 51

-71,

102

51-7

1, 1

02

102

11

23N

a 51

-61,

102

3

3, 5

1-61

, 102

3,

102

12

24M

g 16

, 22,

28,

51-

61, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

61, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

12

25M

g 16

, 22,

28,

51-

67, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

67, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

12

26M

g 16

, 22,

28,

51-

63, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

63, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

13

27A

l 10

2

102

102

14

28Si

51

-67,

102

, 601

-613

, 801

-815

51-6

7, 1

02, 6

01-6

13, 8

01-8

15

14

29Si

51

-69,

102

, 103

, 107

3

3, 5

1-69

, 102

, 103

, 107

3,

102

, 103

, 107

14

30Si

51

-64,

102

, 107

3

3, 5

1-64

, 102

, 107

3,

102

, 107

15

31P

102,

103

, 107

3,

4

3, 4

, 102

, 103

, 107

3,

102

, 103

, 107

16

32S

16, 2

2, 2

8, 5

1-56

, 91,

102

, 103

, 107

16, 2

2, 2

8, 5

1-56

, 91,

102

, 103

, 107

16

, 22,

28,

91,

102

, 103

, 107

16

33S

16, 2

2, 2

8, 5

1-57

, 91,

102

, 103

, 107

16, 2

2, 2

8, 5

1-57

, 91,

102

, 103

, 107

16

, 22,

28,

91,

102

, 103

, 107

16

34S

16, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

16, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

16

, 22,

28,

91,

102

, 103

, 107

16

36S

16, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

16, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

16

, 22,

28,

91,

102

, 103

, 107

17

35C

l 10

2

102

102

17

37C

l 10

2

102

102

19

39K

16

, 22,

28,

51-

54, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

54, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

65

Page 66: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 4

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. L

ist

of a

vaila

ble

reac

tion

s (M

Ts)

in p

hoto

n pr

oduc

tion

file

s M

F=1

2 to

MF

=15

(con

t.).

Z

Sym

-A

MF

=12

MF

=13

MF

=14

MF

=15

19

40K

16

, 22,

28,

51-

55, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

55, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

19

41K

16

, 22,

28,

51,

52,

91,

102

, 103

, 107

16, 2

2, 2

8, 5

1, 5

2, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

23

nat V

10

2 3

3, 1

02

3, 1

02

24

50C

r 51

-56,

102

51-5

6, 1

02

102

24

52C

r 51

-60,

102

51-6

0, 1

02

102

24

53C

r 51

-63,

102

51-6

3, 1

02

102

24

54C

r 51

-54,

102

51-5

4, 1

02

102

25

55M

n 4,

16,

22,

28,

102

, 103

, 107

4, 1

6, 2

2, 2

8, 1

02, 1

03, 1

07

4, 1

6, 2

2, 2

8, 1

02, 1

03, 1

07

26

56Fe

51

-82,

102

, 601

-613

, 801

-810

51-8

2, 1

02, 6

01-6

13, 8

01-8

10

102

27

59C

o 10

2 3

3, 1

02

3, 1

02

28

58N

i 51

-58,

102

51-5

8, 1

02

102

28

59N

i 3,

102

3, 1

02

3, 1

02

28

60N

i 51

-61,

102

51-6

1, 1

02

102

28

61N

i 51

-58,

102

51-5

8, 1

02

102

28

62N

i 51

-54,

102

51-5

4, 1

02

102

28

64N

i 51

, 52,

102

51, 5

2, 1

02

102

29

63C

u 51

-72,

102

51-7

2, 1

02

102

29

65C

u 51

-63,

102

51-6

3, 1

02

102

31

nat G

a 10

2 3

3, 1

02

3, 1

02

39

89Y

10

2 3

3, 1

02

3, 1

02

40

90Z

r 16

, 22,

28,

51-

57, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

57, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

40

91Z

r 16

, 22,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

16

, 22,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

16, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

40

92Z

r 16

, 17,

22,

28,

51-

67, 9

1, 1

02, 1

03, 1

07

16

, 17,

22,

28,

51-

67, 9

1, 1

02, 1

03, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

40

94Z

r 16

, 17,

22,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

16

, 17,

22,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

40

96Z

r 16

, 17,

22,

28,

51-

57, 9

1, 1

02, 1

03, 1

07

16

, 17,

22,

28,

51-

57, 9

1, 1

02, 1

03, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02, 1

03, 1

07

41

93N

b 10

2 3

3, 1

02

3, 1

02

42

100 M

o 10

2 3

3, 1

02

3, 1

02

42

92M

o 10

2 3

3, 1

02

3, 1

02

42

94M

o 10

2 3

3, 1

02

3, 1

02

66

Page 67: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 4

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. L

ist

of a

vaila

ble

reac

tion

s (M

Ts)

in p

hoto

n pr

oduc

tion

file

s M

F=1

2 to

MF

=15

(con

t.).

Z

Sym

-A

MF

=12

MF

=13

MF

=14

MF

=15

42

95M

o 51

-54,

601

, 801

-805

51-5

4, 6

01, 8

01-8

05

42

96M

o 10

2 3

3, 1

02

3, 1

02

42

97M

o 10

2 3

3, 1

02

3, 1

02

42

98M

o 10

2 3

3, 1

02

3, 1

02

63

151 E

u 51

-59,

102

3

3, 5

1-59

, 102

3,

102

67

165 H

o 10

2 4,

16,

17,

37

4, 1

6, 1

7, 3

7, 1

02

4, 1

6, 1

7, 3

7, 1

02

68

162 E

r 16

, 17,

51-

67, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

67, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

68

164 E

r 16

, 17,

51-

66, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

66, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

68

166 E

r 16

, 17,

22,

28,

51-

74, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

74, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

68

167 E

r 16

, 17,

22,

28,

51-

73, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

73, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

68

168 E

r 16

, 17,

22,

28,

51-

79, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

79, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

68

170 E

r 16

, 17,

22,

28,

51-

64, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

64, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

72

174 H

f 16

, 17,

51-

68, 9

1, 1

02

16

, 17,

51-

68, 9

1, 1

02

16, 1

7, 9

1, 1

02

72

176 H

f 16

, 17,

51-

73, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

73, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

72

177 H

f 16

, 17,

51-

66, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

66, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

72

178 H

f 16

, 17,

51-

71, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

71, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

72

179 H

f 16

, 17,

51-

62, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

62, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

72

180 H

f 16

, 17,

51-

61, 9

1, 1

02, 1

03, 1

07

16

, 17,

51-

61, 9

1, 1

02, 1

03, 1

07

16, 1

7, 9

1, 1

02, 1

03, 1

07

73

181 T

a 16

, 17,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

16

, 17,

28,

51-

64, 9

1, 1

02, 1

03, 1

07

16, 1

7, 2

8, 9

1, 1

02, 1

03, 1

07

74

182 W

22

, 51-

70, 1

02, 1

03, 1

07

3 3,

22,

51-

70, 1

02, 1

03, 1

07

3, 2

2, 1

02, 1

03, 1

07

74

183 W

22

, 51-

60, 1

02, 1

03, 1

07

3 3,

22,

51-

60, 1

02, 1

03, 1

07

3, 2

2, 1

02, 1

03, 1

07

74

184 W

51

-60,

102

, 107

3

3, 5

1-60

, 102

, 107

3,

102

, 107

74

186 W

22

, 51-

62, 1

02, 1

07

3 3,

22,

51-

62, 1

02, 1

07

3, 2

2, 1

02, 1

07

76

nat O

s 51

-67,

91,

102

51-6

7, 9

1, 1

02

91, 1

02

77

191 Ir

51

, 52,

54,

91,

102

, 103

, 107

51, 5

2, 5

4, 9

1, 1

02, 1

03, 1

07

91, 1

02, 1

03, 1

07

77

193 Ir

51

, 53,

54,

91,

102

, 103

, 107

51, 5

3, 5

4, 9

1, 1

02, 1

03, 1

07

91, 1

02, 1

03, 1

07

78

nat Pt

10

2 3

3, 1

02

3, 1

02

79

197 A

u 10

2 4,

16,

17,

37

4, 1

6, 1

7, 3

7, 1

02

4, 1

6, 1

7, 3

7, 1

02

80

196 H

g 16

, 17,

22,

28,

51-

70, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

70, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

67

Page 68: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 4

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. L

ist

of a

vaila

ble

reac

tion

s (M

Ts)

in p

hoto

n pr

oduc

tion

file

s M

F=1

2 to

MF

=15

(con

t.).

Z

Sym

-A

MF

=12

MF

=13

MF

=14

MF

=15

80

198 H

g 16

, 17,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

80

199 H

g 16

, 17,

22,

28,

51-

56, 5

8-63

, 91,

102

-104

, 107

16, 1

7, 2

2, 2

8, 5

1-56

, 58-

63, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

80

200 H

g 16

, 17,

22,

28,

51-

84, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

84, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

80

201 H

g 16

, 17,

22,

28,

51-

63, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

63, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

80

202 H

g 16

, 17,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

69, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

80

204 H

g 16

, 17,

22,

28,

51-

68, 9

1, 1

02-1

04, 1

07

16

, 17,

22,

28,

51-

68, 9

1, 1

02-1

04, 1

07

16, 1

7, 2

2, 2

8, 9

1, 1

02-1

04, 1

07

90

232 T

h 18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

92

233 U

4,

18,

102

3

3, 4

, 18,

102

3,

4, 1

8, 1

02

92

235 U

4,

18,

102

3

3, 4

, 18,

102

3,

18,

102

92

236 U

18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

92

237 U

18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

92

238 U

18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

94

240 Pu

4,

18,

102

3

3, 4

, 18,

102

3,

18,

102

94

242 Pu

16

, 17,

51-

70, 9

1, 1

02

16

, 17,

51-

70, 9

1, 1

02

16, 1

7, 9

1, 1

02

94

243 Pu

18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

96

242 C

m

18, 1

02

3 3,

18,

102

3,

18,

102

96

243 C

m

18, 1

02

3 3,

18,

102

3,

18,

102

96

244 C

m

18, 1

02

3 3,

18,

102

3,

18,

102

96

246 C

m

18, 1

02

3 3,

18,

102

3,

18,

102

96

247 C

m

18, 1

02

3 3,

18,

102

3,

18,

102

96

248 C

m

18, 1

02

3 3,

18,

102

3,

18,

102

98

251 C

f 18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

98

252 C

f 18

, 102

3

3, 1

8, 1

02

3, 1

8, 1

02

68

Page 69: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 5

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

cova

rian

ce d

ata

(MF

=33

to M

F=3

6).

Z

Sym

-A

MF

=31

MF

=32

MF

=33

MF

=34

MF

=35

MF

=36

MF

=40

1 3 H

1,

2, 1

6, 1

7

4 9 B

e

1,

2, 1

02-1

05, 1

07, 8

75-8

90

6 na

t C

1-5,

28,

51-

62, 9

1, 1

02-1

04, 1

07

9 19

F

1-

4, 1

6, 2

2, 2

8, 5

1, 5

2, 1

02-1

05, 1

07

14

28Si

1-

4, 1

6, 2

2, 2

8, 5

1-67

, 91,

102

-107

, 111

, 600

-613

, 649

, 800

-815

, 849

, 851

, 852

22

46T

i

1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 854

22

47T

i

1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 852

, 854

22

48T

i

1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 851

, 852

22

49T

i

1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 111

, 852

, 854

22

50T

i

1-

4, 1

6, 2

2, 2

8, 5

1-70

, 91,

102

-107

, 854

23

nat V

1,

16,

103

, 107

24

50C

r

1-

4, 1

6, 2

2, 2

8, 5

1-56

, 91,

102

-104

, 107

24

52C

r

1-

4, 1

6, 2

2, 2

8, 5

1-60

, 91,

102

-107

, 851

, 852

2

24

53C

r

1-

4, 1

6, 2

2, 2

8, 5

1-63

, 91,

102

, 103

, 107

24

54C

r

1-

4, 1

6, 5

1-54

, 91,

102

, 103

, 107

25

55M

n

151

1, 2

, 4, 1

6, 2

2, 2

8, 5

1-66

, 91,

102

-107

26

54Fe

1-

4, 1

6, 2

2, 2

8, 5

1-57

, 91,

102

-104

, 107

26

56Fe

1-

4, 1

6, 2

2, 2

8, 5

1-82

, 91,

102

-107

, 600

-613

, 649

, 800

-810

, 849

, 851

-853

2

26

57Fe

1-

4, 1

6, 2

2, 2

8, 5

1-55

, 91,

102

, 103

, 107

26

58Fe

1-

4, 1

6, 2

2, 2

8, 5

1, 5

2, 9

1, 1

02, 1

03, 1

07

27

59C

o

1,

16,

103

, 107

28

58N

i

1-

4, 1

6, 2

2, 2

8, 5

1-58

, 91,

102

-107

, 112

, 854

2

28

60N

i

1-

4, 1

6, 2

2, 2

8, 5

1-61

, 91,

102

-107

, 851

-853

2

28

61N

i

1-

4, 1

6, 2

8, 5

1-58

, 91,

102

, 103

, 107

, 111

28

62N

i

1-

4, 1

6, 2

2, 2

8, 5

1-54

, 91,

102

-104

, 107

28

64N

i

1-

4, 1

6, 2

2, 2

8, 5

1, 5

2, 9

1, 1

02-1

04, 1

07

29

63C

u

1-

4, 1

6, 2

2, 2

8, 5

1-72

, 91,

102

-104

, 106

, 107

29

65C

u

1-

4, 1

6, 2

2, 2

8, 5

1-63

, 91,

102

-107

39

89Y

1,

2, 4

, 16,

91,

102

, 103

, 107

40

90Z

r

4,

16,

102

69

Page 70: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 5

. Con

tent

s of

the

JE

FF

-3.1

gen

eral

-pur

pose

neu

tron

dat

a lib

rary

. Lis

t of

cova

rian

ce d

ata

(MF

=33

to M

F=3

6) (c

ont.)

.

Z

Sym

-A

MF

=31

MF

=32

MF

=33

MF

=34

MF

=35

MF

=36

MF

=40

41

93N

b

1,

2, 4

, 16,

17,

102

4

75

185 R

e

10

2

75

187 R

e

10

2

79

197 A

u

1

92

233 U

45

2, 4

55, 4

56

151

1, 2

, 4, 1

6-18

, 102

2

18

92

235 U

45

2, 4

56

95

241 A

m

102

70

Page 71: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

1 1 H

N

o

1 2 H

N

o

1 3 H

N

o

2 3 H

e N

o

2 4 H

e N

o

3 6 L

i N

o

3 7L

i N

o

4 9 B

e N

o

5 10

B

No

5 11

B

No

6 na

t C

No

7 14

N

No

7 15

N

No

8 16

O

No

8 17

O

No

9 19

F N

o

11

22N

a Y

es

ML

Bre

it-W

igne

r 1.

50E

+04

Yes

1.

00E

+05

1.45

E+0

2

11

23N

a Y

es

ML

Bre

it-W

igne

r 3.

50E

+05

No

2.

85E

+03

2.99

E+0

5 5.

38E

+05

12

24M

g Y

es

ML

Bre

it-W

igne

r 5.

20E

+05

No

6.

59E

+05

1.04

E+0

6 1.

08E

+06

12

25M

g Y

es

ML

Bre

it-W

igne

r 2.

20E

+05

No

7.

33E

+04

12

26M

g Y

es

ML

Bre

it-W

igne

r 4.

50E

+05

No

13

27A

l Y

es

Rei

ch-M

oore

8.

45E

+05

No

3.

48E

+04

8.63

E+0

4 1.

43E

+05

14

28Si

Y

es

Rei

ch-M

oore

1.

75E

+06

No

5.

57E

+04

1.82

E+0

5 3.

01E

+05

14

29Si

Y

es

ML

Bre

it-W

igne

r 2.

00E

+05

No

14

30Si

Y

es

ML

Bre

it-W

igne

r 5.

00E

+05

No

1.

83E

+05

15

31P

Yes

M

L B

reit

-Wig

ner

5.44

E+0

5 N

o

2.68

E+0

4 8.

40E

+04

9.27

E+0

4

16

32S

Yes

M

L B

reit

-Wig

ner

1.57

E+0

6 N

o

1.03

E+0

5 1.

45E

+05

1.60

E+0

5

16

33S

Yes

M

L B

reit

-Wig

ner

2.60

E+0

5 N

o

1.35

E+0

4 2.

39E

+04

5.20

E+0

4

16

34S

Yes

M

L B

reit

-Wig

ner

4.80

E+0

5 N

o

3.01

E+0

5 3.

57E

+05

4.71

E+0

5

16

36S

No

17

35C

l N

o

17

37C

l N

o

71

Page 72: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

18

36A

r Y

es

ML

Bre

it-W

igne

r 4.

65E

+04

Yes

1.

20E

+06

2.00

E+0

4

18

38A

r Y

es

ML

Bre

it-W

igne

r 3.

00E

+05

Yes

1.

20E

+06

1.35

E+0

5

18

40A

r Y

es

Rei

ch-M

oore

1.

50E

+06

No

7.

65E

+04

1.72

E+0

5 2.

20E

+05

19

39K

Y

es

ML

Bre

it-W

igne

r 2.

00E

+05

No

9.

37E

+03

2.55

E+0

4 4.

27E

+04

19

40K

N

o

19

41K

Y

es

ML

Bre

it-W

igne

r 1.

25E

+05

No

2.

03E

+03

5.51

E+0

3 1.

67E

+04

20

40C

a Y

es

ML

Bre

it-W

igne

r 5.

00E

+05

No

2.

04E

+04

4.21

E+0

4 8.

89E

+04

20

42C

a Y

es

ML

Bre

it-W

igne

r 3.

00E

+05

No

9.

35E

+03

2.27

E+0

4 2.

63E

+04

20

43C

a Y

es

ML

Bre

it-W

igne

r 4.

00E

+04

No

3.

33E

+03

4.32

E+0

3 5.

19E

+03

20

44C

a Y

es

ML

Bre

it-W

igne

r 5.

00E

+05

No

1.

51E

+04

2.31

E+0

4 2.

72E

+04

20

46C

a N

o

20

48C

a Y

es

ML

Bre

it-W

igne

r 5.

00E

+05

No

1.

61E

+05

21

45Sc

Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

3.

30E

+03

4.33

E+0

3 6.

69E

+03

22

46T

i N

o

22

47T

i N

o

22

48T

i N

o

22

49T

i N

o

22

50T

i N

o

23

nat V

Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

1.

67E

+02

1.42

E+0

3 6.

20E

+03

23

nat V

Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

4.

15E

+03

6.80

E+0

3 1.

16E

+04

24

50C

r Y

es

Rei

ch-M

oore

7.

92E

+05

No

5.

50E

+03

2.84

E+0

4 3.

73E

+04

24

52C

r Y

es

Rei

ch-M

oore

1.

20E

+06

No

3.

17E

+04

5.03

E+0

4 9.

67E

+04

24

53C

r Y

es

Rei

ch-M

oore

2.

00E

+05

No

4.

21E

+03

5.67

E+0

3 6.

75E

+03

24

54C

r Y

es

Rei

ch-M

oore

9.

00E

+05

No

2.

26E

+04

1.19

E+0

5 1.

31E

+05

25

55M

n Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

3.

37E

+02

1.10

E+0

3 1.

66E

+03

26

54Fe

Y

es

Rei

ch-M

oore

7.

00E

+05

No

7.

79E

+03

5.29

E+0

4 7.

19E

+04

26

56Fe

Y

es

Rei

ch-M

oore

8.

50E

+05

No

2.

78E

+04

7.40

E+0

4 8.

36E

+04

26

57Fe

Y

es

Rei

ch-M

oore

2.

00E

+05

No

3.

95E

+03

6.26

E+0

3 2.

90E

+04

26

58Fe

Y

es

Rei

ch-M

oore

3.

50E

+05

Yes

3.

00E

+06

1.04

E+0

4 3.

77E

+04

4.38

E+0

4

27

58C

o Y

es

ML

Bre

it-W

igne

r 5.

96E

+02

No

9.

00E

+00

27

58mC

o Y

es

ML

Bre

it-W

igne

r 5.

00E

+02

No

1.

09E

+00

27

59C

o Y

es

Rei

ch-M

oore

1.

00E

+05

No

1.

32E

+02

4.32

E+0

3 5.

02E

+03

72

Page 73: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

28

58N

i Y

es

Rei

ch-M

oore

8.

12E

+05

No

1.

53E

+04

3.61

E+0

4 6.

33E

+04

28

59N

i Y

es

ML

Bre

it-W

igne

r 1.

00E

+04

No

2.

03E

+02

4.21

E+0

3 6.

28E

+03

28

60N

i Y

es

Rei

ch-M

oore

4.

50E

+05

No

1.

25E

+04

2.87

E+0

4 4.

31E

+04

28

61N

i Y

es

Rei

ch-M

oore

7.

00E

+04

No

7.

15E

+03

7.55

E+0

3 8.

75E

+03

28

62N

i Y

es

Rei

ch-M

oore

6.

00E

+05

No

4.

54E

+03

4.29

E+0

4 9.

47E

+04

28

64N

i Y

es

Rei

ch-M

oore

6.

00E

+05

No

1.

43E

+04

3.38

E+0

4 1.

29E

+05

29

63C

u Y

es

Rei

ch-M

oore

9.

95E

+04

No

5.

79E

+02

6.50

E+0

2 8.

07E

+02

29

65C

u Y

es

Rei

ch-M

oore

9.

95E

+04

No

2.

30E

+02

1.36

E+0

3 2.

53E

+03

30

nat Z

n Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

2.

82E

+02

2.63

E+0

3 4.

17E

+03

30

nat Z

n Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

3.

24E

+02

4.05

E+0

3 1.

04E

+04

30

nat Z

n Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

2.

23E

+02

4.48

E+0

2 5.

88E

+02

30

nat Z

n Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

5.

14E

+02

5.04

E+0

3 1.

34E

+04

30

nat Z

n Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

1.

80E

+04

2.30

E+0

4 3.

19E

+04

31

nat G

a Y

es

ML

Bre

it-W

igne

r 5.

90E

+03

No

1.

11E

+02

3.34

E+0

2 4.

73E

+02

31

nat G

a Y

es

ML

Bre

it-W

igne

r 5.

60E

+03

No

9.

57E

+01

2.87

E+0

2 3.

76E

+02

32

70G

e Y

es

ML

Bre

it-W

igne

r 1.

50E

+04

No

1.

12E

+03

1.47

E+0

3 1.

94E

+03

32

72G

e Y

es

ML

Bre

it-W

igne

r 4.

00E

+04

No

2.

61E

+03

2.74

E+0

3 3.

65E

+03

32

73G

e Y

es

ML

Bre

it-W

igne

r 8.

53E

+03

No

1.

02E

+02

2.04

E+0

2 2.

25E

+02

32

74G

e Y

es

ML

Bre

it-W

igne

r 6.

20E

+04

No

2.

85E

+03

3.04

E+0

3 4.

99E

+03

32

76G

e Y

es

ML

Bre

it-W

igne

r 5.

00E

+04

No

5.

50E

+02

4.76

E+0

3 1.

39E

+04

33

75A

s Y

es

ML

Bre

it-W

igne

r 2.

41E

+03

No

4.

70E

+01

9.24

E+0

1 2.

53E

+02

34

74Se

Y

es

ML

Bre

it-W

igne

r 2.

40E

+03

No

2.

71E

+01

2.72

E+0

2 1.

03E

+03

34

76Se

Y

es

ML

Bre

it-W

igne

r 7.

49E

+03

No

3.

77E

+02

8.62

E+0

2 2.

12E

+03

34

77Se

Y

es

ML

Bre

it-W

igne

r 2.

72E

+03

No

1.

12E

+02

2.12

E+0

2 2.

91E

+02

34

78Se

Y

es

ML

Bre

it-W

igne

r 1.

21E

+04

No

3.

83E

+02

3.23

E+0

3 6.

17E

+03

34

79Se

N

o

Y

es

1.00

E+0

5

34

80Se

Y

es

ML

Bre

it-W

igne

r 6.

71E

+03

No

1.

97E

+03

4.27

E+0

3 4.

72E

+03

34

82Se

Y

es

ML

Bre

it-W

igne

r 3.

11E

+04

No

6.

58E

+03

1.38

E+0

4 2.

27E

+04

35

79B

r Y

es

ML

Bre

it-W

igne

r 4.

12E

+02

No

3.

58E

+01

5.38

E+0

1 1.

58E

+02

35

81B

r Y

es

ML

Bre

it-W

igne

r 3.

63E

+03

No

1.

01E

+02

1.36

E+0

2 2.

05E

+02

36

78K

r Y

es

ML

Bre

it-W

igne

r 8.

65E

+02

No

1.

08E

+02

4.51

E+0

2 6.

40E

+02

36

80K

r Y

es

ML

Bre

it-W

igne

r 1.

00E

+03

No

8.

92E

+01

1.06

E+0

2 6.

40E

+02

73

Page 74: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

36

82K

r Y

es

ML

Bre

it-W

igne

r 1.

00E

+02

No

3.

98E

+01

36

83K

r Y

es

ML

Bre

it-W

igne

r 5.

21E

+02

No

2.

79E

+01

2.33

E+0

2

36

84K

r Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

No

5.

19E

+02

5.80

E+0

2 1.

63E

+03

36

85K

r N

o

36

86K

r Y

es

ML

Bre

it-W

igne

r 1.

30E

+04

No

2.

73E

+03

37

85R

b Y

es

ML

Bre

it-W

igne

r 9.

23E

+03

No

4.

74E

+02

5.26

E+0

2 6.

55E

+02

37

86R

b N

o

37

87R

b Y

es

ML

Bre

it-W

igne

r 1.

59E

+04

No

3.

78E

+02

3.84

E+0

3 5.

12E

+03

38

84Sr

Y

es

ML

Bre

it-W

igne

r 3.

50E

+03

No

3.

65E

+02

5.17

E+0

2 6.

35E

+02

38

86Sr

Y

es

ML

Bre

it-W

igne

r 1.

99E

+04

No

5.

88E

+02

3.25

E+0

3 1.

02E

+04

38

87Sr

Y

es

ML

Bre

it-W

igne

r 2.

89E

+03

No

3.

54E

+00

6.48

E+0

2 6.

76E

+02

38

88Sr

Y

es

ML

Bre

it-W

igne

r 1.

66E

+05

No

1.

39E

+04

9.25

E+0

4 1.

06E

+05

38

89Sr

N

o

38

90Sr

N

o

39

89Y

Y

es

SL

Bre

it-W

igne

r 1.

50E

+05

No

2.

60E

+03

7.49

E+0

3 9.

73E

+03

39

90Y

N

o

39

91Y

N

o

40

90Z

r Y

es

ML

Bre

it-W

igne

r 1.

71E

+05

No

3.

86E

+03

1.34

E+0

4 1.

73E

+04

40

91Z

r Y

es

ML

Bre

it-W

igne

r 3.

02E

+04

Yes

1.

00E

+05

2.92

E+0

2 6.

81E

+02

1.53

E+0

3

40

92Z

r Y

es

ML

Bre

it-W

igne

r 7.

10E

+04

Yes

1.

00E

+05

2.69

E+0

3 4.

64E

+03

6.81

E+0

3

40

93Z

r Y

es

ML

Bre

it-W

igne

r 1.

17E

+02

Yes

5.

00E

+04

1.10

E+0

2

40

94Z

r Y

es

ML

Bre

it-W

igne

r 5.

35E

+04

Yes

1.

00E

+05

2.24

E+0

3 5.

76E

+03

7.07

E+0

3

40

95Z

r Y

es

ML

Bre

it-W

igne

r 3.

00E

+03

Yes

5.

00E

+04

1.72

E+0

2 4.

43E

+02

7.14

E+0

2

40

96Z

r Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

5.

44E

+03

1.54

E+0

4 2.

47E

+04

41

93N

b Y

es

SL

Bre

it-W

igne

r 7.

35E

+03

No

1.

06E

+02

1.19

E+0

2 1.

93E

+02

41

94N

b Y

es

ML

Bre

it-W

igne

r 2.

80E

+01

Yes

1.

00E

+05

1.16

E+0

1 2.

26E

+01

41

95N

b N

o

Y

es

1.00

E+0

5

42

100 M

o Y

es

ML

Bre

it-W

igne

r 2.

60E

+04

Yes

1.

00E

+05

3.64

E+0

2 1.

41E

+03

1.94

E+0

3

42

92M

o Y

es

ML

Bre

it-W

igne

r 5.

00E

+04

Yes

1.

00E

+05

3.47

E+0

2 3.

18E

+03

6.82

E+0

3

42

94M

o Y

es

ML

Bre

it-W

igne

r 2.

00E

+04

Yes

1.

00E

+05

1.54

E+0

3 3.

60E

+03

4.62

E+0

3

42

95M

o Y

es

ML

Bre

it-W

igne

r 2.

14E

+03

Yes

2.

06E

+05

4.49

E+0

1 1.

60E

+02

3.58

E+0

2

42

96M

o Y

es

ML

Bre

it-W

igne

r 1.

90E

+04

Yes

1.

00E

+05

1.31

E+0

2 2.

37E

+03

3.29

E+0

3

74

Page 75: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

42

97M

o Y

es

ML

Bre

it-W

igne

r 1.

80E

+03

Yes

1.

00E

+05

7.09

E+0

1 2.

28E

+02

2.68

E+0

2

42

98M

o Y

es

ML

Bre

it-W

igne

r 3.

20E

+04

Yes

1.

00E

+05

4.68

E+0

2 1.

53E

+03

2.55

E+0

3

42

99M

o N

o

Y

es

1.00

E+0

5

43

99T

c Y

es

Rei

ch-M

oore

6.

00E

+03

Yes

1.

00E

+05

5.58

E+0

0 2.

03E

+01

3.98

E+0

1

44

100 R

u Y

es

ML

Bre

it-W

igne

r 5.

02E

+02

No

2.

31E

+02

44

101 R

u Y

es

ML

Bre

it-W

igne

r 1.

04E

+03

Yes

2.

50E

+04

1.57

E+0

1 4.

23E

+01

5.21

E+0

1

44

102 R

u Y

es

SL

Bre

it-W

igne

r 1.

61E

+03

No

1.

30E

+03

44

103 R

u Y

es

ML

Bre

it-W

igne

r 4.

69E

+01

Yes

3.

00E

+03

3.10

E+0

0 9.

30E

+00

1.55

E+0

1

44

104 R

u Y

es

ML

Bre

it-W

igne

r 1.

51E

+03

No

2.

24E

+02

3.81

E+0

2 6.

27E

+02

44

105 R

u N

o

44

106 R

u N

o

44

96R

u N

o

44

98R

u N

o

44

99R

u Y

es

ML

Bre

it-W

igne

r 1.

01E

+03

No

1.

01E

+01

2.52

E+0

1 5.

71E

+01

45

103 R

h Y

es

ML

Bre

it-W

igne

r 4.

12E

+03

Yes

4.

01E

+04

1.26

E+0

0 4.

68E

+01

6.83

E+0

1

45

105 R

h N

o

46

102 Pd

Y

es

ML

Bre

it-W

igne

r 3.

97E

+02

No

1.

91E

+02

46

104 Pd

Y

es

ML

Bre

it-W

igne

r 3.

20E

+03

Yes

1.

00E

+05

1.83

E+0

2 2.

95E

+02

3.47

E+0

2

46

105 Pd

Y

es

ML

Bre

it-W

igne

r 2.

06E

+03

Yes

2.

00E

+04

1.18

E+0

1 1.

32E

+01

2.52

E+0

1

46

106 Pd

Y

es

ML

Bre

it-W

igne

r 3.

20E

+03

Yes

1.

00E

+05

2.82

E+0

2 4.

08E

+02

4.63

E+0

2

46

107 Pd

Y

es

ML

Bre

it-W

igne

r 6.

60E

+02

Yes

5.

00E

+04

3.92

E+0

0 5.

20E

+00

6.83

E+0

0

46

108 Pd

Y

es

ML

Bre

it-W

igne

r 3.

20E

+03

Yes

1.

00E

+05

3.32

E+0

1 9.

10E

+01

1.13

E+0

2

46

110 Pd

Y

es

ML

Bre

it-W

igne

r 2.

90E

+03

Yes

1.

00E

+05

2.63

E+0

2 8.

58E

+02

9.00

E+0

2

47

107 A

g Y

es

ML

Bre

it-W

igne

r 1.

06E

+03

No

1.

63E

+01

4.15

E+0

1 4.

48E

+01

47

109 A

g Y

es

ML

Bre

it-W

igne

r 9.

84E

+02

Yes

8.

00E

+04

5.19

E+0

0 3.

04E

+01

4.01

E+0

1

47

110m

Ag

Yes

M

L B

reit

-Wig

ner

1.25

E+0

2 Y

es

1.00

E+0

5 1.

15E

+01

1.95

E+0

1 2.

12E

+01

47

111 A

g N

o

48

106 C

d Y

es

ML

Bre

it-W

igne

r 6.

00E

+03

Yes

1.

00E

+05

2.32

E+0

2 4.

56E

+02

4.97

E+0

2

48

108 C

d Y

es

ML

Bre

it-W

igne

r 6.

10E

+03

Yes

1.

00E

+05

5.42

E+0

1 2.

34E

+02

3.12

E+0

2

48

110 C

d Y

es

ML

Bre

it-W

igne

r 7.

18E

+03

Yes

1.

00E

+05

8.95

E+0

1 2.

31E

+02

3.70

E+0

2

48

111 C

d Y

es

SL

Bre

it-W

igne

r 2.

40E

+03

No

2.

75E

+01

6.94

E+0

1 8.

61E

+01

48

112 C

d Y

es

ML

Bre

it-W

igne

r 7.

35E

+03

Yes

1.

00E

+05

6.68

E+0

1 2.

26E

+02

4.43

E+0

2

75

Page 76: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

48

113 C

d Y

es

SL

Bre

it-W

igne

r 2.

25E

+03

No

1.

78E

-01

1.84

E+0

1 6.

37E

+01

48

114 C

d Y

es

ML

Bre

it-W

igne

r 8.

00E

+03

Yes

1.

00E

+05

1.20

E+0

2 2.

27E

+02

3.92

E+0

2

48

115m

Cd

No

48

116 C

d Y

es

ML

Bre

it-W

igne

r 9.

00E

+03

Yes

1.

00E

+05

2.90

E+0

1 6.

76E

+02

8.89

E+0

2

49

113 In

Y

es

ML

Bre

it-W

igne

r 8.

30E

+02

Yes

1.

00E

+05

1.80

E+0

0 4.

70E

+00

1.46

E+0

1

49

115 In

Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

Yes

1.

00E

+05

1.46

E+0

0 3.

82E

+00

9.07

E+0

0

50

112 Sn

Y

es

ML

Bre

it-W

igne

r 1.

50E

+03

Yes

1.

00E

+05

6.47

E+0

1 9.

48E

+01

1.05

E+0

2

50

114 Sn

Y

es

ML

Bre

it-W

igne

r 2.

50E

+03

Yes

1.

00E

+05

2.78

E+0

2 6.

66E

+02

9.84

E+0

2

50

115 Sn

Y

es

ML

Bre

it-W

igne

r 9.

50E

+02

Yes

1.

00E

+05

2.93

E+0

2 4.

48E

+02

4.94

E+0

2

50

116 Sn

Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

Yes

1.

00E

+05

1.11

E+0

2 1.

34E

+03

1.56

E+0

3

50

117 Sn

Y

es

ML

Bre

it-W

igne

r 2.

35E

+03

Yes

1.

00E

+05

3.88

E+0

1 1.

20E

+02

1.24

E+0

2

50

118 Sn

Y

es

ML

Bre

it-W

igne

r 4.

80E

+03

Yes

1.

00E

+05

3.59

E+0

2 7.

71E

+02

1.58

E+0

3

50

119 Sn

Y

es

ML

Bre

it-W

igne

r 1.

30E

+03

Yes

1.

00E

+05

1.15

E+0

2 1.

41E

+02

2.23

E+0

2

50

120 Sn

Y

es

ML

Bre

it-W

igne

r 7.

00E

+04

Yes

1.

00E

+05

9.52

E+0

2 3.

12E

+03

4.36

E+0

3

50

122 Sn

Y

es

ML

Bre

it-W

igne

r 2.

90E

+04

Yes

1.

00E

+05

1.75

E+0

3 5.

40E

+03

6.82

E+0

3

50

123 Sn

N

o

50

124 Sn

Y

es

ML

Bre

it-W

igne

r 1.

07E

+04

Yes

1.

00E

+05

50

125 Sn

N

o

50

126 Sn

N

o

51

121 Sb

Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

Yes

1.

00E

+05

6.22

E+0

0 1.

54E

+01

2.96

E+0

1

51

123 Sb

Y

es

ML

Bre

it-W

igne

r 2.

50E

+03

Yes

1.

00E

+05

2.14

E+0

1 5.

05E

+01

7.67

E+0

1

51

124 Sb

N

o

51

125 Sb

N

o

51

126 Sb

N

o

52

120 T

e N

o

52

122 T

e Y

es

ML

Bre

it-W

igne

r 3.

79E

+03

No

7.

28E

+01

2.31

E+0

2 3.

33E

+02

52

123 T

e Y

es

ML

Bre

it-W

igne

r 6.

33E

+02

No

2.

33E

+00

2.41

E+0

1 3.

59E

+01

52

124 T

e Y

es

ML

Bre

it-W

igne

r 5.

70E

+03

No

3.

52E

+02

5.41

E+0

2 6.

79E

+02

52

125 T

e Y

es

ML

Bre

it-W

igne

r 1.

34E

+03

No

2.

63E

+01

1.06

E+0

2 1.

35E

+02

52

126 T

e Y

es

ML

Bre

it-W

igne

r 6.

35E

+03

No

2.

01E

+02

1.75

E+0

3 2.

15E

+03

52

127m

Te

No

52

128 T

e Y

es

ML

Bre

it-W

igne

r 1.

29E

+04

No

3.

48E

+02

4.24

E+0

2 1.

32E

+03

76

Page 77: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

52

129m

Te

No

52

130 T

e Y

es

ML

Bre

it-W

igne

r 3.

43E

+04

No

7.

02E

+03

1.00

E+0

4 2.

42E

+04

52

132 T

e N

o

53

127 I

Yes

R

eich

-Moo

re

5.20

E+0

3 Y

es

5.76

E+0

4 2.

04E

+01

3.12

E+0

1 3.

77E

+01

53

129 I

Yes

R

eich

-Moo

re

5.10

E+0

3 Y

es

2.78

E+0

4 4.

14E

+01

7.21

E+0

1 7.

61E

+01

53

130 I

No

53

131 I

No

53

135 I

No

54

124 X

e Y

es

ML

Bre

it-W

igne

r 3.

75E

+02

No

5.

16E

+00

9.88

E+0

0 2.

52E

+02

54

126 X

e Y

es

ML

Bre

it-W

igne

r 6.

50E

+02

No

8.

66E

+01

1.00

E+0

2 4.

60E

+02

54

128 X

e Y

es

ML

Bre

it-W

igne

r 4.

00E

+03

No

2.

38E

+02

3.71

E+0

2 5.

55E

+02

54

129 X

e Y

es

ML

Bre

it-W

igne

r 4.

20E

+03

No

9.

44E

+00

9.05

E+0

1 9.

23E

+01

54

130 X

e Y

es

ML

Bre

it-W

igne

r 4.

00E

+03

No

4.

30E

+02

9.41

E+0

2 1.

48E

+03

54

131 X

e Y

es

ML

Bre

it-W

igne

r 2.

19E

+03

No

1.

44E

+01

4.60

E+0

1 7.

56E

+01

54

132 X

e Y

es

ML

Bre

it-W

igne

r 4.

26E

+03

No

6.

43E

+02

2.13

E+0

3 2.

85E

+03

54

133 X

e N

o

54

134 X

e Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

No

1.

00E

+03

54

135 X

e N

o

54

136 X

e N

o

55

133 C

s Y

es

ML

Bre

it-W

igne

r 3.

99E

+03

Yes

8.

16E

+04

5.86

E+0

0 2.

25E

+01

4.76

E+0

1

55

134 C

s Y

es

ML

Bre

it-W

igne

r 1.

87E

+02

No

1.

23E

+01

3.90

E+0

1 4.

21E

+01

55

135 C

s Y

es

ML

Bre

it-W

igne

r 4.

63E

+02

Yes

5.

00E

+04

5.00

E+0

1 1.

32E

+02

2.14

E+0

2

55

136 C

s Y

es

ML

Bre

it-W

igne

r 2.

97E

+02

No

4.

23E

+01

6.63

E+0

1 1.

36E

+02

55

137 C

s Y

es

ML

Bre

it-W

igne

r 1.

06E

+04

Yes

1.

00E

+05

7.20

E+0

2 1.

52E

+03

2.07

E+0

3

56

130 B

a Y

es

ML

Bre

it-W

igne

r 2.

53E

+03

Yes

1.

00E

+05

4.63

E+0

1 5.

79E

+01

1.36

E+0

2

56

132 B

a N

o

Y

es

1.00

E+0

5

56

134 B

a Y

es

ML

Bre

it-W

igne

r 1.

06E

+04

Yes

1.

00E

+05

1.02

E+0

2 2.

63E

+02

3.29

E+0

2

56

135 B

a Y

es

ML

Bre

it-W

igne

r 5.

96E

+03

Yes

1.

00E

+05

2.42

E+0

1 8.

15E

+01

8.72

E+0

1

56

136 B

a Y

es

ML

Bre

it-W

igne

r 3.

45E

+04

Yes

1.

00E

+05

4.49

E+0

2 5.

11E

+02

2.16

E+0

3

56

137 B

a Y

es

ML

Bre

it-W

igne

r 1.

19E

+04

Yes

1.

00E

+05

1.27

E+0

2 4.

18E

+02

5.77

E+0

2

56

138 B

a Y

es

ML

Bre

it-W

igne

r 1.

00E

+05

No

7.

88E

+03

3.09

E+0

4 4.

03E

+04

56

140 B

a Y

es

ML

Bre

it-W

igne

r 2.

30E

+04

Yes

1.

00E

+05

1.22

E+0

2 1.

07E

+03

2.87

E+0

3

77

Page 78: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

57

138 L

a Y

es

ML

Bre

it-W

igne

r 3.

30E

+02

Yes

1.

00E

+05

2.99

E+0

0 2.

10E

+01

6.71

E+0

1

57

139 L

a Y

es

ML

Bre

it-W

igne

r 1.

08E

+04

Yes

2.

50E

+05

7.22

E+0

1 8.

76E

+02

9.63

E+0

2

57

140 L

a N

o

58

140 C

e Y

es

ML

Bre

it-W

igne

r 2.

00E

+04

No

2.

54E

+03

6.01

E+0

3 9.

57E

+03

58

141 C

e Y

es

ML

Bre

it-W

igne

r 5.

00E

+02

Yes

1.

00E

+04

2.30

E+0

1 5.

90E

+01

9.50

E+0

1

58

142 C

e Y

es

ML

Bre

it-W

igne

r 4.

88E

+03

Yes

1.

00E

+04

1.29

E+0

3 1.

64E

+03

2.74

E+0

3

58

143 C

e N

o

58

144 C

e Y

es

ML

Bre

it-W

igne

r 1.

04E

+04

Yes

2.

00E

+04

3.60

E+0

2 1.

16E

+03

1.96

E+0

3

59

141 Pr

Y

es

ML

Bre

it-W

igne

r 5.

77E

+03

Yes

3.

00E

+05

8.52

E+0

1 1.

12E

+02

2.19

E+0

2

59

142 Pr

N

o

59

143 Pr

N

o

60

142 N

d Y

es

ML

Bre

it-W

igne

r 1.

11E

+04

No

2.

19E

+02

2.35

E+0

2 6.

36E

+02

60

143 N

d Y

es

ML

Bre

it-W

igne

r 5.

52E

+03

Yes

1.

00E

+04

5.53

E+0

1 1.

27E

+02

1.36

E+0

2

60

144 N

d Y

es

ML

Bre

it-W

igne

r 1.

20E

+04

Yes

5.

00E

+04

3.74

E+0

2 7.

34E

+02

1.28

E+0

3

60

145 N

d Y

es

ML

Bre

it-W

igne

r 2.

17E

+03

Yes

5.

00E

+04

4.35

E+0

0 4.

25E

+01

8.56

E+0

1

60

146 N

d Y

es

ML

Bre

it-W

igne

r 1.

00E

+04

Yes

5.

00E

+04

3.60

E+0

2 7.

23E

+02

8.10

E+0

2

60

147 N

d Y

es

ML

Bre

it-W

igne

r 3.

57E

+01

No

4.

79E

+00

6.26

E+0

0 1.

03E

+01

60

148 N

d Y

es

ML

Bre

it-W

igne

r 7.

70E

+03

Yes

5.

00E

+04

9.49

E+0

1 1.

55E

+02

2.88

E+0

2

60

150 N

d Y

es

ML

Bre

it-W

igne

r 5.

12E

+03

No

7.

88E

+01

2.66

E+0

2 3.

13E

+02

61

147 Pm

Y

es

ML

Bre

it-W

igne

r 3.

19E

+02

Yes

5.

00E

+04

5.36

E+0

0 6.

57E

+00

6.92

E+0

0

61

148 Pm

N

o

61

148m

Pm

Yes

M

L B

reit

-Wig

ner

1.00

E+0

0 N

o

1.69

E-0

1

61

149 Pm

N

o

61

151 Pm

N

o

62

144 Sm

N

o

62

147 Sm

Y

es

ML

Bre

it-W

igne

r 7.

69E

+02

Yes

7.

00E

+04

3.40

E+0

0 1.

83E

+01

2.71

E+0

1

62

148 Sm

N

o

62

149 Sm

Y

es

ML

Bre

it-W

igne

r 5.

20E

+02

Yes

1.

00E

+05

9.73

E-0

2 8.

72E

-01

4.95

E+0

0

62

150 Sm

Y

es

ML

Bre

it-W

igne

r 5.

93E

+02

No

2.

07E

+01

4.81

E+0

1 1.

11E

+02

62

151 Sm

Y

es

ML

Bre

it-W

igne

r 2.

97E

+02

Yes

4.

00E

+03

4.56

E-0

1 1.

09E

+00

1.70

E+0

0

62

152 Sm

Y

es

ML

Bre

it-W

igne

r 3.

69E

+03

Yes

7.

00E

+04

8.05

E+0

0 6.

22E

+01

8.77

E+0

1

62

153 Sm

N

o

78

Page 79: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

62

154 Sm

Y

es

ML

Bre

it-W

igne

r 3.

10E

+03

No

9.

30E

+01

2.61

E+0

2 3.

42E

+02

63

151 E

u Y

es

ML

Bre

it-W

igne

r 9.

88E

+01

Yes

1.

00E

+04

3.21

E-0

1 4.

61E

-01

1.06

E+0

0

63

152 E

u Y

es

ML

Bre

it-W

igne

r 6.

55E

+00

Yes

1.

00E

+05

8.84

E-0

1 1.

34E

+00

1.63

E+0

0

63

153 E

u Y

es

ML

Bre

it-W

igne

r 9.

72E

+01

Yes

1.

00E

+05

1.73

E+0

0 2.

46E

+00

3.29

E+0

0

63

154 E

u Y

es

ML

Bre

it-W

igne

r 6.

30E

+01

Yes

1.

00E

+04

1.90

E-0

1 8.

57E

-01

1.37

E+0

0

63

155 E

u Y

es

ML

Bre

it-W

igne

r 3.

75E

+01

Yes

1.

00E

+04

6.03

E-0

1 2.

04E

+00

7.19

E+0

0

63

156 E

u N

o

63

157 E

u N

o

64

152 G

d Y

es

ML

Bre

it-W

igne

r 2.

66E

+03

Yes

1.

00E

+05

3.31

E+0

0 8.

00E

+00

9.55

E+0

0

64

154 G

d Y

es

ML

Bre

it-W

igne

r 2.

76E

+02

No

9.

41E

+00

1.16

E+0

1 2.

23E

+01

64

155 G

d Y

es

ML

Bre

it-W

igne

r 1.

82E

+02

Yes

1.

00E

+05

2.68

E-0

2 2.

01E

+00

2.57

E+0

0

64

156 G

d Y

es

ML

Bre

it-W

igne

r 1.

58E

+03

Yes

5.

00E

+04

3.31

E+0

1 8.

02E

+01

1.50

E+0

2

64

157 G

d Y

es

ML

Bre

it-W

igne

r 2.

15E

+02

No

3.

14E

-02

2.83

E+0

0 1.

62E

+01

64

158 G

d Y

es

ML

Bre

it-W

igne

r 6.

04E

+03

No

2.

23E

+01

1.01

E+0

2 2.

43E

+02

64

160 G

d Y

es

ML

Bre

it-W

igne

r 2.

88E

+03

No

2.

22E

+02

4.22

E+0

2 4.

48E

+02

65

159 T

b Y

es

ML

Bre

it-W

igne

r 1.

70E

+02

Yes

1.

00E

+04

3.34

E+0

0 4.

98E

+00

1.11

E+0

1

65

160 T

b N

o

66

160 D

y Y

es

ML

Bre

it-W

igne

r 2.

44E

+01

No

1.

88E

+00

1.04

E+0

1 2.

05E

+01

66

161 D

y Y

es

ML

Bre

it-W

igne

r 1.

00E

+03

Yes

1.

00E

+04

2.71

E+0

0 3.

68E

+00

4.33

E+0

0

66

162 D

y Y

es

ML

Bre

it-W

igne

r 1.

22E

+04

Yes

5.

00E

+04

5.44

E+0

0 7.

11E

+01

1.17

E+0

2

66

163 D

y Y

es

ML

Bre

it-W

igne

r 1.

00E

+03

No

1.

71E

+00

5.81

E+0

0 1.

62E

+01

66

164 D

y Y

es

ML

Bre

it-W

igne

r 1.

60E

+04

Yes

5.

00E

+04

1.47

E+0

2 4.

50E

+02

5.36

E+0

2

67

165 H

o Y

es

SL

Bre

it-W

igne

r 1.

52E

+02

No

3.

92E

+00

8.16

E+0

0 1.

28E

+01

68

162 E

r Y

es

ML

Bre

it-W

igne

r 2.

50E

+02

No

5.

48E

+00

7.60

E+0

0 1.

46E

+01

68

164 E

r Y

es

ML

Bre

it-W

igne

r 8.

00E

+02

No

7.

92E

+00

3.05

E+0

1 4.

97E

+01

68

166 E

r Y

es

ML

Bre

it-W

igne

r 3.

00E

+03

No

1.

56E

+01

7.38

E+0

1 8.

17E

+01

68

167 E

r Y

es

ML

Bre

it-W

igne

r 5.

91E

+02

Yes

1.

00E

+04

4.60

E-0

1 5.

83E

-01

5.99

E+0

0

68

168 E

r Y

es

ML

Bre

it-W

igne

r 3.

50E

+03

No

7.

97E

+01

1.89

E+0

2 2.

44E

+02

68

170 E

r Y

es

ML

Bre

it-W

igne

r 3.

00E

+03

No

9.

51E

+01

2.84

E+0

2 4.

97E

+02

71

175 L

u Y

es

ML

Bre

it-W

igne

r 4.

11E

+02

Yes

1.

00E

+04

2.59

E+0

0 4.

75E

+00

5.22

E+0

0

71

176 L

u Y

es

ML

Bre

it-W

igne

r 1.

02E

+02

Yes

1.

00E

+04

1.41

E-0

1 1.

57E

+00

4.36

E+0

0

72

174 H

f Y

es

Rei

ch-M

oore

2.

20E

+02

Yes

5.

00E

+04

4.06

E+0

0 1.

34E

+01

3.00

E+0

1

79

Page 80: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

72

176 H

f Y

es

Rei

ch-M

oore

7.

00E

+02

Yes

5.

00E

+04

7.89

E+0

0 4.

83E

+01

5.33

E+0

1

72

177 H

f Y

es

Rei

ch-M

oore

2.

50E

+02

Yes

5.

00E

+04

1.10

E+0

0 2.

39E

+00

5.90

E+0

0

72

178 H

f Y

es

Rei

ch-M

oore

1.

50E

+03

Yes

5.

00E

+04

7.79

E+0

0 1.

05E

+02

1.65

E+0

2

72

179 H

f Y

es

Rei

ch-M

oore

2.

50E

+02

Yes

5.

00E

+04

5.69

E+0

0 1.

77E

+01

1.91

E+0

1

72

180 H

f Y

es

Rei

ch-M

oore

2.

50E

+03

Yes

5.

00E

+04

7.25

E+0

1 1.

72E

+02

4.47

E+0

2

73

181 T

a Y

es

ML

Bre

it-W

igne

r 2.

40E

+03

Yes

1.

00E

+05

4.28

E+0

0 1.

04E

+01

1.40

E+0

1

73

182 T

a Y

es

ML

Bre

it-W

igne

r 3.

50E

+01

Yes

1.

00E

+04

1.47

E-0

1 1.

82E

+00

5.98

E+0

0

74

182 W

Y

es

ML

Bre

it-W

igne

r 1.

20E

+04

No

4.

15E

+00

2.11

E+0

1 1.

14E

+02

74

183 W

Y

es

ML

Bre

it-W

igne

r 2.

20E

+03

No

7.

64E

+00

2.70

E+0

1 4.

06E

+01

74

184 W

Y

es

ML

Bre

it-W

igne

r 1.

50E

+04

No

1.

02E

+02

1.69

E+0

2 1.

84E

+02

74

186 W

Y

es

ML

Bre

it-W

igne

r 1.

50E

+04

No

1.

88E

+01

1.71

E+0

2 2.

18E

+02

75

185 R

e Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

Yes

3.

50E

+04

2.16

E+0

0 5.

92E

+00

7.22

E+0

0

75

187 R

e Y

es

ML

Bre

it-W

igne

r 2.

00E

+03

Yes

3.

50E

+04

4.42

E+0

0 1.

11E

+01

1.60

E+0

1

76

nat O

s Y

es

ML

Bre

it-W

igne

r 1.

60E

+02

No

76

nat O

s Y

es

ML

Bre

it-W

igne

r 3.

36E

+03

No

2.

24E

+01

4.47

E+0

1 6.

63E

+01

76

nat O

s Y

es

ML

Bre

it-W

igne

r 9.

90E

+02

No

9.

47E

+00

1.27

E+0

1 2.

02E

+01

76

nat O

s Y

es

ML

Bre

it-W

igne

r 5.

00E

+03

No

3.

87E

+01

7.86

E+0

1 1.

50E

+02

76

nat O

s Y

es

ML

Bre

it-W

igne

r 7.

70E

+01

No

6.

71E

+00

8.96

E+0

0 1.

03E

+01

76

nat O

s Y

es

ML

Bre

it-W

igne

r 1.

50E

+02

No

9.

16E

+01

1.45

E+0

2 2.

02E

+02

76

nat O

s Y

es

ML

Bre

it-W

igne

r 1.

50E

+02

No

2.

05E

+01

1.28

E+0

2 2.

00E

+02

77

191 Ir

Y

es

ML

Bre

it-W

igne

r 1.

60E

+02

Yes

1.

00E

+04

6.53

E-0

1 5.

36E

+00

6.13

E+0

0

77

193 Ir

Y

es

ML

Bre

it-W

igne

r 3.

00E

+02

Yes

1.

00E

+04

1.30

E+0

0 9.

07E

+00

2.45

E+0

1

78

nat Pt

N

o

79

197 A

u Y

es

ML

Bre

it-W

igne

r 5.

00E

+03

No

4.

91E

+00

4.65

E+0

1 5.

81E

+01

80

196 H

g Y

es

ML

Bre

it-W

igne

r 1.

03E

+02

No

9.

35E

+01

80

198 H

g Y

es

ML

Bre

it-W

igne

r 4.

59E

+02

No

2.

31E

+01

8.98

E+0

1 3.

03E

+02

80

199 H

g Y

es

ML

Bre

it-W

igne

r 9.

68E

+02

No

3.

35E

+01

1.30

E+0

2 1.

75E

+02

80

200 H

g Y

es

ML

Bre

it-W

igne

r 8.

58E

+03

No

1.

33E

+03

2.71

E+0

3 5.

06E

+03

80

201 H

g Y

es

ML

Bre

it-W

igne

r 7.

54E

+02

No

4.

30E

+01

7.09

E+0

1 2.

10E

+02

80

202 H

g Y

es

ML

Bre

it-W

igne

r 4.

52E

+03

No

1.

71E

+03

4.11

E+0

3

80

204 H

g N

o

81

nat T

l Y

es

SL

Bre

it-W

igne

r 5.

00E

+04

No

2.

38E

+02

8.42

E+0

2 1.

13E

+03

80

Page 81: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

81

nat T

l Y

es

SL

Bre

it-W

igne

r 5.

00E

+04

No

2.

79E

+03

3.04

E+0

3 5.

10E

+03

82

204 Pb

Y

es

ML

Bre

it-W

igne

r 5.

00E

+04

No

1.

69E

+03

2.48

E+0

3 6.

70E

+03

82

206 Pb

Y

es

Rei

ch-M

oore

9.

00E

+05

No

1.

64E

+04

6.60

E+0

4 9.

26E

+04

82

207 Pb

Y

es

Rei

ch-M

oore

4.

75E

+05

No

4.

13E

+04

1.02

E+0

5 1.

82E

+05

82

208 Pb

Y

es

Rei

ch-M

oore

1.

00E

+06

No

5.

06E

+05

8.88

E+0

5 9.

98E

+05

83

209 B

i Y

es

ML

Bre

it-W

igne

r 2.

00E

+05

No

8.

00E

+02

2.31

E+0

3 5.

11E

+03

88

223 R

a N

o

88

224 R

a N

o

88

225 R

a N

o

88

226 R

a Y

es

ML

Bre

it-W

igne

r 1.

00E

+03

No

5.

37E

-01

2.43

E+0

1 3.

91E

+01

89

225 A

c N

o

89

226 A

c N

o

89

227 A

c N

o

90

227 T

h N

o

90

228 T

h Y

es

ML

Bre

it-W

igne

r 7.

80E

+00

No

1.

90E

+00

7.55

E+0

0

90

229 T

h Y

es

SL

Bre

it-W

igne

r 9.

50E

+00

No

6.

09E

-01

1.26

E+0

0 1.

44E

+00

90

230 T

h Y

es

ML

Bre

it-W

igne

r 2.

51E

+02

No

1.

43E

+00

1.73

E+0

1 2.

38E

+01

90

232 T

h Y

es

ML

Bre

it-W

igne

r 4.

00E

+03

Yes

1.

50E

+05

2.18

E+0

1 2.

35E

+01

5.95

E+0

1

90

233 T

h N

o

90

234 T

h N

o

91

231 Pa

Y

es

ML

Bre

it-W

igne

r 1.

43E

+01

Yes

1.

00E

+03

3.96

E-0

1 4.

94E

-01

7.43

E-0

1

91

232 Pa

Y

es

ML

Bre

it-W

igne

r 1.

00E

+01

No

3.

30E

-01

6.90

E-0

1 1.

40E

+00

91

233 Pa

Y

es

ML

Bre

it-W

igne

r 3.

85E

+01

Yes

1.

00E

+04

7.95

E-0

1 1.

34E

+00

1.64

E+0

0

92

232 U

Y

es

ML

Bre

it-W

igne

r 5.

30E

+01

Yes

1.

00E

+03

5.98

E+0

0 1.

27E

+01

2.10

E+0

1

92

233 U

Y

es

Rei

ch-M

oore

1.

50E

+02

Yes

3.

00E

+04

1.70

E-0

1 4.

40E

-01

1.43

E+0

0

92

234 U

Y

es

ML

Bre

it-W

igne

r 1.

50E

+03

Yes

1.

40E

+05

5.16

E+0

0 2.

27E

+01

2.34

E+0

1

92

235 U

Y

es

Rei

ch-M

oore

2.

25E

+03

Yes

2.

50E

+04

3.66

E-0

5 2.

74E

-01

1.13

E+0

0

92

236 U

Y

es

ML

Bre

it-W

igne

r 1.

50E

+03

No

5.

45E

+00

2.97

E+0

1 3.

41E

+01

92

237 U

Y

es

ML

Bre

it-W

igne

r 2.

00E

+02

Yes

1.

00E

+04

1.50

E+0

0 5.

00E

+00

8.50

E+0

0

92

238 U

Y

es

Rei

ch-M

oore

2.

00E

+04

Yes

3.

00E

+05

6.67

E+0

0 2.

09E

+01

3.67

E+0

1

93

235 N

p N

o

93

236 N

p N

o

81

Page 82: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

93

237 N

p Y

es

ML

Bre

it-W

igne

r 5.

00E

+02

Yes

3.

50E

+04

4.90

E-0

1 1.

32E

+00

1.48

E+0

0

93

238 N

p Y

es

ML

Bre

it-W

igne

r 1.

00E

+02

Yes

1.

00E

+04

1.52

E+0

0 2.

57E

+00

3.62

E+0

0

93

239 N

p N

o

94

236 Pu

Y

es

ML

Bre

it-W

igne

r 1.

00E

+01

Yes

3.

00E

+04

3.16

E+0

0 6.

30E

+00

1.20

E+0

1

94

237 Pu

N

o

94

238 Pu

Y

es

ML

Bre

it-W

igne

r 5.

00E

+02

Yes

1.

50E

+05

2.90

E+0

0 9.

98E

+00

1.86

E+0

1

94

239 Pu

Y

es

Rei

ch-M

oore

2.

50E

+03

Yes

3.

00E

+04

2.96

E-0

1 7.

82E

+00

1.09

E+0

1

94

240 Pu

Y

es

Rei

ch-M

oore

5.

70E

+03

Yes

4.

00E

+04

1.06

E+0

0 2.

04E

+01

3.83

E+0

1

94

241 Pu

Y

es

Rei

ch-M

oore

3.

00E

+02

Yes

3.

00E

+04

1.50

E-0

1 2.

64E

-01

1.73

E+0

0

94

242 Pu

Y

es

ML

Bre

it-W

igne

r 1.

15E

+03

Yes

4.

00E

+04

2.67

E+0

0 1.

46E

+01

2.26

E+0

1

94

243 Pu

Y

es

ML

Bre

it-W

igne

r 1.

02E

+02

Yes

1.

00E

+04

1.66

E+0

0 4.

16E

+00

6.66

E+0

0

94

244 Pu

Y

es

ML

Bre

it-W

igne

r 2.

49E

+02

Yes

1.

00E

+04

2.12

E+0

1 3.

26E

+01

4.40

E+0

1

94

246 Pu

N

o

95

241 A

m

Yes

M

L B

reit

-Wig

ner

1.50

E+0

2 Y

es

4.00

E+0

4 3.

07E

-01

5.76

E-0

1 1.

27E

+00

95

242 A

m

Yes

M

L B

reit

-Wig

ner

1.00

E+0

2 Y

es

4.43

E+0

4 3.

50E

-01

2.19

E+0

0 2.

31E

+00

95

242m

Am

Y

es

ML

Bre

it-W

igne

r 4.

30E

+01

Yes

2.

73E

+04

1.78

E-0

1 6.

15E

-01

1.10

E+0

0

95

243 A

m

Yes

M

L B

reit

-Wig

ner

2.50

E+0

2 Y

es

4.24

E+0

4 4.

19E

-01

9.83

E-0

1 1.

36E

+00

95

244 A

m

No

95

244m

Am

N

o

96

240 C

m

Yes

M

L B

reit

-Wig

ner

1.50

E+0

2 Y

es

3.00

E+0

4 3.

39E

+00

1.02

E+0

1 1.

69E

+01

96

241 C

m

No

96

242 C

m

Yes

M

L B

reit

-Wig

ner

2.75

E+0

2 Y

es

4.00

E+0

4 1.

36E

+01

3.03

E+0

1 3.

75E

+01

96

243 C

m

Yes

S

L B

reit

-Wig

ner

7.00

E+0

1 Y

es

4.00

E+0

4 6.

71E

-01

1.14

E+0

0 1.

47E

+00

96

244 C

m

Yes

S

L B

reit

-Wig

ner

5.25

E+0

2 Y

es

1.00

E+0

4 7.

67E

+00

1.68

E+0

1 2.

28E

+01

96

245 C

m

Yes

M

L B

reit

-Wig

ner

1.00

E+0

2 Y

es

5.50

E+0

4 8.

50E

-01

1.98

E+0

0 2.

15E

+00

96

246 C

m

Yes

M

L B

reit

-Wig

ner

4.00

E+0

2 Y

es

4.30

E+0

4 4.

32E

+00

1.53

E+0

1 3.

30E

+01

96

247 C

m

Yes

S

L B

reit

-Wig

ner

6.00

E+0

1 Y

es

3.00

E+0

4 1.

25E

+00

2.92

E+0

0 3.

19E

+00

96

248 C

m

Yes

M

L B

reit

-Wig

ner

1.50

E+0

3 Y

es

3.00

E+0

4 7.

25E

+00

2.69

E+0

1 3.

50E

+01

96

249 C

m

Yes

M

L B

reit

-Wig

ner

1.50

E+0

2 Y

es

2.50

E+0

4 1.

50E

+01

3.00

E+0

1 5.

00E

+01

96

250 C

m

Yes

M

L B

reit

-Wig

ner

1.50

E+0

2 Y

es

3.00

E+0

4 2.

00E

+01

2.70

E+0

2 4.

50E

+02

97

247 B

k Y

es

SL

Bre

it-W

igne

r 1.

50E

+02

No

1.

01E

+00

3.02

E+0

0 5.

03E

+00

97

249 B

k Y

es

ML

Bre

it-W

igne

r 6.

00E

+01

Yes

3.

00E

+04

1.95

E-0

1 1.

34E

+00

1.60

E+0

0

82

Page 83: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 6

. Res

onan

ce d

ata

in t

he J

EF

F-3

.1 g

ener

al-p

urpo

se n

eutr

on d

ata

libra

ry (

cont

.)

Z

Isot

ope

Res

dat

a F

orm

alis

m

Upp

er li

mit

RR

R

Av

para

m in

UR

R

Upp

er li

mit

UR

R

Ene

rgy

of 3

s-w

ave

res.

(eV

)

97

250 B

k Y

es

ML

Bre

it-W

igne

r 1.

00E

+02

Yes

3.

00E

+04

1.82

E+0

0 3.

91E

+00

6.00

E+0

0

98

249 C

f Y

es

ML

Bre

it-W

igne

r 7.

00E

+01

Yes

3.

00E

+04

7.00

E-0

1 3.

88E

+00

5.07

E+0

0

98

250 C

f Y

es

SL

Bre

it-W

igne

r 1.

50E

+02

Yes

3.

00E

+04

1.00

E+0

0 1.

70E

+01

3.30

E+0

1

98

251 C

f Y

es

ML

Bre

it-W

igne

r 1.

64E

+02

Yes

1.

00E

+04

7.12

E-0

1 8.

87E

+00

1.70

E+0

1

98

252 C

f Y

es

ML

Bre

it-W

igne

r 3.

67E

+02

Yes

1.

00E

+04

1.71

E+0

1 3.

46E

+01

5.21

E+0

1

98

254 C

f N

o

99

253 E

s Y

es

ML

Bre

it-W

igne

r 1.

01E

+02

Yes

1.

00E

+04

5.86

E-0

1 4.

31E

+00

8.04

E+0

0

99

254 E

s N

o

99

255 E

s N

o

100

255 Fm

N

o

83

Page 84: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 7

. Con

tent

s of

the

JE

FF

-3.1

the

rmal

sca

tter

ing

law

libr

ary

Mat

eria

l M

AT

no.

M

F1

MF

7

H(H

2O)

1 45

1 4

H(Z

rH)

7 45

1 2,

4

H(C

aH2)

8

451

2, 4

D(D

2O)

11

451

4 4 B

e 26

45

1 2,

4

Gra

phit

e 31

45

1 2,

4

H(C

H2)

37

45

1 2,

4

24M

g 52

45

1 2,

4

Ca(

CaH

2)

59

451

2, 4

84

Page 85: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 8

. Con

tent

s of

the

JE

FF

-3.1

pro

ton

spec

ial-

purp

ose

libra

ry. L

ist

of a

vaila

ble

reac

tion

s (M

Ts)

in fi

les

MF

=3 to

MF

=6.

Z

Sym

M

F1

MF

3 M

F6

20

40C

a 45

1 2,

5

2, 5

20

42C

a 45

1 2,

5

2, 5

20

43C

a 45

1 2,

5

2, 5

20

44C

a 45

1 2,

5

2, 5

20

46C

a 45

1 2,

5

2, 5

20

48C

a 45

1 2,

5

2, 5

21

45Sc

45

1 2,

5

2, 5

22

46T

i 45

1 2,

5

2, 5

22

47T

i 45

1 2,

5

2, 5

22

48T

i 45

1 2,

5

2, 5

22

49T

i 45

1 2,

5

2, 5

22

50T

i 45

1 2,

5

2, 5

26

54Fe

45

1 2,

5

2, 5

26

56Fe

45

1 2,

5

2, 5

26

57Fe

45

1 2,

5

2, 5

26

58Fe

45

1 2,

5

2, 5

32

70G

e 45

1 2,

5

2, 5

32

72G

e 45

1 2,

5

2, 5

32

73G

e 45

1 2,

5

2, 5

32

74G

e 45

1 2,

5

2, 5

32

76G

e 45

1 2,

5

2, 5

82

204 Pb

45

1 2,

5

2, 5

82

206 Pb

45

1 2,

5

2, 5

82

207 Pb

45

1 2,

5

2, 5

82

208 Pb

45

1 2,

5

2, 5

83

209 B

i 45

1 2,

5

2, 5

85

Page 86: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=12

5:H

-1

001

Tot

al

3.04

548E

+01

3.30

070E

+01

1.08

381

2.40

810E

+02

4.00

392E

+00

6.92

003E

-01

002

Ela

stic

3.

0122

8E+0

1 3.

2675

0E+0

1 1.

0847

3 2.

4066

1E+0

2 4.

0039

0E+0

0 6.

9197

4E-0

1 10

2 n,

gam

ma

3.31

982E

-01

3.32

070E

-01

1.00

026

1.49

128E

-01

3.95

867E

-05

2.97

350E

-05

Mat

eria

l(M

AT

)=12

8:H

-2

001

Tot

al

4.23

413E

+00

4.69

340E

+00

1.10

848

4.13

548E

+01

2.54

100E

+00

8.12

870E

-01

002

Ela

stic

4.

2336

2E+0

0 4.

6929

0E+0

0 1.

1084

9 4.

1354

6E+0

1 2.

5352

0E+0

0 6.

4643

7E-0

1 10

2 n,

gam

ma

5.05

707E

-04

5.05

780E

-04

1.00

015

2.28

669E

-04

6.99

577E

-06

9.53

295E

-06

Mat

eria

l(M

AT

)=13

1:H

-3

001

Tot

al

1.98

141E

+00

2.21

350E

+00

1.11

712

2.05

035E

+01

1.95

013E

+00

9.73

764E

-01

002

Ela

stic

1.

9814

1E+0

0 2.

2135

0E+0

0 1.

1171

2 2.

0503

5E+0

1 1.

9499

3E+0

0 9.

2356

4E-0

1

Mat

eria

l(M

AT

)=22

5:H

e-3

001

Tot

al

5.31

964E

+03

5.32

140E

+03

1.00

032

2.41

544E

+03

2.96

585E

+00

1.16

941E

+00

002

Ela

stic

3.

8610

0E+0

0 4.

3149

0E+0

0 1.

1175

7 3.

8645

5E+0

1 2.

1479

6E+0

0 9.

7190

5E-0

1 10

2 n,

gam

ma

3.10

003E

-05

3.10

090E

-05

1.00

027

1.39

449E

-05

4.80

149E

-09

1.32

057E

-09

Mat

eria

l(M

AT

)=22

8:H

e-4

001

Tot

al

8.54

660E

-01

9.58

730E

-01

1.12

176

9.28

162E

+00

3.66

169E

+00

1.05

708E

+00

002

Ela

stic

8.

5466

0E-0

1 9.

5873

0E-0

1 1.

1217

6 9.

2816

2E+0

0 3.

6616

9E+0

0 1.

0570

8E+0

0

Mat

eria

l(M

AT

)=32

5:L

i-6

001

Tot

al

9.41

742E

+02

9.42

080E

+02

1.00

036

4.31

319E

+02

1.92

581E

+00

1.45

307E

+00

002

Ela

stic

7.

2775

4E-0

1 8.

1898

0E-0

1 1.

1253

5 8.

1829

3E+0

0 1.

4448

6E+0

0 8.

6589

1E-0

1 10

2 n,

gam

ma

3.85

004E

-02

3.85

110E

-02

1.00

027

1.73

185E

-02

1.17

405E

-05

1.02

286E

-05

Mat

eria

l(M

AT

)=32

8:L

i-7

001

Tot

al

1.08

499E

+00

1.21

640E

+00

1.12

110

1.25

033E

+01

1.81

894E

+00

1.44

555E

+00

002

Ela

stic

1.

0395

8E+0

0 1.

1710

0E+0

0 1.

1263

8 1.

2482

9E+0

1 1.

6406

5E+0

0 1.

0145

1E+0

0 10

2 n,

gam

ma

4.54

021E

-02

4.54

160E

-02

1.00

030

2.04

148E

-02

7.19

468E

-06

4.12

092E

-06

Mat

eria

l(M

AT

)=42

5:B

e-9

001

Tot

al

6.51

084E

+00

7.33

650E

+00

1.12

682

7.41

846E

+01

2.70

883E

+00

1.01

556E

+00

002

Ela

stic

6.

5020

6E+0

0 7.

3278

0E+0

0 1.

1269

9 7.

4180

6E+0

1 2.

6747

9E+0

0 9.

8772

3E-0

1 10

2 n,

gam

ma

8.77

353E

-03

8.77

590E

-03

1.00

027

3.95

827E

-03

1.16

436E

-05

1.24

715E

-06

Mat

eria

l(M

AT

)=52

5:B

-10

001

Tot

al

3.84

215E

+03

3.84

330E

+03

1.00

030

1.75

052E

+03

2.64

081E

+00

1.46

866E

+00

002

Ela

stic

2.

2504

8E+0

0 2.

5374

0E+0

0 1.

1274

9 2.

6385

4E+0

1 2.

0899

4E+0

0 9.

0883

3E-0

1 10

2 n,

gam

ma

4.99

872E

-01

4.99

840E

-01

0.99

994

2.23

447E

-01

3.32

211E

-05

0.00

000E

+00

86

Page 87: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=52

8:B

-11

001

Tot

al

5.06

677E

+00

5.71

290E

+00

1.12

753

5.93

102E

+01

2.44

559E

+00

1.41

534E

+00

002

Ela

stic

5.

0612

7E+0

0 5.

7074

0E+0

0 1.

1276

6 5.

9307

4E+0

1 2.

4137

1E+0

0 7.

9118

7E-0

1 10

2 n,

gam

ma

5.50

006E

-03

5.50

200E

-03

1.00

035

2.74

777E

-03

2.78

593E

-06

2.14

331E

-07

Mat

eria

l(M

AT

)=60

0:C

-Nat

00

1 T

otal

4.

9413

6E+0

0 5.

5725

0E+0

0 1.

1277

4 5.

7576

9E+0

1 2.

3891

6E+0

0 1.

3023

7E+0

0 00

2 E

last

ic

4.93

799E

+00

5.56

920E

+00

1.12

782

5.75

754E

+01

2.37

556E

+00

8.19

286E

-01

102

n,ga

mm

a 3.

3670

5E-0

3 3.

3774

0E-0

3 1.

0030

7 1.

5281

7E-0

3 9.

4882

6E-0

6 1.

1518

9E-0

4

Mat

eria

l(M

AT

)=72

5:N

-14

001

Tot

al

1.21

698E

+01

1.34

850E

+01

1.10

808

1.11

668E

+02

2.00

777E

+00

1.56

850E

+00

002

Ela

stic

1.

0267

6E+0

1 1.

1582

0E+0

1 1.

1280

6 1.

1081

3E+0

2 1.

8692

6E+0

0 9.

6914

3E-0

1 10

2 n,

gam

ma

7.49

915E

-02

7.49

970E

-02

1.00

008

3.36

688E

-02

3.65

302E

-05

1.72

232E

-05

Mat

eria

l(M

AT

)=72

8:N

-15

001

Tot

al

4.56

325E

+00

5.13

890E

+00

1.12

615

5.21

077E

+01

2.61

947E

+00

1.65

255E

+00

002

Ela

stic

4.

5632

2E+0

0 5.

1389

0E+0

0 1.

1261

5 5.

2107

7E+0

1 2.

6071

7E+0

0 9.

6109

2E-0

1 10

2 n,

gam

ma

2.40

099E

-05

2.40

330E

-05

1.00

096

3.20

621E

-05

1.87

229E

-05

8.60

002E

-06

Mat

eria

l(M

AT

)=82

5:O

-16

001

Tot

al

3.97

321E

+00

4.48

260E

+00

1.12

822

4.68

501E

+01

2.80

403E

+00

1.59

271E

+00

002

Ela

stic

3.

9730

2E+0

0 4.

4825

0E+0

0 1.

1282

2 4.

6850

0E+0

1 2.

7868

6E+0

0 9.

5724

2E-0

1 10

2 n,

gam

ma

1.90

002E

-04

1.90

050E

-04

1.00

028

8.54

667E

-05

2.94

284E

-08

8.09

378E

-09

Mat

eria

l(M

AT

)=82

8:O

-17

001

Tot

al

4.08

957E

+00

4.58

360E

+00

1.12

079

4.49

406E

+01

1.52

525E

+00

1.67

803E

+00

002

Ela

stic

3.

8507

3E+0

0 4.

3447

0E+0

0 1.

1282

7 4.

4832

9E+0

1 1.

3695

1E+0

0 7.

2000

0E-0

1 10

2 n,

gam

ma

3.82

863E

-03

3.82

720E

-03

0.99

962

1.71

412E

-03

1.93

617E

-04

2.08

823E

-04

Mat

eria

l(M

AT

)=92

5:F

-19

001

Tot

al

3.74

669E

+00

4.22

520E

+00

1.12

771

5.14

824E

+01

3.63

682E

+00

1.75

887E

+00

002

Ela

stic

3.

7371

1E+0

0 4.

2156

0E+0

0 1.

1280

4 5.

1467

2E+0

1 2.

6441

0E+0

0 9.

4552

7E-0

1 10

2 n,

gam

ma

9.57

845E

-03

9.58

110E

-03

1.00

028

1.51

906E

-02

2.08

080E

-04

3.53

925E

-05

Mat

eria

l(M

AT

)=11

22:N

a-22

001

Tot

al

2.90

779E

+04

2.91

360E

+04

1.00

202

1.57

862E

+04

2.94

234E

+00

1.61

298E

+00

002

Ela

stic

7.

4157

5E+0

1 8.

3689

0E+0

1 1.

1285

3 9.

6369

2E+0

2 2.

0485

1E+0

0 7.

2902

6E-0

1 10

2 n,

gam

ma

2.52

100E

+02

2.52

580E

+02

1.00

192

1.28

624E

+02

7.72

932E

-04

2.10

470E

-04

Mat

eria

l(M

AT

)=11

25:N

a-23

001

Tot

al

3.62

117E

+00

4.01

830E

+00

1.10

968

1.23

147E

+02

3.42

022E

+00

1.80

909E

+00

002

Ela

stic

3.

0898

0E+0

0 3.

4868

0E+0

0 1.

1284

9 1.

2283

6E+0

2 3.

0427

6E+0

0 1.

0190

4E+0

0 10

2 n,

gam

ma

5.31

372E

-01

5.31

550E

-01

1.00

034

3.10

635E

-01

2.30

165E

-04

1.48

817E

-04

87

Page 88: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=12

25:M

g-24

001

Tot

al

3.87

745E

+00

4.36

920E

+00

1.12

683

5.40

101E

+01

3.55

191E

+00

1.74

764E

+00

002

Ela

stic

3.

8271

6E+0

0 4.

3189

0E+0

0 1.

1284

9 5.

3980

9E+0

1 3.

2056

0E+0

0 5.

2493

7E-0

1 10

2 n,

gam

ma

5.02

895E

-02

5.03

060E

-02

1.00

033

2.91

613E

-02

3.88

811E

-04

3.44

609E

-05

Mat

eria

l(M

AT

)=12

28:M

g-25

001

Tot

al

2.83

737E

+00

3.17

760E

+00

1.11

992

4.13

022E

+01

3.10

292E

+00

1.82

570E

+00

002

Ela

stic

2.

6469

9E+0

0 2.

9872

0E+0

0 1.

1285

2 4.

1205

0E+0

1 2.

7370

6E+0

0 6.

8573

3E-0

1 10

2 n,

gam

ma

1.90

374E

-01

1.90

440E

-01

1.00

033

9.73

437E

-02

3.57

814E

-04

6.98

834E

-06

Mat

eria

l(M

AT

)=12

31:M

g-26

001

Tot

al

2.92

345E

+00

3.29

430E

+00

1.12

685

3.39

465E

+01

3.28

270E

+00

1.85

076E

+00

002

Ela

stic

2.

8851

4E+0

0 3.

2560

0E+0

0 1.

1285

3 3.

3929

3E+0

1 3.

0499

3E+0

0 6.

8158

8E-0

1 10

2 n,

gam

ma

3.83

094E

-02

3.83

220E

-02

1.00

033

1.72

200E

-02

3.22

012E

-04

2.12

583E

-05

Mat

eria

l(M

AT

)=13

25:A

l-27

001

Tot

al

1.68

510E

+00

1.87

180E

+00

1.11

079

2.38

144E

+01

3.24

197E

+00

1.74

426E

+00

002

Ela

stic

1.

4516

4E+0

0 1.

6382

0E+0

0 1.

1285

5 2.

3686

8E+0

1 2.

9251

9E+0

0 7.

7943

7E-0

1 10

2 n,

gam

ma

2.33

463E

-01

2.33

540E

-01

1.00

033

1.27

603E

-01

5.46

344E

-04

6.27

689E

-04

Mat

eria

l(M

AT

)=14

25:S

i-28

001

Tot

al

2.16

030E

+00

2.41

630E

+00

1.11

851

2.38

949E

+01

3.16

056E

+00

1.73

039E

+00

002

Ela

stic

1.

9911

7E+0

0 2.

2471

0E+0

0 1.

1285

5 2.

3813

0E+0

1 2.

9599

7E+0

0 6.

9695

5E-0

1 10

2 n,

gam

ma

1.69

135E

-01

1.69

190E

-01

1.00

033

8.18

819E

-02

6.91

704E

-04

6.32

557E

-04

Mat

eria

l(M

AT

)=14

28:S

i-29

001

Tot

al

2.99

378E

+00

3.36

580E

+00

1.12

428

3.36

688E

+01

3.61

851E

+00

1.75

658E

+00

002

Ela

stic

2.

8922

8E+0

0 3.

2642

0E+0

0 1.

1285

8 3.

3604

1E+0

1 3.

3014

6E+0

0 7.

7079

6E-0

1 10

2 n,

gam

ma

1.01

499E

-01

1.01

690E

-01

1.00

188

6.47

622E

-02

2.99

550E

-04

3.25

080E

-04

Mat

eria

l(M

AT

)=14

31:S

i-30

001

Tot

al

2.64

032E

+00

2.96

650E

+00

1.12

355

3.53

750E

+01

3.59

449E

+00

1.77

936E

+00

002

Ela

stic

2.

5325

6E+0

0 2.

8582

0E+0

0 1.

1285

8 3.

4670

7E+0

1 3.

4182

5E+0

0 7.

3745

1E-0

1 10

2 n,

gam

ma

1.07

758E

-01

1.08

350E

-01

1.00

550

7.04

389E

-01

6.78

705E

-04

4.79

509E

-04

Mat

eria

l(M

AT

)=15

25:P

-31

001

Tot

al

3.35

111E

+00

3.76

070E

+00

1.12

223

3.72

489E

+01

2.88

188E

+00

1.83

244E

+00

002

Ela

stic

3.

1849

3E+0

0 3.

5945

0E+0

0 1.

1285

9 3.

7173

1E+0

1 2.

5547

9E+0

0 1.

1614

3E+0

0 10

2 n,

gam

ma

1.66

183E

-01

1.66

240E

-01

1.00

033

7.58

402E

-02

1.01

302E

-03

9.89

520E

-06

Mat

eria

l(M

AT

)=16

25:S

-32

001

Tot

al

1.51

395E

+00

1.64

090E

+00

1.08

385

1.22

652E

+01

2.77

745E

+00

1.73

826E

+00

002

Ela

stic

9.

7863

9E-0

1 1.

1045

0E+0

0 1.

1286

0 1.

1934

6E+0

1 2.

5344

1E+0

0 7.

6411

4E-0

1 10

2 n,

gam

ma

5.28

204E

-01

5.28

370E

-01

1.00

032

2.45

208E

-01

5.91

342E

-04

3.23

500E

-06

88

Page 89: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=16

28:S

-33

001

Tot

al

3.41

074E

+00

3.80

450E

+00

1.11

543

3.45

035E

+01

2.70

933E

+00

1.76

369E

+00

002

Ela

stic

2.

8878

5E+0

0 3.

2592

0E+0

0 1.

1286

0 3.

2261

9E+0

1 2.

3226

9E+0

0 7.

2960

8E-0

1 10

2 n,

gam

ma

3.50

050E

-01

3.50

160E

-01

1.00

032

1.63

419E

-01

2.06

035E

-04

7.15

924E

-07

Mat

eria

l(M

AT

)=16

31:S

-34

001

Tot

al

2.33

180E

+00

2.60

300E

+00

1.11

631

2.39

443E

+01

2.64

806E

+00

1.77

993E

+00

002

Ela

stic

2.

1082

0E+0

0 2.

3793

0E+0

0 1.

1286

1 2.

3845

1E+0

1 2.

5161

6E+0

0 7.

4804

8E-0

1 10

2 n,

gam

ma

2.23

602E

-01

2.23

670E

-01

1.00

032

9.92

256E

-02

2.77

325E

-04

3.66

670E

-06

Mat

eria

l(M

AT

)=16

37:S

-36

001

Tot

al

2.36

577E

+00

2.65

280E

+00

1.12

133

2.67

993E

+01

2.64

465E

+00

1.82

909E

+00

002

Ela

stic

2.

2153

1E+0

0 2.

5003

0E+0

0 1.

1286

2 2.

6679

2E+0

1 2.

5652

8E+0

0 7.

9344

7E-0

1 10

2 n,

gam

ma

1.50

455E

-01

1.52

560E

-01

1.01

398

1.20

122E

-01

2.49

779E

-04

1.36

924E

-06

Mat

eria

l(M

AT

)=17

25:C

l-35

001

Tot

al

6.50

682E

+01

6.77

940E

+01

1.04

189

1.37

649E

+02

2.82

680E

+00

2.02

639E

+00

002

Ela

stic

2.

0969

0E+0

1 2.

3661

0E+0

1 1.

1283

8 1.

1921

0E+0

2 2.

4762

1E+0

0 8.

9058

9E-0

1 10

2 n,

gam

ma

4.36

185E

+01

4.36

520E

+01

1.00

077

1.79

651E

+01

8.80

508E

-04

4.78

074E

-04

Mat

eria

l(M

AT

)=17

31:C

l-37

001

Tot

al

1.59

639E

+00

1.74

630E

+00

1.09

393

1.89

685E

+01

2.61

868E

+00

2.11

029E

+00

002

Ela

stic

1.

1632

8E+0

0 1.

3129

0E+0

0 1.

1286

2 1.

8765

6E+0

1 2.

4538

4E+0

0 1.

0083

3E+0

0 10

2 n,

gam

ma

4.33

111E

-01

4.33

430E

-01

1.00

074

2.02

939E

-01

4.36

191E

-04

2.86

825E

-04

Mat

eria

l(M

AT

)=18

25:A

r-36

001

Tot

al

7.96

350E

+01

8.93

080E

+01

1.12

147

6.69

243E

+02

2.86

333E

+00

1.82

368E

+00

002

Ela

stic

7.

4591

1E+0

1 8.

4185

0E+0

1 1.

1286

2 6.

6698

2E+0

2 2.

5192

1E+0

0 7.

9207

8E-0

1 10

2 n,

gam

ma

5.04

389E

+00

5.12

340E

+00

1.01

576

2.26

121E

+00

3.41

829E

-03

4.38

002E

-04

Mat

eria

l(M

AT

)=18

31:A

r-38

001

Tot

al

9.74

215E

+00

1.09

250E

+01

1.12

138

7.89

270E

+01

2.75

368E

+00

1.94

775E

+00

002

Ela

stic

8.

9403

4E+0

0 1.

0090

0E+0

1 1.

1286

3 7.

8573

6E+0

1 2.

5511

9E+0

0 8.

3593

3E-0

1 10

2 n,

gam

ma

8.01

803E

-01

8.34

300E

-01

1.04

053

3.53

343E

-01

7.90

696E

-04

1.36

301E

-04

Mat

eria

l(M

AT

)=18

37:A

r-40

001

Tot

al

1.31

519E

+00

1.39

970E

+00

1.06

422

1.07

072E

+01

2.97

259E

+00

2.29

042E

+00

002

Ela

stic

6.

5516

1E-0

1 7.

3944

0E-0

1 1.

1286

5 1.

0418

4E+0

1 2.

5531

3E+0

0 7.

8804

0E-0

1 10

2 n,

gam

ma

6.60

032E

-01

6.60

210E

-01

1.00

027

2.88

811E

-01

1.01

837E

-03

3.46

454E

-04

Mat

eria

l(M

AT

)=19

25:K

-39

001

Tot

al

4.19

098E

+00

4.46

030E

+00

1.06

426

2.27

656E

+01

2.79

479E

+00

2.01

647E

+00

002

Ela

stic

2.

0887

0E+0

0 2.

3574

0E+0

0 1.

1286

3 2.

1690

5E+0

1 2.

5852

4E+0

0 9.

5943

2E-0

1 10

2 n,

gam

ma

2.09

798E

+00

2.09

860E

+00

1.00

028

1.07

007E

+00

2.69

600E

-03

7.42

755E

-06

89

Page 90: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=19

28:K

-40

001

Tot

al

3.75

618E

+01

3.79

020E

+01

1.00

905

4.94

325E

+01

2.84

401E

+00

2.05

040E

+00

002

Ela

stic

2.

7853

8E+0

0 3.

1437

0E+0

0 1.

1286

4 3.

3585

1E+0

1 2.

2966

4E+0

0 9.

8135

6E-0

1 10

2 n,

gam

ma

3.00

006E

+01

3.00

090E

+01

1.00

028

1.34

665E

+01

1.58

449E

-03

4.10

919E

-06

Mat

eria

l(M

AT

)=19

31:K

-41

001

Tot

al

4.05

690E

+00

4.39

150E

+00

1.08

249

3.64

086E

+01

2.86

509E

+00

2.08

421E

+00

002

Ela

stic

2.

5977

3E+0

0 2.

9319

0E+0

0 1.

1286

6 3.

4857

1E+0

1 2.

5129

3E+0

0 1.

0010

8E+0

0 10

2 n,

gam

ma

1.45

918E

+00

1.45

960E

+00

1.00

029

1.55

151E

+00

5.95

575E

-03

1.73

407E

-05

Mat

eria

l(M

AT

)=20

25:C

a-40

001

Tot

al

3.46

997E

+00

3.86

380E

+00

1.11

349

3.31

713E

+01

2.83

215E

+00

2.15

785E

+00

002

Ela

stic

3.

0600

4E+0

0 3.

4537

0E+0

0 1.

1286

5 3.

2964

4E+0

1 2.

6327

9E+0

0 9.

1361

3E-0

1 10

2 n,

gam

ma

4.07

531E

-01

4.07

650E

-01

1.00

030

2.05

769E

-01

1.51

393E

-03

4.12

903E

-04

Mat

eria

l(M

AT

)=20

31:C

a-42

001

Tot

al

1.91

957E

+00

2.07

880E

+00

1.08

296

1.56

843E

+01

3.37

225E

+00

2.15

703E

+00

002

Ela

stic

1.

2365

0E+0

0 1.

3956

0E+0

0 1.

1286

5 1.

5321

0E+0

1 2.

9318

5E+0

0 8.

9302

5E-0

1 10

2 n,

gam

ma

6.83

070E

-01

6.83

240E

-01

1.00

024

3.63

336E

-01

2.66

602E

-03

1.03

534E

-03

Mat

eria

l(M

AT

)=20

34:C

a-43

001

Tot

al

1.58

735E

+01

1.64

180E

+01

1.03

428

1.36

430E

+02

3.36

798E

+00

2.17

612E

+00

002

Ela

stic

4.

2091

5E+0

0 4.

7505

0E+0

0 1.

1286

3 1.

3064

9E+0

2 2.

6896

1E+0

0 9.

0423

2E-0

1 10

2 n,

gam

ma

1.16

642E

+01

1.16

670E

+01

1.00

023

5.78

042E

+00

2.81

581E

-03

1.84

957E

-03

Mat

eria

l(M

AT

)=20

37:C

a-44

001

Tot

al

4.24

620E

+00

4.67

850E

+00

1.10

181

3.58

669E

+01

3.26

208E

+00

2.20

125E

+00

002

Ela

stic

3.

3577

6E+0

0 3.

7898

0E+0

0 1.

1286

7 3.

5447

3E+0

1 2.

7265

6E+0

0 9.

2134

4E-0

1 10

2 n,

gam

ma

8.88

447E

-01

8.88

690E

-01

1.00

027

4.19

537E

-01

1.18

977E

-03

1.36

568E

-03

Mat

eria

l(M

AT

)=20

43:C

a-46

001

Tot

al

7.00

018E

-01

7.00

210E

-01

1.00

027

9.09

167E

+01

3.45

203E

+00

2.24

524E

+00

002

Ela

stic

0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 9.

0598

2E+0

1 2.

9914

3E+0

0 9.

4862

6E-0

1 10

2 n,

gam

ma

7.00

018E

-01

7.00

210E

-01

1.00

027

3.18

522E

-01

5.34

989E

-04

1.39

966E

-03

Mat

eria

l(M

AT

)=20

49:C

a-48

001

Tot

al

4.84

844E

+00

5.33

190E

+00

1.09

972

4.04

005E

+01

3.25

557E

+00

2.29

332E

+00

002

Ela

stic

3.

7555

3E+0

0 4.

2388

0E+0

0 1.

1286

8 3.

9915

7E+0

1 3.

1617

5E+0

0 9.

8020

9E-0

1 10

2 n,

gam

ma

1.09

291E

+00

1.09

310E

+00

1.00

020

4.84

856E

-01

2.04

214E

-04

8.38

941E

-04

Mat

eria

l(M

AT

)=21

25:S

c-45

001

Tot

al

4.98

776E

+01

5.28

040E

+01

1.05

868

2.33

484E

+02

3.38

297E

+00

2.22

608E

+00

002

Ela

stic

2.

2734

1E+0

1 2.

5656

0E+0

1 1.

1285

2 2.

2160

5E+0

2 2.

5128

5E+0

0 9.

9354

2E-0

1 10

2 n,

gam

ma

2.71

415E

+01

2.71

470E

+01

1.00

019

1.18

163E

+01

4.82

458E

-03

1.50

655E

-03

90

Page 91: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=22

25:T

i-46

001

Tot

al

1.05

718E

+01

1.11

390E

+01

1.05

361

1.38

817E

+02

3.31

866E

+00

2.31

722E

+00

002

Ela

stic

4.

4589

9E+0

0 5.

0265

0E+0

0 1.

1272

6 1.

3638

3E+0

2 2.

6347

6E+0

0 1.

0175

5E+0

0 10

2 n,

gam

ma

6.11

286E

+00

6.11

210E

+00

0.99

988

2.43

356E

+00

4.87

896E

-03

5.93

338E

-04

Mat

eria

l(M

AT

)=22

28:T

i-47

001

Tot

al

1.05

709E

+01

1.11

380E

+01

1.05

360

1.38

818E

+02

3.31

858E

+00

2.31

611E

+00

002

Ela

stic

4.

4580

0E+0

0 5.

0254

0E+0

0 1.

1272

7 1.

3638

5E+0

2 2.

3611

2E+0

0 9.

8161

0E-0

1 10

2 n,

gam

ma

6.11

286E

+00

6.11

210E

+00

0.99

988

2.43

356E

+00

5.90

897E

-03

6.06

647E

-04

Mat

eria

l(M

AT

)=22

31:T

i-48

001

Tot

al

1.05

613E

+01

1.11

230E

+01

1.05

317

1.38

743E

+02

3.31

837E

+00

2.32

241E

+00

002

Ela

stic

4.

4484

7E+0

0 5.

0108

0E+0

0 1.

1264

1 1.

3630

9E+0

2 2.

7113

7E+0

0 1.

0263

4E+0

0 10

2 n,

gam

ma

6.11

287E

+00

6.11

210E

+00

0.99

988

2.43

356E

+00

2.26

615E

-03

5.94

579E

-04

Mat

eria

l(M

AT

)=22

34:T

i-49

001

Tot

al

1.05

690E

+01

1.11

350E

+01

1.05

358

1.38

817E

+02

3.31

871E

+00

2.32

236E

+00

002

Ela

stic

4.

4561

6E+0

0 5.

0232

0E+0

0 1.

1272

5 1.

3638

4E+0

2 2.

7759

6E+0

0 9.

9056

1E-0

1 10

2 n,

gam

ma

6.11

287E

+00

6.11

210E

+00

0.99

988

2.43

356E

+00

3.78

821E

-03

6.22

830E

-04

Mat

eria

l(M

AT

)=22

37:T

i-50

001

Tot

al

1.05

682E

+01

1.11

340E

+01

1.05

357

1.38

818E

+02

3.31

869E

+00

2.32

262E

+00

002

Ela

stic

4.

4552

9E+0

0 5.

0222

0E+0

0 1.

1272

4 1.

3638

5E+0

2 2.

8969

7E+0

0 9.

6021

2E-0

1 10

2 n,

gam

ma

6.11

288E

+00

6.11

220E

+00

0.99

988

2.43

356E

+00

8.48

028E

-04

4.79

753E

-04

Mat

eria

l(M

AT

)=23

00:V

-Nat

001

Tot

al

1.02

507E

+01

1.09

190E

+01

1.06

518

2.65

086E

+02

3.85

758E

+00

2.35

807E

+00

002

Ela

stic

5.

2065

6E+0

0 5.

8765

0E+0

0 1.

1286

8 2.

6244

4E+0

2 3.

1930

4E+0

0 1.

1042

9E+0

0 10

2 n,

gam

ma

5.04

419E

+00

5.04

240E

+00

0.99

964

2.64

298E

+00

1.90

136E

-03

6.39

995E

-04

Mat

eria

l(M

AT

)=24

25:C

r-50

001

Tot

al

1.82

987E

+01

1.86

080E

+01

1.01

689

2.60

271E

+02

3.66

852E

+00

2.41

614E

+00

002

Ela

stic

2.

3716

7E+0

0 2.

6770

0E+0

0 1.

1287

3 2.

5280

2E+0

2 2.

9739

9E+0

0 1.

0970

7E+0

0 10

2 n,

gam

ma

1.59

270E

+01

1.59

310E

+01

1.00

023

7.46

971E

+00

4.41

724E

-03

1.08

000E

-03

Mat

eria

l(M

AT

)=24

31:C

r-52

001

Tot

al

3.71

429E

+00

4.09

460E

+00

1.10

239

3.69

913E

+01

3.39

292E

+00

2.44

218E

+00

002

Ela

stic

2.

9542

0E+0

0 3.

3344

0E+0

0 1.

1286

8 3.

6539

1E+0

1 2.

9479

0E+0

0 1.

0835

5E+0

0 10

2 n,

gam

ma

7.60

092E

-01

7.60

250E

-01

1.00

020

4.52

165E

-01

2.11

168E

-03

7.23

925E

-04

Mat

eria

l(M

AT

)=24

34:C

r-53

001

Tot

al

2.59

891E

+01

2.70

120E

+01

1.03

937

3.42

880E

+02

3.78

221E

+00

2.41

771E

+00

002

Ela

stic

7.

9234

9E+0

0 8.

9434

0E+0

0 1.

1287

2 3.

3444

9E+0

2 2.

9969

0E+0

0 1.

0160

4E+0

0 10

2 n,

gam

ma

1.80

656E

+01

1.80

690E

+01

1.00

018

8.43

178E

+00

2.07

872E

-03

9.39

396E

-04

91

Page 92: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=24

37:C

r-54

001

Tot

al

2.92

391E

+00

3.25

390E

+00

1.11

286

4.25

940E

+01

3.67

328E

+00

2.41

770E

+00

002

Ela

stic

2.

5638

8E+0

0 2.

8938

0E+0

0 1.

1286

8 4.

2403

1E+0

1 2.

9828

6E+0

0 1.

0013

2E+0

0 10

2 n,

gam

ma

3.60

034E

-01

3.60

120E

-01

1.00

024

1.90

908E

-01

1.59

417E

-03

5.45

397E

-04

Mat

eria

l(M

AT

)=25

25:M

n-55

001

Tot

al

1.56

008E

+01

1.58

860E

+01

1.01

828

6.15

513E

+02

3.67

946E

+00

2.57

127E

+00

002

Ela

stic

2.

1864

7E+0

0 2.

4680

0E+0

0 1.

1287

5 6.

0374

9E+0

2 2.

8000

2E+0

0 1.

2179

4E+0

0 10

2 n,

gam

ma

1.34

144E

+01

1.34

180E

+01

1.00

027

1.17

637E

+01

2.94

457E

-03

6.63

000E

-04

Mat

eria

l(M

AT

)=26

25:F

e-54

001

Tot

al

4.45

333E

+00

4.73

710E

+00

1.06

372

1.07

745E

+02

3.64

968E

+00

2.60

816E

+00

002

Ela

stic

2.

2016

1E+0

0 2.

4849

0E+0

0 1.

1286

7 1.

0656

3E+0

2 3.

1261

1E+0

0 1.

1870

6E+0

0 10

2 n,

gam

ma

2.25

172E

+00

2.25

220E

+00

1.00

022

1.18

148E

+00

4.88

778E

-03

9.35

309E

-04

Mat

eria

l(M

AT

)=26

31:F

e-56

001

Tot

al

1.47

933E

+01

1.63

650E

+01

1.10

623

1.21

968E

+02

3.24

797E

+00

2.58

777E

+00

002

Ela

stic

1.

2207

3E+0

1 1.

3778

0E+0

1 1.

1286

9 1.

2063

9E+0

2 2.

6264

9E+0

0 1.

1627

8E+0

0 10

2 n,

gam

ma

2.58

593E

+00

2.58

650E

+00

1.00

021

1.32

903E

+00

2.73

132E

-03

7.67

939E

-04

Mat

eria

l(M

AT

)=26

34:F

e-57

001

Tot

al

2.66

648E

+00

2.69

340E

+00

1.01

009

8.30

276E

+01

4.08

150E

+00

2.69

920E

+00

002

Ela

stic

2.

0391

5E-0

1 2.

3015

0E-0

1 1.

1286

6 7.

8511

4E+0

1 2.

5745

6E+0

0 1.

2580

5E+0

0 10

2 n,

gam

ma

2.46

257E

+00

2.46

320E

+00

1.00

027

1.41

952E

+00

1.76

058E

-03

8.92

490E

-04

Mat

eria

l(M

AT

)=26

37:F

e-58

001

Tot

al

8.85

573E

+00

9.82

640E

+00

1.10

961

9.67

920E

+01

4.79

543E

+00

2.71

964E

+00

002

Ela

stic

7.

5412

1E+0

0 8.

5116

0E+0

0 1.

1286

8 9.

5530

0E+0

1 3.

9835

2E+0

0 1.

2755

2E+0

0 10

2 n,

gam

ma

1.31

452E

+00

1.31

480E

+00

1.00

024

1.26

200E

+00

2.10

066E

-03

9.75

096E

-04

Mat

eria

l(M

AT

)=27

22:C

o-58

001

Tot

al

1.95

377E

+03

1.97

300E

+03

1.00

982

1.18

551E

+04

3.91

418E

+00

2.71

649E

+00

002

Ela

stic

7.

3606

1E+0

1 8.

3604

0E+0

1 1.

1358

3 5.

5488

7E+0

3 2.

6237

2E+0

0 1.

2489

0E+0

0 10

2 n,

gam

ma

1.64

607E

+02

1.67

750E

+02

1.01

907

2.19

955E

+02

2.62

689E

-03

7.16

790E

-04

Mat

eria

l(M

AT

)=27

23:C

o-58

M

00

1 T

otal

1.

4504

6E+0

5 1.

4959

0E+0

5 1.

0313

2 2.

3550

6E+0

5 3.

9124

7E+0

0 2.

7194

4E+0

0 00

2 E

last

ic

7.06

280E

+03

8.35

190E

+03

1.18

251

5.90

540E

+04

2.71

667E

+00

1.24

895E

+00

102

n,ga

mm

a 1.

0086

8E+0

5 1.

0344

0E+0

5 1.

0255

1 1.

2780

1E+0

5 4.

3048

3E-0

3 7.

5209

0E-0

4

Mat

eria

l(M

AT

)=27

25:C

o-59

001

Tot

al

4.32

091E

+01

4.40

000E

+01

1.01

829

8.55

772E

+02

3.73

341E

+00

2.71

319E

+00

002

Ela

stic

6.

0317

5E+0

0 6.

8078

0E+0

0 1.

1286

6 7.

7991

1E+0

2 3.

0002

4E+0

0 1.

3897

0E+0

0 10

2 n,

gam

ma

3.71

774E

+01

3.71

920E

+01

1.00

038

7.58

617E

+01

5.00

514E

-03

8.99

996E

-04

92

Page 93: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=28

25:N

i-58

001

Tot

al

2.96

383E

+01

3.28

590E

+01

1.10

865

2.67

948E

+02

3.65

247E

+00

2.71

372E

+00

002

Ela

stic

2.

5017

6E+0

1 2.

8237

0E+0

1 1.

1286

8 2.

6578

0E+0

2 3.

1631

0E+0

0 1.

2953

7E+0

0 10

2 n,

gam

ma

4.62

067E

+00

4.62

170E

+00

1.00

023

2.16

790E

+00

7.81

934E

-03

4.99

542E

-04

Mat

eria

l(M

AT

)=28

28:N

i-59

001

Tot

al

9.83

465E

+01

9.86

710E

+01

1.00

330

5.17

906E

+02

1.19

612E

+01

5.82

713E

+00

002

Ela

stic

2.

3542

7E+0

0 2.

6575

0E+0

0 1.

1287

9 3.

6755

1E+0

2 1.

1816

7E+0

1 4.

6082

1E+0

0 10

2 n,

gam

ma

8.07

520E

+01

8.07

820E

+01

1.00

037

1.26

737E

+02

4.85

057E

-03

5.60

002E

-04

Mat

eria

l(M

AT

)=28

31:N

i-60

001

Tot

al

3.74

894E

+00

3.87

620E

+00

1.03

394

8.02

122E

+01

3.46

259E

+00

2.72

305E

+00

002

Ela

stic

9.

8480

0E-0

1 1.

1115

0E+0

0 1.

1287

0 7.

8839

1E+0

1 2.

9359

8E+0

0 1.

2769

0E+0

0 10

2 n,

gam

ma

2.76

414E

+00

2.76

460E

+00

1.00

018

1.37

324E

+00

6.28

746E

-03

7.56

393E

-04

Mat

eria

l(M

AT

)=28

34:N

i-61

001

Tot

al

1.04

566E

+01

1.14

810E

+01

1.09

800

1.06

184E

+02

3.58

225E

+00

2.76

093E

+00

002

Ela

stic

7.

9580

7E+0

0 8.

9822

0E+0

0 1.

1286

9 1.

0456

7E+0

2 2.

3450

7E+0

0 1.

3077

2E+0

0 10

2 n,

gam

ma

2.49

853E

+00

2.49

910E

+00

1.00

023

1.52

555E

+00

4.91

953E

-03

4.22

401E

-04

Mat

eria

l(M

AT

)=28

37:N

i-62

001

Tot

al

2.43

887E

+01

2.56

720E

+01

1.05

264

4.62

763E

+02

3.64

198E

+00

2.75

836E

+00

002

Ela

stic

9.

9722

7E+0

0 1.

1256

0E+0

1 1.

1287

5 4.

5678

9E+0

2 3.

0698

2E+0

0 1.

2813

2E+0

0 10

2 n,

gam

ma

1.44

164E

+01

1.44

160E

+01

0.99

999

5.97

539E

+00

6.71

034E

-03

2.39

399E

-04

Mat

eria

l(M

AT

)=28

43:N

i-64

001

Tot

al

1.53

452E

+00

1.53

700E

+00

1.00

161

8.56

927E

+01

4.07

532E

+00

2.75

888E

+00

002

Ela

stic

1.

6372

0E-0

2 1.

8480

0E-0

2 1.

1287

4 8.

4940

5E+0

1 3.

5720

6E+0

0 1.

2745

7E+0

0 10

2 n,

gam

ma

1.51

815E

+00

1.51

850E

+00

1.00

024

7.52

291E

-01

4.68

378E

-03

1.93

599E

-04

Mat

eria

l(M

AT

)=29

25:C

u-63

001

Tot

al

9.61

284E

+00

1.02

750E

+01

1.06

891

1.01

779E

+02

3.66

096E

+00

2.91

220E

+00

002

Ela

stic

5.

1432

4E+0

0 5.

8049

0E+0

0 1.

1286

5 9.

6850

3E+0

1 2.

8782

7E+0

0 1.

4749

9E+0

0 10

2 n,

gam

ma

4.46

960E

+00

4.47

030E

+00

1.00

016

4.92

903E

+00

1.07

519E

-02

2.72

000E

-03

Mat

eria

l(M

AT

)=29

31:C

u-65

001

Tot

al

1.60

409E

+01

1.78

290E

+01

1.11

148

1.52

485E

+02

3.74

049E

+00

2.95

880E

+00

002

Ela

stic

1.

3892

1E+0

1 1.

5680

0E+0

1 1.

1286

9 1.

5030

7E+0

2 3.

0414

0E+0

0 1.

4027

4E+0

0 10

2 n,

gam

ma

2.14

880E

+00

2.14

930E

+00

1.00

023

2.17

899E

+00

7.10

443E

-03

5.20

002E

-04

Mat

eria

l(M

AT

)=30

00:Z

n-N

at

00

1 T

otal

5.

3048

4E+0

0 5.

8490

0E+0

0 1.

1025

7 9.

9797

0E+0

1 3.

8036

8E+0

0 2.

9500

0E+0

0 00

2 E

last

ic

4.22

602E

+00

4.76

990E

+00

1.12

870

9.73

000E

+01

3.15

852E

+00

1.69

709E

+00

102

n,ga

mm

a 1.

0788

2E+0

0 1.

0791

0E+0

0 1.

0002

2 2.

4971

6E+0

0 1.

5892

8E-0

2 2.

4869

9E-0

3

93

Page 94: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=31

00:G

a-N

at

00

1 T

otal

9.

8479

7E+0

0 1.

0755

0E+0

1 1.

0921

1 2.

2604

7E+0

2 3.

8048

0E+0

0 3.

2306

9E+0

0 00

2 E

last

ic

7.04

515E

+00

7.95

160E

+00

1.12

866

2.02

347E

+02

2.95

062E

+00

1.62

693E

+00

102

n,ga

mm

a 2.

8028

3E+0

0 2.

8035

0E+0

0 1.

0002

5 2.

3699

3E+0

1 1.

5313

1E-0

2 7.

6136

4E-0

4

Mat

eria

l(M

AT

)=32

25:G

e-70

001

Tot

al

1.55

257E

+01

1.71

460E

+01

1.10

434

1.43

586E

+02

4.39

187E

+00

3.28

016E

+00

002

Ela

stic

1.

2590

7E+0

1 1.

4210

0E+0

1 1.

1286

3 1.

4122

0E+0

2 3.

5130

3E+0

0 1.

7332

3E+0

0 10

2 n,

gam

ma

2.93

501E

+00

2.93

550E

+00

1.00

016

2.36

557E

+00

2.17

554E

-02

6.86

584E

-04

Mat

eria

l(M

AT

)=32

31:G

e-72

001

Tot

al

9.97

383E

+00

1.11

530E

+01

1.11

824

1.04

549E

+02

4.57

000E

+00

3.31

673E

+00

002

Ela

stic

9.

1636

9E+0

0 1.

0343

0E+0

1 1.

1286

8 1.

0380

1E+0

2 3.

4941

0E+0

0 1.

7408

1E+0

0 10

2 n,

gam

ma

8.10

138E

-01

8.10

300E

-01

1.00

020

7.47

966E

-01

1.74

680E

-02

8.69

823E

-04

Mat

eria

l(M

AT

)=32

34:G

e-73

001

Tot

al

1.92

357E

+01

1.98

610E

+01

1.03

250

4.61

939E

+02

4.11

702E

+00

3.31

387E

+00

002

Ela

stic

4.

8331

1E+0

0 5.

4544

0E+0

0 1.

1285

6 3.

9962

0E+0

2 2.

7881

5E+0

0 1.

7127

6E+0

0 10

2 n,

gam

ma

1.44

026E

+01

1.44

060E

+01

1.00

027

6.22

392E

+01

1.40

008E

-02

7.05

540E

-04

Mat

eria

l(M

AT

)=32

37:G

e-74

001

Tot

al

7.26

637E

+00

8.14

750E

+00

1.12

126

9.73

499E

+01

4.44

431E

+00

3.34

262E

+00

002

Ela

stic

6.

8462

8E+0

0 7.

7274

0E+0

0 1.

1286

9 9.

6932

0E+0

1 3.

3025

4E+0

0 1.

7164

5E+0

0 10

2 n,

gam

ma

4.20

090E

-01

4.20

160E

-01

1.00

017

4.18

082E

-01

6.08

952E

-03

8.12

471E

-04

Mat

eria

l(M

AT

)=32

43:G

e-76

001

Tot

al

7.91

114E

+00

8.91

010E

+00

1.12

628

1.00

008E

+02

4.56

345E

+00

3.39

814E

+00

002

Ela

stic

7.

7611

2E+0

0 8.

7601

0E+0

0 1.

1287

1 9.

8702

2E+0

1 3.

4041

0E+0

0 1.

7772

6E+0

0 10

2 n,

gam

ma

1.50

021E

-01

1.50

060E

-01

1.00

025

1.30

591E

+00

2.63

586E

-03

9.78

019E

-04

Mat

eria

l(M

AT

)=33

25:A

s-75

001

Tot

al

6.19

044E

+00

6.43

540E

+00

1.03

958

1.83

644E

+02

4.07

585E

+00

3.73

274E

+00

002

Ela

stic

1.

8892

9E+0

0 2.

1323

0E+0

0 1.

1286

3 1.

2374

2E+0

2 2.

8363

5E+0

0 2.

4546

3E+0

0 10

2 n,

gam

ma

4.30

115E

+00

4.30

310E

+00

1.00

046

5.99

015E

+01

4.59

555E

-02

1.53

781E

-03

Mat

eria

l(M

AT

)=34

25:S

e-74

001

Tot

al

5.16

882E

+01

5.17

410E

+01

1.00

101

1.32

547E

+03

4.67

325E

+00

6.23

995E

+00

002

Ela

stic

1.

0159

4E-0

2 1.

1242

0E-0

2 1.

1065

7 7.

4576

7E+0

2 3.

6581

5E+0

0 4.

4790

0E+0

0 10

2 n,

gam

ma

5.16

780E

+01

5.17

290E

+01

1.00

099

5.79

705E

+02

2.94

543E

-02

1.64

001E

-03

Mat

eria

l(M

AT

)=34

31:S

e-76

001

Tot

al

8.69

202E

+01

8.71

900E

+01

1.00

310

1.33

606E

+02

4.13

803E

+00

3.76

858E

+00

002

Ela

stic

1.

9171

3E+0

0 2.

1639

0E+0

0 1.

1287

0 8.

9216

4E+0

1 3.

3708

7E+0

0 2.

5005

6E+0

0 10

2 n,

gam

ma

8.50

031E

+01

8.50

260E

+01

1.00

027

4.43

899E

+01

3.64

057E

-02

1.62

327E

-03

95 94

Page 95: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=34

34:S

e-77

001

Tot

al

4.44

167E

+01

4.47

390E

+01

1.00

726

1.44

659E

+02

4.19

914E

+00

3.79

736E

+00

002

Ela

stic

2.

4150

8E+0

0 2.

7259

0E+0

0 1.

1286

9 1.

0871

0E+0

2 2.

9208

0E+0

0 2.

5377

3E+0

0 10

2 n,

gam

ma

4.20

016E

+01

4.20

130E

+01

1.00

028

3.59

489E

+01

4.11

323E

-02

2.06

045E

-03

Mat

eria

l(M

AT

)=34

37:S

e-78

001

Tot

al

2.95

097E

+00

3.27

940E

+00

1.11

129

6.84

704E

+01

4.26

703E

+00

3.83

190E

+00

002

Ela

stic

2.

5509

2E+0

0 2.

8792

0E+0

0 1.

1287

1 6.

3955

2E+0

1 3.

4789

5E+0

0 2.

6043

8E+0

0 10

2 n,

gam

ma

4.00

054E

-01

4.00

160E

-01

1.00

027

4.51

521E

+00

1.50

675E

-02

1.52

333E

-03

Mat

eria

l(M

AT

)=34

40:S

e-79

001

Tot

al

5.63

420E

+01

5.71

860E

+01

1.01

498

1.82

151E

+02

4.98

592E

+00

3.84

400E

+00

002

Ela

stic

6.

3402

5E+0

0 7.

1711

0E+0

0 1.

1310

5 1.

2147

2E+0

2 3.

6272

8E+0

0 2.

5169

3E+0

0 10

2 n,

gam

ma

5.00

018E

+01

5.00

150E

+01

1.00

027

6.06

797E

+01

3.09

790E

-02

1.00

054E

-03

Mat

eria

l(M

AT

)=34

43:S

e-80

001

Tot

al

1.68

050E

+00

1.81

840E

+00

1.08

207

1.13

629E

+02

4.41

486E

+00

3.89

107E

+00

002

Ela

stic

1.

0703

7E+0

0 1.

2081

0E+0

0 1.

1286

9 1.

1262

8E+0

2 3.

6516

8E+0

0 2.

6938

1E+0

0 10

2 n,

gam

ma

6.10

128E

-01

6.10

300E

-01

1.00

028

1.00

143E

+00

1.51

340E

-02

1.45

032E

-03

Mat

eria

l(M

AT

)=34

49:S

e-82

001

Tot

al

2.96

072E

+00

3.33

600E

+00

1.12

677

4.91

176E

+01

4.54

578E

+00

3.95

270E

+00

002

Ela

stic

2.

9157

1E+0

0 3.

2910

0E+0

0 1.

1287

2 4.

9050

7E+0

1 3.

8244

1E+0

0 2.

7975

5E+0

0 10

2 n,

gam

ma

4.50

079E

-02

4.50

190E

-02

1.00

026

6.70

126E

-02

4.61

867E

-03

1.32

207E

-03

Mat

eria

l(M

AT

)=35

25:B

r-79

001

Tot

al

1.35

428E

+01

1.38

640E

+01

1.02

369

2.51

831E

+02

4.33

777E

+00

3.86

129E

+00

002

Ela

stic

2.

4402

1E+0

0 2.

7539

0E+0

0 1.

1285

7 1.

1585

0E+0

2 3.

0075

6E+0

0 2.

6274

7E+0

0 10

2 n,

gam

ma

1.11

026E

+01

1.11

100E

+01

1.00

063

1.35

981E

+02

8.73

364E

-02

1.72

088E

-03

Mat

eria

l(M

AT

)=35

31:B

r-81

001

Tot

al

6.94

178E

+00

7.47

900E

+00

1.07

738

1.88

174E

+02

4.47

974E

+00

3.91

687E

+00

002

Ela

stic

4.

1660

0E+0

0 4.

7020

0E+0

0 1.

1286

6 1.

3390

4E+0

2 3.

4443

3E+0

0 2.

6854

5E+0

0 10

2 n,

gam

ma

2.77

578E

+00

2.77

700E

+00

1.00

043

5.42

704E

+01

5.89

765E

-02

1.63

915E

-03

Mat

eria

l(M

AT

)=36

25:K

r-78

001

Tot

al

1.36

121E

+01

1.47

400E

+01

1.08

285

1.68

139E

+02

5.07

189E

+00

3.78

486E

+00

002

Ela

stic

8.

7654

9E+0

0 9.

8930

0E+0

0 1.

1286

3 1.

4478

5E+0

2 3.

5154

2E+0

0 1.

9266

0E+0

0 10

2 n,

gam

ma

4.84

661E

+00

4.84

690E

+00

1.00

005

2.33

538E

+01

7.15

888E

-02

1.76

983E

-04

Mat

eria

l(M

AT

)=36

31:K

r-80

001

Tot

al

2.06

734E

+01

2.18

240E

+01

1.05

565

3.13

919E

+02

5.23

669E

+00

3.65

418E

+00

002

Ela

stic

8.

9353

0E+0

0 1.

0084

0E+0

1 1.

1285

1 2.

4552

5E+0

2 3.

8126

5E+0

0 1.

9375

6E+0

0 10

2 n,

gam

ma

1.17

381E

+01

1.17

400E

+01

1.00

019

6.83

936E

+01

4.28

568E

-02

1.04

505E

-03

95

Page 96: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=36

37:K

r-82

001

Tot

al

3.99

432E

+01

4.11

960E

+01

1.03

137

3.85

861E

+02

5.01

738E

+00

3.78

332E

+00

002

Ela

stic

9.

7700

4E+0

0 1.

1023

0E+0

1 1.

1282

6 2.

0267

7E+0

2 3.

8987

8E+0

0 2.

0444

0E+0

0 10

2 n,

gam

ma

3.01

731E

+01

3.01

730E

+01

1.00

000

1.83

184E

+02

1.85

246E

-02

3.36

355E

-05

Mat

eria

l(M

AT

)=36

40:K

r-83

001

Tot

al

2.18

072E

+02

2.18

180E

+02

1.00

052

3.35

645E

+02

5.18

901E

+00

3.50

009E

+00

002

Ela

stic

1.

0411

2E+0

1 1.

1712

0E+0

1 1.

1249

7 1.

4301

1E+0

2 3.

6929

2E+0

0 2.

0754

9E+0

0 10

2 n,

gam

ma

2.07

661E

+02

2.06

470E

+02

0.99

428

1.91

687E

+02

3.95

263E

-02

4.05

716E

-05

Mat

eria

l(M

AT

)=36

43:K

r-84

001

Tot

al

6.83

268E

+00

7.70

160E

+00

1.12

717

1.06

202E

+02

5.24

608E

+00

3.84

927E

+00

002

Ela

stic

6.

7497

9E+0

0 7.

6187

0E+0

0 1.

1287

3 1.

0275

2E+0

2 4.

1687

1E+0

0 2.

1048

6E+0

0 10

2 n,

gam

ma

8.28

891E

-02

8.29

130E

-02

1.00

029

3.45

012E

+00

7.31

558E

-03

2.16

013E

-05

Mat

eria

l(M

AT

)=36

46:K

r-85

001

Tot

al

5.22

436E

+00

5.69

530E

+00

1.09

014

7.94

170E

+01

4.76

214E

+00

4.03

083E

+00

002

Ela

stic

3.

5643

0E+0

0 4.

0348

0E+0

0 1.

1320

0 7.

7773

8E+0

1 4.

3505

0E+0

0 2.

8649

6E+0

0 10

2 n,

gam

ma

1.66

006E

+00

1.66

050E

+00

1.00

027

1.64

321E

+00

5.58

426E

-03

2.00

911E

-03

Mat

eria

l(M

AT

)=36

49:K

r-86

001

Tot

al

6.10

820E

+00

6.88

650E

+00

1.12

741

1.01

108E

+02

5.54

416E

+00

3.91

874E

+00

002

Ela

stic

6.

0467

3E+0

0 6.

8250

0E+0

0 1.

1287

1 1.

0097

2E+0

2 4.

6839

7E+0

0 2.

1621

8E+0

0 10

2 n,

gam

ma

6.14

645E

-02

6.14

780E

-02

1.00

023

1.36

106E

-01

1.29

145E

-03

5.31

394E

-06

Mat

eria

l(M

AT

)=37

25:R

b-85

001

Tot

al

6.81

099E

+00

7.62

630E

+00

1.11

970

1.17

884E

+02

4.77

926E

+00

4.03

089E

+00

002

Ela

stic

6.

3345

4E+0

0 7.

1498

0E+0

0 1.

1286

9 1.

1166

5E+0

2 3.

8516

2E+0

0 2.

8393

6E+0

0 10

2 n,

gam

ma

4.76

452E

-01

4.76

550E

-01

1.00

020

6.21

950E

+00

2.81

558E

-02

7.37

329E

-04

Mat

eria

l(M

AT

)=37

28:R

b-86

001

Tot

al

8.49

793E

+00

8.97

430E

+00

1.05

606

1.01

906E

+02

4.83

008E

+00

4.05

370E

+00

002

Ela

stic

3.

5978

4E+0

0 4.

0733

0E+0

0 1.

1321

6 7.

7995

2E+0

1 3.

7497

8E+0

0 2.

8605

2E+0

0 10

2 n,

gam

ma

4.90

009E

+00

4.90

100E

+00

1.00

018

2.39

106E

+01

1.08

713E

-02

2.16

141E

-03

Mat

eria

l(M

AT

)=37

31:R

b-87

001

Tot

al

2.47

264E

+00

2.77

550E

+00

1.12

247

7.25

427E

+01

4.91

192E

+00

4.07

523E

+00

002

Ela

stic

2.

3526

4E+0

0 2.

6554

0E+0

0 1.

1287

0 7.

0471

2E+0

1 4.

0020

7E+0

0 2.

8983

1E+0

0 10

2 n,

gam

ma

1.20

001E

-01

1.20

030E

-01

1.00

028

2.07

165E

+00

2.86

419E

-03

7.64

339E

-05

Mat

eria

l(M

AT

)=38

25:S

r-84

001

Tot

al

4.74

353E

+00

5.24

980E

+00

1.10

672

1.24

233E

+02

5.06

453E

+00

6.26

200E

+00

002

Ela

stic

3.

9311

1E+0

0 4.

4370

0E+0

0 1.

1287

0 1.

1404

1E+0

2 4.

1829

8E+0

0 4.

6647

2E+0

0 10

2 n,

gam

ma

8.12

427E

-01

8.12

730E

-01

1.00

038

1.01

928E

+01

6.81

472E

-02

2.02

001E

-03

96

Page 97: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=38

31:S

r-86

001

Tot

al

5.07

848E

+00

5.36

730E

+00

1.05

687

1.17

934E

+02

4.83

674E

+00

4.05

035E

+00

002

Ela

stic

2.

2381

0E+0

0 2.

5261

0E+0

0 1.

1286

8 1.

1283

6E+0

2 4.

3287

5E+0

0 2.

8383

1E+0

0 10

2 n,

gam

ma

2.84

038E

+00

2.84

120E

+00

1.00

028

5.09

801E

+00

1.79

912E

-02

1.95

121E

-03

Mat

eria

l(M

AT

)=38

34:S

r-87

001

Tot

al

1.92

555E

+01

1.97

680E

+01

1.02

661

1.86

436E

+02

4.90

578E

+00

4.07

492E

+00

002

Ela

stic

3.

2476

3E+0

0 3.

6645

0E+0

0 1.

1283

6 6.

8012

3E+0

1 4.

3701

0E+0

0 2.

8953

4E+0

0 10

2 n,

gam

ma

1.60

079E

+01

1.61

030E

+01

1.00

597

1.18

424E

+02

1.95

297E

-02

2.38

936E

-03

Mat

eria

l(M

AT

)=38

37:S

r-88

001

Tot

al

3.64

252E

+00

4.11

060E

+00

1.12

851

4.40

012E

+01

4.83

970E

+00

4.09

786E

+00

002

Ela

stic

3.

6367

2E+0

0 4.

1048

0E+0

0 1.

1287

2 4.

3995

5E+0

1 4.

5207

7E+0

0 2.

9466

1E+0

0 10

2 n,

gam

ma

5.80

024E

-03

5.80

180E

-03

1.00

027

5.76

642E

-03

1.27

540E

-03

1.59

881E

-03

Mat

eria

l(M

AT

)=38

40:S

r-89

001

Tot

al

4.08

464E

+00

4.55

650E

+00

1.11

551

7.05

337E

+01

5.03

845E

+00

4.11

974E

+00

002

Ela

stic

3.

6646

3E+0

0 4.

1363

0E+0

0 1.

1287

2 7.

0042

3E+0

1 4.

7459

6E+0

0 2.

9626

2E+0

0 10

2 n,

gam

ma

4.20

015E

-01

4.20

130E

-01

1.00

027

4.91

440E

-01

8.19

075E

-03

2.15

555E

-03

Mat

eria

l(M

AT

)=38

43:S

r-90

001

Tot

al

4.59

500E

+00

5.08

400E

+00

1.10

643

5.82

125E

+01

5.08

317E

+00

4.14

078E

+00

002

Ela

stic

3.

6949

7E+0

0 4.

1838

0E+0

0 1.

1322

9 5.

7732

0E+0

1 4.

4065

3E+0

0 2.

9699

8E+0

0 10

2 n,

gam

ma

9.00

032E

-01

9.00

280E

-01

1.00

027

4.80

433E

-01

5.94

259E

-03

1.50

930E

-03

Mat

eria

l(M

AT

)=39

25:Y

-89

00

1 T

otal

9.

0166

1E+0

0 9.

8696

0E+0

0 1.

0946

0 9.

4893

8E+0

1 5.

6355

6E+0

0 3.

8569

3E+0

0 00

2 E

last

ic

7.73

094E

+00

8.58

360E

+00

1.11

029

9.39

966E

+01

4.91

895E

+00

2.24

392E

+00

102

n,ga

mm

a 1.

2856

7E+0

0 1.

2860

0E+0

0 1.

0002

3 8.

9724

0E-0

1 4.

7608

0E-0

3 6.

9773

4E-0

4

Mat

eria

l(M

AT

)=39

28:Y

-90

00

1 T

otal

7.

2053

5E+0

0 7.

6997

0E+0

0 1.

0686

1 8.

8258

2E+0

1 5.

0857

8E+0

0 4.

1399

1E+0

0 00

2 E

last

ic

3.70

523E

+00

4.19

870E

+00

1.13

317

8.36

077E

+01

3.96

739E

+00

2.94

810E

+00

102

n,ga

mm

a 3.

5001

3E+0

0 3.

5011

0E+0

0 1.

0002

7 4.

6504

3E+0

0 1.

7687

5E-0

2 1.

9223

7E-0

3

Mat

eria

l(M

AT

)=39

31:Y

-91

00

1 T

otal

5.

1227

0E+0

0 5.

6120

0E+0

0 1.

0955

2 7.

7460

8E+0

1 5.

1484

6E+0

0 4.

1619

5E+0

0 00

2 E

last

ic

3.72

265E

+00

4.21

160E

+00

1.13

134

7.58

331E

+01

4.14

353E

+00

2.85

036E

+00

102

n,ga

mm

a 1.

4000

5E+0

0 1.

4004

0E+0

0 1.

0002

7 1.

6276

7E+0

0 6.

7733

3E-0

3 1.

6563

6E-0

3

Mat

eria

l(M

AT

)=40

25:Z

r-90

001

Tot

al

5.40

629E

+00

6.10

080E

+00

1.12

846

7.73

259E

+01

5.73

633E

+00

3.83

550E

+00

002

Ela

stic

5.

3951

7E+0

0 6.

0897

0E+0

0 1.

1287

2 7.

7185

4E+0

1 5.

2559

2E+0

0 2.

1724

4E+0

0 10

2 n,

gam

ma

1.11

263E

-02

1.11

290E

-02

1.00

021

1.40

601E

-01

6.28

599E

-03

1.03

383E

-03

97

Page 98: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=40

28:Z

r-91

001

Tot

al

1.18

921E

+01

1.32

620E

+01

1.11

519

1.50

977E

+02

5.74

780E

+00

3.84

553E

+00

002

Ela

stic

1.

0644

4E+0

1 1.

2014

0E+0

1 1.

1286

7 1.

4408

9E+0

2 5.

0602

8E+0

0 2.

1398

5E+0

0 10

2 n,

gam

ma

1.24

766E

+00

1.24

790E

+00

1.00

017

6.88

861E

+00

9.20

165E

-03

1.00

200E

-03

Mat

eria

l(M

AT

)=40

31:Z

r-92

001

Tot

al

7.37

830E

+00

8.29

840E

+00

1.12

471

1.13

649E

+02

5.76

145E

+00

3.84

583E

+00

002

Ela

stic

7.

1490

8E+0

0 8.

0692

0E+0

0 1.

1287

0 1.

1302

9E+0

2 4.

7691

3E+0

0 2.

1082

4E+0

0 10

2 n,

gam

ma

2.29

214E

-01

2.29

260E

-01

1.00

021

6.20

763E

-01

1.52

913E

-02

1.02

401E

-03

Mat

eria

l(M

AT

)=40

34:Z

r-93

001

Tot

al

7.68

851E

+00

8.44

970E

+00

1.09

900

1.81

202E

+02

5.62

826E

+00

4.11

875E

+00

002

Ela

stic

5.

9078

9E+0

0 6.

6682

0E+0

0 1.

1286

9 1.

4816

6E+0

2 4.

5545

9E+0

0 2.

3807

7E+0

0 10

2 n,

gam

ma

1.78

062E

+00

1.78

150E

+00

1.00

049

3.30

361E

+01

1.46

075E

-02

1.00

828E

-03

Mat

eria

l(M

AT

)=40

37:Z

r-94

001

Tot

al

6.23

477E

+00

7.03

090E

+00

1.12

769

8.94

050E

+01

5.75

911E

+00

3.84

357E

+00

002

Ela

stic

6.

1849

5E+0

0 6.

9810

0E+0

0 1.

1287

1 8.

9145

1E+0

1 4.

7620

8E+0

0 2.

1374

8E+0

0 10

2 n,

gam

ma

4.98

188E

-02

4.98

280E

-02

1.00

019

2.60

082E

-01

9.77

974E

-03

1.00

184E

-03

Mat

eria

l(M

AT

)=40

40:Z

r-95

001

Tot

al

5.64

375E

+00

6.34

130E

+00

1.12

359

1.32

316E

+02

5.72

506E

+00

4.19

620E

+00

002

Ela

stic

5.

4187

6E+0

0 6.

1162

0E+0

0 1.

1287

1 1.

2656

1E+0

2 4.

9477

9E+0

0 2.

4271

8E+0

0 10

2 n,

gam

ma

2.24

993E

-01

2.25

080E

-01

1.00

038

5.75

529E

+00

1.35

755E

-02

2.00

725E

-03

Mat

eria

l(M

AT

)=40

43:Z

r-96

001

Tot

al

6.18

599E

+00

6.97

930E

+00

1.12

825

1.04

150E

+02

5.79

846E

+00

3.84

628E

+00

002

Ela

stic

6.

1631

9E+0

0 6.

9565

0E+0

0 1.

1287

2 9.

8316

2E+0

1 5.

1589

3E+0

0 2.

1156

7E+0

0 10

2 n,

gam

ma

2.28

057E

-02

2.28

180E

-02

1.00

054

5.83

434E

+00

5.74

046E

-03

1.00

053E

-03

Mat

eria

l(M

AT

)=41

25:N

b-93

001

Tot

al

7.51

996E

+00

8.26

500E

+00

1.09

907

9.53

486E

+01

5.79

033E

+00

3.96

935E

+00

002

Ela

stic

6.

3646

6E+0

0 7.

1076

0E+0

0 1.

1167

3 8.

5601

2E+0

1 4.

5316

8E+0

0 2.

1091

8E+0

0 10

2 n,

gam

ma

1.15

530E

+00

1.15

730E

+00

1.00

176

9.74

724E

+00

2.78

472E

-02

5.60

002E

-04

Mat

eria

l(M

AT

)=41

28:N

b-94

001

Tot

al

2.22

549E

+01

2.30

720E

+01

1.03

671

2.36

241E

+02

5.73

091E

+00

4.32

530E

+00

002

Ela

stic

6.

4870

8E+0

0 7.

3195

0E+0

0 1.

1283

2 1.

1077

2E+0

2 4.

1432

5E+0

0 2.

8142

4E+0

0 10

2 n,

gam

ma

1.57

678E

+01

1.57

520E

+01

0.99

903

1.25

363E

+02

1.79

928E

-02

1.00

541E

-03

Mat

eria

l(M

AT

)=41

31:N

b-95

001

Tot

al

1.27

305E

+01

1.34

810E

+01

1.05

894

1.39

891E

+02

5.71

855E

+00

4.32

526E

+00

002

Ela

stic

5.

7302

8E+0

0 6.

4787

0E+0

0 1.

1306

1 9.

8388

4E+0

1 4.

8411

4E+0

0 2.

8169

4E+0

0 10

2 n,

gam

ma

7.00

025E

+00

7.00

220E

+00

1.00

028

4.15

029E

+01

6.84

151E

-02

1.00

995E

-03

98

Page 99: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=42

25:M

o-92

001

Tot

al

5.59

637E

+00

6.31

400E

+00

1.12

823

7.98

423E

+01

5.89

305E

+00

4.06

088E

+00

002

Ela

stic

5.

5756

2E+0

0 6.

2933

0E+0

0 1.

1287

1 7.

8988

7E+0

1 5.

2419

7E+0

0 2.

2758

9E+0

0 10

2 n,

gam

ma

2.07

557E

-02

2.07

610E

-02

1.00

027

8.53

757E

-01

2.79

986E

-02

1.04

482E

-03

Mat

eria

l(M

AT

)=42

31:M

o-94

001

Tot

al

6.04

323E

+00

6.81

940E

+00

1.12

843

8.84

864E

+01

5.88

853E

+00

4.06

141E

+00

002

Ela

stic

6.

0301

1E+0

0 6.

8062

0E+0

0 1.

1287

1 8.

7250

6E+0

1 4.

8694

4E+0

0 2.

2766

9E+0

0 10

2 n,

gam

ma

1.31

124E

-02

1.31

150E

-02

1.00

021

1.23

582E

+00

3.56

549E

-02

1.00

786E

-03

Mat

eria

l(M

AT

)=42

34:M

o-95

001

Tot

al

1.99

816E

+01

2.08

020E

+01

1.04

103

3.12

353E

+02

5.89

045E

+00

4.36

250E

+00

002

Ela

stic

6.

4138

6E+0

0 7.

2367

0E+0

0 1.

1282

9 2.

0175

3E+0

2 4.

5178

1E+0

0 2.

8429

4E+0

0 10

2 n,

gam

ma

1.35

678E

+01

1.35

650E

+01

0.99

978

1.10

600E

+02

4.80

498E

-02

1.40

815E

-03

Mat

eria

l(M

AT

)=42

37:M

o-96

001

Tot

al

5.34

722E

+00

5.95

890E

+00

1.11

440

1.62

142E

+02

5.88

934E

+00

4.06

777E

+00

002

Ela

stic

4.

7517

1E+0

0 5.

3632

0E+0

0 1.

1286

8 1.

4474

4E+0

2 4.

7439

2E+0

0 2.

2884

0E+0

0 10

2 n,

gam

ma

5.95

512E

-01

5.95

750E

-01

1.00

040

1.73

980E

+01

2.77

164E

-02

1.00

993E

-03

Mat

eria

l(M

AT

)=42

40:M

o-97

001

Tot

al

7.98

732E

+00

8.74

280E

+00

1.09

458

1.05

408E

+02

5.88

976E

+00

4.06

094E

+00

002

Ela

stic

5.

8870

1E+0

0 6.

6444

0E+0

0 1.

1286

5 8.

8551

3E+0

1 4.

3487

5E+0

0 2.

2743

4E+0

0 10

2 n,

gam

ma

2.10

031E

+00

2.09

840E

+00

0.99

909

1.68

566E

+01

4.27

044E

-02

1.00

104E

-03

Mat

eria

l(M

AT

)=42

43:M

o-98

001

Tot

al

5.80

088E

+00

6.53

090E

+00

1.12

584

1.01

793E

+02

5.88

452E

+00

4.06

868E

+00

002

Ela

stic

5.

6708

8E+0

0 6.

4008

0E+0

0 1.

1287

1 9.

5374

2E+0

1 4.

7250

1E+0

0 2.

2945

2E+0

0 10

2 n,

gam

ma

1.29

997E

-01

1.30

090E

-01

1.00

075

6.41

857E

+00

2.68

333E

-02

1.01

157E

-03

Mat

eria

l(M

AT

)=42

46:M

o-99

001

Tot

al

1.37

293E

+01

1.44

790E

+01

1.05

462

1.41

503E

+02

5.72

682E

+00

4.32

713E

+00

002

Ela

stic

5.

7290

5E+0

0 6.

4769

0E+0

0 1.

1305

3 1.

0010

8E+0

2 4.

0161

9E+0

0 2.

8187

5E+0

0 10

2 n,

gam

ma

8.00

027E

+00

8.00

240E

+00

1.00

026

4.13

948E

+01

3.54

163E

-02

1.00

065E

-03

Mat

eria

l(M

AT

)=42

49:M

o-10

0

001

Tot

al

5.52

608E

+00

6.21

170E

+00

1.12

407

1.00

774E

+02

5.88

707E

+00

4.07

231E

+00

002

Ela

stic

5.

3270

3E+0

0 6.

0126

0E+0

0 1.

1287

0 9.

6983

4E+0

1 4.

5626

3E+0

0 2.

2335

7E+0

0 10

2 n,

gam

ma

1.99

057E

-01

1.99

090E

-01

1.00

019

3.79

090E

+00

2.12

326E

-02

1.00

826E

-03

Mat

eria

l(M

AT

)=43

31:T

c-99

001

Tot

al

2.81

477E

+01

2.89

020E

+01

1.02

679

4.16

632E

+02

5.92

070E

+00

4.20

027E

+00

002

Ela

stic

5.

3255

8E+0

0 6.

0070

0E+0

0 1.

1279

6 9.

3801

6E+0

1 4.

1617

7E+0

0 2.

2483

6E+0

0 10

2 n,

gam

ma

2.28

221E

+01

2.28

950E

+01

1.00

319

3.22

830E

+02

8.86

188E

-02

1.33

780E

-03

99

Page 100: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=44

25:R

u-96

001

Tot

al

6.32

602E

+00

7.20

630E

+00

1.13

915

1.23

624E

+02

5.92

249E

+00

6.87

140E

+00

002

Ela

stic

6.

0774

5E+0

0 6.

9573

0E+0

0 1.

1447

8 1.

1139

9E+0

2 4.

7821

7E+0

0 4.

8920

4E+0

0 10

2 n,

gam

ma

2.48

575E

-01

2.48

920E

-01

1.00

137

1.22

245E

+01

1.42

408E

-01

1.40

000E

-03

Mat

eria

l(M

AT

)=44

31:R

u-98

001

Tot

al

1.41

701E

+01

1.57

600E

+01

1.11

221

1.23

164E

+02

5.95

393E

+00

6.58

240E

+00

002

Ela

stic

6.

2145

9E+0

0 7.

7878

0E+0

0 1.

2531

6 1.

1136

8E+0

2 4.

8725

0E+0

0 4.

9064

3E+0

0 10

2 n,

gam

ma

7.95

549E

+00

7.97

220E

+00

1.00

210

1.17

966E

+01

2.61

225E

-02

2.38

001E

-03

Mat

eria

l(M

AT

)=44

34:R

u-99

001

Tot

al

1.20

752E

+01

1.27

300E

+01

1.05

427

2.50

073E

+02

5.43

102E

+00

4.32

872E

+00

002

Ela

stic

4.

9730

3E+0

0 5.

6122

0E+0

0 1.

1285

3 8.

7675

4E+0

1 4.

0063

3E+0

0 3.

0382

5E+0

0 10

2 n,

gam

ma

7.10

217E

+00

7.11

830E

+00

1.00

227

1.62

395E

+02

6.18

145E

-02

2.51

477E

-03

Mat

eria

l(M

AT

)=44

37:R

u-10

0

001

Tot

al

9.73

363E

+00

1.02

410E

+01

1.05

218

7.92

562E

+01

5.45

025E

+00

4.34

760E

+00

002

Ela

stic

3.

9334

6E+0

0 4.

4397

0E+0

0 1.

1287

1 7.

1340

7E+0

1 4.

5516

8E+0

0 3.

0927

1E+0

0 10

2 n,

gam

ma

5.80

017E

+00

5.80

180E

+00

1.00

027

7.91

550E

+00

5.72

047E

-02

2.52

898E

-03

Mat

eria

l(M

AT

)=44

40:R

u-10

1

001

Tot

al

8.49

337E

+00

9.15

120E

+00

1.07

745

2.00

157E

+02

5.93

843E

+00

4.19

486E

+00

002

Ela

stic

5.

0786

8E+0

0 5.

7319

0E+0

0 1.

1286

2 8.

9532

7E+0

1 4.

0671

1E+0

0 2.

1740

7E+0

0 10

2 n,

gam

ma

3.41

468E

+00

3.41

930E

+00

1.00

136

1.10

625E

+02

6.63

402E

-02

1.00

912E

-03

Mat

eria

l(M

AT

)=44

43:R

u-10

2

001

Tot

al

5.26

876E

+00

5.78

000E

+00

1.09

704

6.60

695E

+01

5.48

814E

+00

4.38

905E

+00

002

Ela

stic

3.

9687

8E+0

0 4.

4796

0E+0

0 1.

1287

2 6.

3120

3E+0

1 4.

5136

1E+0

0 3.

2524

1E+0

0 10

2 n,

gam

ma

1.29

997E

+00

1.30

040E

+00

1.00

034

2.94

918E

+00

5.94

090E

-02

1.58

180E

-03

Mat

eria

l(M

AT

)=44

46:R

u-10

3

001

Tot

al

7.18

727E

+01

7.25

730E

+01

1.00

975

6.89

172E

+02

5.83

095E

+00

4.34

622E

+00

002

Ela

stic

5.

0462

9E+0

0 5.

6846

0E+0

0 1.

1264

9 9.

4264

9E+0

1 3.

6674

2E+0

0 2.

4514

1E+0

0 10

2 n,

gam

ma

6.68

264E

+01

6.68

890E

+01

1.00

093

5.93

666E

+02

1.44

340E

-01

2.12

022E

-03

Mat

eria

l(M

AT

)=44

49:R

u-10

4

001

Tot

al

8.42

116E

+00

9.46

690E

+00

1.12

418

1.06

903E

+02

5.51

583E

+00

4.43

238E

+00

002

Ela

stic

8.

1239

3E+0

0 9.

1696

0E+0

0 1.

1287

1 1.

0125

9E+0

2 4.

6315

3E+0

0 3.

1723

6E+0

0 10

2 n,

gam

ma

2.97

232E

-01

2.97

300E

-01

1.00

024

5.64

401E

+00

3.19

619E

-02

9.09

251E

-04

Mat

eria

l(M

AT

)=44

52:R

u-10

5

001

Tot

al

4.28

853E

+00

4.81

490E

+00

1.12

274

7.16

876E

+01

5.50

783E

+00

4.45

482E

+00

002

Ela

stic

4.

0885

2E+0

0 4.

6148

0E+0

0 1.

1287

3 6.

4619

3E+0

1 3.

8992

4E+0

0 3.

0854

9E+0

0 10

2 n,

gam

ma

2.00

007E

-01

2.00

060E

-01

1.00

027

7.06

702E

+00

4.07

980E

-02

2.14

829E

-03

100

Page 101: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=44

55:R

u-10

6

001

Tot

al

4.26

047E

+00

4.79

010E

+00

1.12

432

6.45

412E

+01

5.52

688E

+00

4.47

375E

+00

002

Ela

stic

4.

1144

6E+0

0 4.

6441

0E+0

0 1.

1287

3 6.

2511

5E+0

1 4.

4566

2E+0

0 3.

1128

3E+0

0 10

2 n,

gam

ma

1.46

005E

-01

1.46

040E

-01

1.00

027

2.02

978E

+00

1.12

556E

-02

1.62

707E

-03

Mat

eria

l(M

AT

)=45

25:R

h-10

3

001

Tot

al

1.46

614E

+02

1.50

360E

+02

1.02

553

1.05

330E

+03

5.76

648E

+00

4.30

114E

+00

002

Ela

stic

3.

8841

6E+0

0 4.

3637

0E+0

0 1.

1234

7 8.

4914

1E+0

1 3.

9886

9E+0

0 2.

2630

6E+0

0 10

2 n,

gam

ma

1.42

730E

+02

1.45

990E

+02

1.02

286

9.68

383E

+02

8.48

846E

-02

2.20

335E

-03

Mat

eria

l(M

AT

)=45

31:R

h-10

5

001

Tot

al

1.53

371E

+04

1.24

920E

+04

0.81

447

1.57

628E

+04

5.49

583E

+00

4.45

468E

+00

002

Ela

stic

4.

0885

2E+0

0 4.

6148

0E+0

0 1.

1287

3 7.

0015

9E+0

1 4.

4518

8E+0

0 3.

1380

6E+0

0 10

2 n,

gam

ma

1.53

330E

+04

1.24

870E

+04

0.81

439

1.56

927E

+04

1.19

453E

-01

1.89

058E

-03

Mat

eria

l(M

AT

)=46

25:P

d-10

2

001

Tot

al

9.07

312E

+00

9.80

010E

+00

1.08

012

1.18

784E

+02

6.08

934E

+00

6.91

461E

+00

002

Ela

stic

5.

7083

6E+0

0 6.

4423

0E+0

0 1.

1285

8 1.

0582

9E+0

2 5.

0214

2E+0

0 5.

1878

2E+0

0 10

2 n,

gam

ma

3.36

476E

+00

3.35

770E

+00

0.99

791

1.29

559E

+01

4.72

718E

-02

3.19

001E

-03

Mat

eria

l(M

AT

)=46

31:P

d-10

4

001

Tot

al

4.77

052E

+00

5.34

410E

+00

1.12

023

1.26

663E

+02

5.81

452E

+00

4.31

016E

+00

002

Ela

stic

4.

4554

0E+0

0 5.

0288

0E+0

0 1.

1287

1 1.

1285

1E+0

2 4.

6416

8E+0

0 2.

2120

9E+0

0 10

2 n,

gam

ma

3.15

122E

-01

3.15

230E

-01

1.00

035

1.38

117E

+01

4.61

101E

-02

1.09

600E

-03

Mat

eria

l(M

AT

)=46

34:P

d-10

5

001

Tot

al

2.70

706E

+01

2.76

440E

+01

1.02

117

1.75

282E

+02

5.81

456E

+00

4.41

289E

+00

002

Ela

stic

5.

2451

2E+0

0 5.

9167

0E+0

0 1.

1280

3 8.

2183

5E+0

1 3.

8932

6E+0

0 2.

4928

0E+0

0 10

2 n,

gam

ma

2.18

255E

+01

2.17

270E

+01

0.99

549

9.30

981E

+01

1.35

719E

-01

2.26

276E

-03

Mat

eria

l(M

AT

)=46

37:P

d-10

6

001

Tot

al

4.88

900E

+00

5.47

950E

+00

1.12

078

1.06

946E

+02

5.82

203E

+00

4.32

932E

+00

002

Ela

stic

4.

5885

9E+0

0 5.

1791

0E+0

0 1.

1286

9 1.

0103

3E+0

2 4.

5902

4E+0

0 2.

2412

7E+0

0 10

2 n,

gam

ma

3.00

411E

-01

3.00

390E

-01

0.99

991

5.91

346E

+00

5.45

932E

-02

9.73

198E

-04

Mat

eria

l(M

AT

)=46

40:P

d-10

7

001

Tot

al

6.25

655E

+00

6.83

140E

+00

1.09

187

1.94

711E

+02

5.83

960E

+00

4.34

360E

+00

002

Ela

stic

4.

4513

0E+0

0 5.

0239

0E+0

0 1.

1286

4 8.

9834

1E+0

1 4.

0336

7E+0

0 2.

2559

0E+0

0 10

2 n,

gam

ma

1.80

525E

+00

1.80

750E

+00

1.00

122

1.04

877E

+02

1.20

911E

-01

9.65

398E

-04

Mat

eria

l(M

AT

)=46

43:P

d-10

8

001

Tot

al

1.07

868E

+01

1.12

300E

+01

1.04

109

6.30

731E

+02

5.83

260E

+00

4.35

178E

+00

002

Ela

stic

3.

4306

5E+0

0 3.

8694

0E+0

0 1.

1279

0 4.

5769

3E+0

2 4.

5246

3E+0

0 2.

2703

1E+0

0 10

2 n,

gam

ma

7.35

616E

+00

7.36

060E

+00

1.00

060

1.73

037E

+02

4.29

796E

-02

8.78

498E

-04

101

Page 102: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=46

49:P

d-11

0

001

Tot

al

5.29

551E

+00

5.94

800E

+00

1.12

321

7.13

228E

+01

5.83

264E

+00

4.38

634E

+00

002

Ela

stic

5.

0685

0E+0

0 5.

7209

0E+0

0 1.

1287

1 6.

9035

0E+0

1 4.

4702

7E+0

0 2.

2997

7E+0

0 10

2 n,

gam

ma

2.27

009E

-01

2.27

070E

-01

1.00

027

2.28

776E

+00

2.17

900E

-02

8.99

294E

-04

Mat

eria

l(M

AT

)=47

25:A

g-10

7

001

Tot

al

4.51

804E

+01

4.60

790E

+01

1.01

989

2.10

128E

+02

6.03

096E

+00

4.25

875E

+00

002

Ela

stic

7.

5691

8E+0

0 8.

5349

0E+0

0 1.

1275

9 1.

0319

8E+0

2 4.

3658

9E+0

0 2.

6987

0E+0

0 10

2 n,

gam

ma

3.76

113E

+01

3.75

440E

+01

0.99

821

1.06

930E

+02

1.01

761E

-01

8.78

603E

-07

Mat

eria

l(M

AT

)=47

31:A

g-10

9

001

Tot

al

9.30

482E

+01

9.38

040E

+01

1.00

812

1.69

090E

+03

5.68

305E

+00

4.33

369E

+00

002

Ela

stic

2.

3089

8E+0

0 2.

5969

0E+0

0 1.

1246

8 2.

1641

5E+0

2 3.

9089

7E+0

0 2.

5411

6E+0

0 10

2 n,

gam

ma

9.07

392E

+01

9.12

070E

+01

1.00

515

1.47

448E

+03

1.33

509E

-01

1.01

500E

-03

Mat

eria

l(M

AT

)=47

35:A

g-11

0M

00

1 T

otal

8.

8490

9E+0

1 8.

8379

0E+0

1 0.

9987

4 1.

5620

9E+0

2 5.

5999

9E+0

0 4.

4690

0E+0

0 00

2 E

last

ic

6.49

750E

+00

7.31

770E

+00

1.12

623

6.58

520E

+01

3.83

631E

+00

2.64

754E

+00

102

n,ga

mm

a 8.

1993

4E+0

1 8.

1062

0E+0

1 0.

9886

4 9.

0341

5E+0

1 5.

7899

0E-0

1 1.

0426

6E-0

3

Mat

eria

l(M

AT

)=47

37:A

g-11

1

001

Tot

al

7.24

813E

+00

7.79

810E

+00

1.07

588

1.69

565E

+02

5.53

005E

+00

4.57

077E

+00

002

Ela

stic

4.

2480

2E+0

0 4.

7972

0E+0

0 1.

1292

7 6.

5769

8E+0

1 4.

2177

6E+0

0 3.

3249

4E+0

0 10

2 n,

gam

ma

3.00

011E

+00

3.00

090E

+00

1.00

027

1.03

795E

+02

5.22

261E

-02

1.93

898E

-03

Mat

eria

l(M

AT

)=48

25:C

d-10

6

001

Tot

al

4.72

711E

+00

5.19

150E

+00

1.09

824

9.63

023E

+01

5.80

243E

+00

4.33

052E

+00

002

Ela

stic

3.

6087

8E+0

0 4.

0732

0E+0

0 1.

1286

8 8.

2491

4E+0

1 4.

3795

6E+0

0 2.

4866

6E+0

0 10

2 n,

gam

ma

1.11

833E

+00

1.11

830E

+00

1.00

002

1.38

109E

+01

1.67

909E

-01

6.00

076E

-04

Mat

eria

l(M

AT

)=48

31:C

d-10

8

001

Tot

al

5.16

197E

+00

5.68

460E

+00

1.10

125

1.31

720E

+02

5.84

760E

+00

4.37

039E

+00

002

Ela

stic

4.

0608

6E+0

0 4.

5833

0E+0

0 1.

1286

6 1.

1507

4E+0

2 4.

4156

1E+0

0 2.

5254

4E+0

0 10

2 n,

gam

ma

1.10

111E

+00

1.10

130E

+00

1.00

019

1.66

459E

+01

1.25

051E

-01

6.00

020E

-04

Mat

eria

l(M

AT

)=48

37:C

d-11

0

001

Tot

al

2.93

270E

+01

3.16

800E

+01

1.08

023

2.23

103E

+02

5.86

601E

+00

4.40

867E

+00

002

Ela

stic

1.

8314

6E+0

1 2.

0667

0E+0

1 1.

1284

4 1.

8183

5E+0

2 4.

4658

6E+0

0 2.

5648

9E+0

0 10

2 n,

gam

ma

1.10

124E

+01

1.10

130E

+01

1.00

004

4.12

676E

+01

7.39

418E

-02

6.00

025E

-04

Mat

eria

l(M

AT

)=48

40:C

d-11

1

001

Tot

al

2.86

759E

+01

2.91

310E

+01

1.01

586

1.20

763E

+02

5.89

117E

+00

4.44

297E

+00

002

Ela

stic

4.

6484

9E+0

0 5.

2393

0E+0

0 1.

1270

9 7.

1198

4E+0

1 3.

9838

5E+0

0 2.

6209

4E+0

0 10

2 n,

gam

ma

2.40

274E

+01

2.38

910E

+01

0.99

434

4.95

647E

+01

1.02

943E

-01

6.00

252E

-05

104 102

Page 103: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=48

43:C

d-11

2

001

Tot

al

8.53

545E

+00

9.35

110E

+00

1.09

556

9.53

259E

+01

5.90

564E

+00

4.44

747E

+00

002

Ela

stic

6.

3402

1E+0

0 7.

1557

0E+0

0 1.

1286

2 8.

2191

4E+0

1 4.

4564

9E+0

0 2.

6044

4E+0

0 10

2 n,

gam

ma

2.19

524E

+00

2.19

540E

+00

1.00

007

1.31

346E

+01

7.40

631E

-02

6.00

318E

-05

Mat

eria

l(M

AT

)=48

46:C

d-11

3

001

Tot

al

2.07

451E

+04

2.77

690E

+04

1.33

860

4.93

075E

+02

5.93

147E

+00

4.47

681E

+00

002

Ela

stic

2.

4431

2E+0

1 5.

6909

0E+0

1 2.

3293

6 1.

0146

5E+0

2 4.

1448

4E+0

0 2.

5250

0E+0

0 10

2 n,

gam

ma

2.07

207E

+04

2.77

130E

+04

1.33

744

3.91

610E

+02

5.79

242E

-02

6.00

005E

-04

Mat

eria

l(M

AT

)=48

49:C

d-11

4

001

Tot

al

4.81

643E

+00

5.39

310E

+00

1.11

973

1.17

565E

+02

5.95

002E

+00

4.48

368E

+00

002

Ela

stic

4.

4803

7E+0

0 5.

0569

0E+0

0 1.

1286

9 1.

0459

5E+0

2 4.

4654

1E+0

0 2.

6427

1E+0

0 10

2 n,

gam

ma

3.36

055E

-01

3.36

150E

-01

1.00

029

1.29

701E

+01

3.29

201E

-02

9.99

993E

-04

Mat

eria

l(M

AT

)=48

53:C

d-11

5M

00

1 T

otal

3.

5385

0E+0

1 3.

6023

0E+0

1 1.

0180

4 2.

6716

4E+0

2 5.

5274

1E+0

0 4.

6192

3E+0

0 00

2 E

last

ic

4.38

391E

+00

5.01

360E

+00

1.14

363

7.06

723E

+01

4.58

814E

+00

3.10

513E

+00

102

n,ga

mm

a 3.

1001

1E+0

1 3.

1010

0E+0

1 1.

0002

7 1.

9649

1E+0

2 4.

6814

3E-0

2 2.

3988

5E-0

3

Mat

eria

l(M

AT

)=48

55:C

d-11

6

001

Tot

al

5.90

629E

+00

6.65

680E

+00

1.12

707

7.82

829E

+01

5.98

643E

+00

4.51

997E

+00

002

Ela

stic

5.

8313

1E+0

0 6.

5818

0E+0

0 1.

1287

1 7.

6708

1E+0

1 4.

5032

4E+0

0 2.

6819

7E+0

0 10

2 n,

gam

ma

7.49

863E

-02

7.50

030E

-02

1.00

022

1.57

494E

+00

1.72

456E

-02

6.00

042E

-05

Mat

eria

l(M

AT

)=49

25:I

n-11

3

001

Tot

al

1.57

690E

+01

1.63

940E

+01

1.03

963

4.08

641E

+02

5.53

705E

+00

4.62

764E

+00

002

Ela

stic

3.

6953

8E+0

0 4.

1675

0E+0

0 1.

1277

7 8.

4400

1E+0

1 4.

4519

7E+0

0 2.

4987

0E+0

0 10

2 n,

gam

ma

1.20

736E

+01

1.22

260E

+01

1.01

265

3.24

241E

+02

2.00

994E

-01

1.00

552E

-03

Mat

eria

l(M

AT

)=49

31:I

n-11

5

001

Tot

al

2.03

651E

+02

2.07

860E

+02

1.02

065

3.40

638E

+03

5.53

556E

+00

4.63

543E

+00

002

Ela

stic

2.

5364

2E+0

0 2.

8381

0E+0

0 1.

1189

2 1.

9664

7E+0

2 4.

4472

2E+0

0 2.

9420

1E+0

0 10

2 n,

gam

ma

2.01

114E

+02

2.05

020E

+02

1.01

941

3.20

974E

+03

1.62

835E

-01

1.02

122E

-03

Mat

eria

l(M

AT

)=50

25:S

n-11

2

001

Tot

al

5.61

792E

+00

6.21

080E

+00

1.10

553

1.13

334E

+02

5.53

681E

+00

4.63

999E

+00

002

Ela

stic

4.

6087

6E+0

0 5.

2019

0E+0

0 1.

1286

9 8.

3262

9E+0

1 4.

7851

0E+0

0 2.

9303

3E+0

0 10

2 n,

gam

ma

1.00

915E

+00

1.00

890E

+00

0.99

977

3.00

715E

+01

1.09

058E

-01

1.11

473E

-03

Mat

eria

l(M

AT

)=50

31:S

n-11

4

001

Tot

al

4.69

113E

+00

5.27

880E

+00

1.12

528

8.78

257E

+01

5.53

279E

+00

4.63

944E

+00

002

Ela

stic

4.

5658

3E+0

0 5.

1535

0E+0

0 1.

1287

1 8.

1491

9E+0

1 4.

7907

2E+0

0 2.

9137

2E+0

0 10

2 n,

gam

ma

1.25

298E

-01

1.25

340E

-01

1.00

030

6.33

397E

+00

8.94

539E

-02

1.02

469E

-03

103

Page 104: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=50

34:S

n-11

5

001

Tot

al

3.82

588E

+01

3.92

620E

+01

1.02

623

8.93

714E

+01

5.53

896E

+00

4.62

614E

+00

002

Ela

stic

8.

4062

6E+0

0 9.

4769

0E+0

0 1.

1273

6 7.

5977

7E+0

1 4.

3627

8E+0

0 2.

9043

2E+0

0 10

2 n,

gam

ma

2.98

525E

+01

2.97

850E

+01

0.99

775

1.33

936E

+01

8.06

733E

-02

1.00

708E

-03

Mat

eria

l(M

AT

)=50

37:S

n-11

6

001

Tot

al

4.45

806E

+00

5.01

540E

+00

1.12

502

9.56

221E

+01

5.53

888E

+00

4.63

939E

+00

002

Ela

stic

4.

3303

3E+0

0 4.

8876

0E+0

0 1.

1287

0 8.

3453

7E+0

1 4.

8048

7E+0

0 2.

9209

7E+0

0 10

2 n,

gam

ma

1.27

727E

-01

1.27

780E

-01

1.00

042

1.21

684E

+01

5.61

089E

-02

1.01

422E

-03

Mat

eria

l(M

AT

)=50

40:S

n-11

7

001

Tot

al

7.29

946E

+00

7.95

850E

+00

1.09

028

8.63

472E

+01

5.53

961E

+00

4.63

577E

+00

002

Ela

stic

5.

1259

9E+0

0 5.

7850

0E+0

0 1.

1285

7 6.

8483

1E+0

1 4.

2321

1E+0

0 2.

9214

2E+0

0 10

2 n,

gam

ma

2.17

347E

+00

2.17

350E

+00

1.00

000

1.78

641E

+01

5.46

134E

-02

1.00

649E

-03

Mat

eria

l(M

AT

)=50

43:S

n-11

8

001

Tot

al

4.45

761E

+00

5.00

330E

+00

1.12

243

7.95

210E

+01

5.53

118E

+00

4.63

893E

+00

002

Ela

stic

4.

2397

4E+0

0 4.

7854

0E+0

0 1.

1287

1 7.

4308

3E+0

1 4.

7976

0E+0

0 2.

9281

5E+0

0 10

2 n,

gam

ma

2.17

871E

-01

2.17

890E

-01

1.00

009

5.21

280E

+00

3.19

105E

-02

1.00

205E

-03

Mat

eria

l(M

AT

)=50

46:S

n-11

9

001

Tot

al

6.87

177E

+00

7.47

070E

+00

1.08

716

7.30

315E

+01

5.53

652E

+00

4.62

728E

+00

002

Ela

stic

4.

6954

2E+0

0 5.

2993

0E+0

0 1.

1286

0 6.

7238

0E+0

1 4.

1363

0E+0

0 2.

9198

1E+0

0 10

2 n,

gam

ma

2.17

635E

+00

2.17

150E

+00

0.99

776

5.15

433E

+00

3.45

344E

-02

1.00

439E

-03

Mat

eria

l(M

AT

)=50

49:S

n-12

0

001

Tot

al

5.50

149E

+00

6.19

170E

+00

1.12

547

6.56

693E

+01

5.52

982E

+00

4.63

889E

+00

002

Ela

stic

5.

3622

5E+0

0 6.

0525

0E+0

0 1.

1287

2 6.

4523

8E+0

1 4.

7888

8E+0

0 2.

9280

7E+0

0 10

2 n,

gam

ma

1.39

242E

-01

1.39

260E

-01

1.00

015

1.14

561E

+00

1.78

833E

-02

1.00

503E

-03

Mat

eria

l(M

AT

)=50

55:S

n-12

2

001

Tot

al

3.99

467E

+00

4.48

480E

+00

1.12

270

5.80

979E

+01

5.53

266E

+00

4.63

851E

+00

002

Ela

stic

3.

8109

7E+0

0 4.

3015

0E+0

0 1.

1287

1 5.

7212

1E+0

1 4.

8173

6E+0

0 2.

9298

3E+0

0 10

2 n,

gam

ma

1.83

698E

-01

1.83

330E

-01

0.99

799

8.85

467E

-01

1.03

793E

-02

1.00

590E

-03

Mat

eria

l(M

AT

)=50

58:S

n-12

3

001

Tot

al

4.57

959E

+00

5.18

280E

+00

1.13

172

7.07

646E

+01

5.59

164E

+00

4.65

191E

+00

002

Ela

stic

4.

5465

9E+0

0 5.

1498

0E+0

0 1.

1326

8 6.

8234

5E+0

1 4.

9554

2E+0

0 3.

5168

2E+0

0 10

2 n,

gam

ma

3.30

011E

-02

3.30

100E

-02

1.00

027

2.52

952E

+00

3.90

166E

-02

2.38

770E

-03

Mat

eria

l(M

AT

)=50

61:S

n-12

4

001

Tot

al

4.55

323E

+00

5.12

170E

+00

1.12

485

6.79

956E

+01

5.53

200E

+00

4.63

822E

+00

002

Ela

stic

4.

4177

5E+0

0 4.

9863

0E+0

0 1.

1287

0 6.

0174

0E+0

1 4.

7856

2E+0

0 2.

9290

6E+0

0 10

2 n,

gam

ma

1.35

485E

-01

1.35

390E

-01

0.99

931

7.82

164E

+00

6.34

190E

-03

1.00

510E

-03

104

Page 105: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=50

64:S

n-12

5

001

Tot

al

5.13

944E

+00

5.73

030E

+00

1.11

498

8.70

434E

+01

5.61

205E

+00

4.65

260E

+00

002

Ela

stic

4.

5894

2E+0

0 5.

1802

0E+0

0 1.

1287

2 7.

2212

1E+0

1 5.

0736

6E+0

0 3.

7143

6E+0

0 10

2 n,

gam

ma

5.50

019E

-01

5.50

170E

-01

1.00

027

1.48

307E

+01

1.11

216E

-02

2.27

306E

-03

Mat

eria

l(M

AT

)=50

67:S

n-12

6

001

Tot

al

4.91

338E

+00

5.50

730E

+00

1.12

087

5.95

673E

+01

5.61

668E

+00

4.65

612E

+00

002

Ela

stic

4.

6133

7E+0

0 5.

2072

0E+0

0 1.

1287

1 5.

9407

5E+0

1 5.

1402

7E+0

0 3.

1459

5E+0

0 10

2 n,

gam

ma

3.00

010E

-01

3.00

090E

-01

1.00

027

1.59

773E

-01

5.62

493E

-03

1.81

098E

-03

Mat

eria

l(M

AT

)=51

25:S

b-12

1

001

Tot

al

9.59

805E

+00

1.00

820E

+01

1.05

044

2.82

351E

+02

5.77

910E

+00

4.70

525E

+00

002

Ela

stic

3.

6052

4E+0

0 4.

0679

0E+0

0 1.

1283

3 6.

8449

3E+0

1 4.

3417

8E+0

0 2.

3717

3E+0

0 10

2 n,

gam

ma

5.99

281E

+00

6.01

420E

+00

1.00

358

2.13

663E

+02

8.32

566E

-02

1.00

408E

-03

Mat

eria

l(M

AT

)=51

31:S

b-12

3

001

Tot

al

8.10

223E

+00

8.60

630E

+00

1.06

222

2.18

346E

+02

5.79

676E

+00

4.73

292E

+00

002

Ela

stic

3.

9145

3E+0

0 4.

4174

0E+0

0 1.

1284

5 9.

6258

0E+0

1 4.

5390

8E+0

0 2.

5194

9E+0

0 10

2 n,

gam

ma

4.18

770E

+00

4.18

900E

+00

1.00

030

1.22

088E

+02

6.17

992E

-02

1.00

514E

-03

Mat

eria

l(M

AT

)=51

34:S

b-12

4

001

Tot

al

1.10

748E

+01

1.16

830E

+01

1.05

490

8.77

617E

+01

5.60

579E

+00

4.65

832E

+00

002

Ela

stic

4.

5745

3E+0

0 5.

1807

0E+0

0 1.

1325

2 6.

1427

8E+0

1 3.

8809

7E+0

0 3.

1107

9E+0

0 10

2 n,

gam

ma

6.50

022E

+00

6.50

200E

+00

1.00

027

2.59

782E

+01

5.99

563E

-02

2.50

741E

-03

Mat

eria

l(M

AT

)=51

37:S

b-12

5

001

Tot

al

5.58

945E

+00

6.18

080E

+00

1.10

579

9.97

985E

+01

5.62

480E

+00

4.65

900E

+00

002

Ela

stic

4.

5894

2E+0

0 5.

1805

0E+0

0 1.

1287

9 8.

1744

5E+0

1 4.

6227

4E+0

0 3.

1407

2E+0

0 10

2 n,

gam

ma

1.00

003E

+00

1.00

030E

+00

1.00

027

1.80

541E

+01

7.80

453E

-02

2.01

261E

-03

Mat

eria

l(M

AT

)=51

40:S

b-12

6

001

Tot

al

1.04

288E

+01

1.10

440E

+01

1.05

899

1.29

683E

+02

5.62

322E

+00

4.65

719E

+00

002

Ela

stic

4.

6286

5E+0

0 5.

2423

0E+0

0 1.

1325

8 8.

4040

1E+0

1 4.

5735

6E+0

0 3.

2217

7E+0

0 10

2 n,

gam

ma

5.80

020E

+00

5.80

180E

+00

1.00

027

4.55

309E

+01

3.80

566E

-02

2.37

553E

-03

Mat

eria

l(M

AT

)=52

25:T

e-12

0

001

Tot

al

7.17

874E

+00

8.19

280E

+00

1.14

126

1.13

139E

+02

6.37

980E

+00

7.52

705E

+00

002

Ela

stic

4.

8923

1E+0

0 5.

9055

0E+0

0 1.

2071

0 9.

3761

2E+0

1 5.

0794

6E+0

0 5.

7255

7E+0

0 10

2 n,

gam

ma

2.28

643E

+00

2.28

730E

+00

1.00

036

1.93

774E

+01

1.41

316E

-01

1.40

000E

-03

Mat

eria

l(M

AT

)=52

31:T

e-12

2

001

Tot

al

5.87

157E

+00

6.26

810E

+00

1.06

754

1.88

297E

+02

5.58

529E

+00

4.64

921E

+00

002

Ela

stic

3.

0704

6E+0

0 3.

4655

0E+0

0 1.

1286

4 1.

1474

2E+0

2 4.

6264

3E+0

0 3.

1570

9E+0

0 10

2 n,

gam

ma

2.80

110E

+00

2.80

270E

+00

1.00

057

7.35

552E

+01

1.23

053E

-01

2.26

881E

-03

105

Page 106: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=52

34:T

e-12

3

001

Tot

al

4.10

594E

+02

4.15

520E

+02

1.01

200

6.19

940E

+03

5.59

430E

+00

4.65

302E

+00

002

Ela

stic

5.

9973

4E-0

1 6.

9763

0E-0

1 1.

1632

3 6.

5439

3E+0

2 4.

2105

6E+0

0 3.

1153

5E+0

0 10

2 n,

gam

ma

4.09

994E

+02

4.14

820E

+02

1.01

177

5.54

502E

+03

8.69

948E

-02

2.77

100E

-03

Mat

eria

l(M

AT

)=52

37:T

e-12

4

001

Tot

al

1.06

573E

+01

1.11

560E

+01

1.04

676

7.81

580E

+01

5.60

728E

+00

4.65

583E

+00

002

Ela

stic

3.

8572

1E+0

0 4.

3537

0E+0

0 1.

1287

1 7.

0228

5E+0

1 4.

6532

5E+0

0 3.

2307

8E+0

0 10

2 n,

gam

ma

6.80

014E

+00

6.80

200E

+00

1.00

027

7.92

969E

+00

1.09

897E

-01

2.16

671E

-03

Mat

eria

l(M

AT

)=52

40:T

e-12

5

001

Tot

al

5.54

761E

+00

6.06

260E

+00

1.09

283

1.01

451E

+02

5.62

152E

+00

4.65

885E

+00

002

Ela

stic

3.

9974

3E+0

0 4.

5119

0E+0

0 1.

1287

0 7.

8255

3E+0

1 4.

1983

9E+0

0 3.

1571

5E+0

0 10

2 n,

gam

ma

1.55

018E

+00

1.55

070E

+00

1.00

033

2.29

080E

+01

4.30

885E

-02

2.65

827E

-03

Mat

eria

l(M

AT

)=52

43:T

e-12

6

001

Tot

al

5.16

884E

+00

5.70

120E

+00

1.10

299

9.07

430E

+01

5.63

152E

+00

4.65

544E

+00

002

Ela

stic

4.

1337

4E+0

0 4.

6658

0E+0

0 1.

1287

1 8.

0551

5E+0

1 4.

7199

0E+0

0 3.

1576

4E+0

0 10

2 n,

gam

ma

1.03

511E

+00

1.03

540E

+00

1.00

030

1.01

916E

+01

3.94

435E

-02

2.07

803E

-03

Mat

eria

l(M

AT

)=52

47:T

e-12

7M

00

1 T

otal

1.

4038

6E+0

1 1.

4638

0E+0

1 1.

0427

1 1.

3727

1E+0

2 5.

6333

8E+0

0 4.

6603

4E+0

0 00

2 E

last

ic

4.63

832E

+00

5.23

540E

+00

1.12

872

9.50

185E

+01

4.75

448E

+00

3.14

254E

+00

102

n,ga

mm

a 9.

4003

2E+0

0 9.

4029

0E+0

0 1.

0002

7 4.

2252

8E+0

1 6.

6268

9E-0

2 2.

5264

2E-0

3

Mat

eria

l(M

AT

)=52

49:T

e-12

8

001

Tot

al

4.08

658E

+00

4.58

500E

+00

1.12

196

5.52

733E

+01

5.88

803E

+00

4.82

995E

+00

002

Ela

stic

3.

8716

5E+0

0 4.

3700

0E+0

0 1.

1287

2 5.

3567

9E+0

1 4.

9183

7E+0

0 2.

8747

8E+0

0 10

2 n,

gam

ma

2.14

933E

-01

2.14

990E

-01

1.00

028

1.70

540E

+00

9.29

373E

-03

7.82

185E

-06

Mat

eria

l(M

AT

)=52

53:T

e-12

9M

00

1 T

otal

5.

7862

6E+0

0 6.

3900

0E+0

0 1.

1043

4 9.

5912

1E+0

1 5.

6646

5E+0

0 4.

6576

8E+0

0 00

2 E

last

ic

4.68

623E

+00

5.28

970E

+00

1.12

877

8.99

261E

+01

4.71

901E

+00

3.12

917E

+00

102

n,ga

mm

a 1.

1000

4E+0

0 1.

1003

0E+0

0 1.

0002

7 5.

9860

9E+0

0 1.

3425

4E-0

2 2.

4321

7E-0

3

Mat

eria

l(M

AT

)=52

55:T

e-13

0

001

Tot

al

4.93

680E

+00

5.53

510E

+00

1.12

119

5.90

384E

+01

5.69

073E

+00

4.65

728E

+00

002

Ela

stic

4.

6467

9E+0

0 5.

2450

0E+0

0 1.

1287

3 5.

8702

1E+0

1 4.

9347

9E+0

0 3.

1478

1E+0

0 10

2 n,

gam

ma

2.90

012E

-01

2.90

090E

-01

1.00

028

3.36

403E

-01

4.48

075E

-03

1.95

092E

-03

Mat

eria

l(M

AT

)=52

61:T

e-13

2

001

Tot

al

4.76

009E

+00

5.37

260E

+00

1.12

868

5.78

688E

+01

5.70

793E

+00

4.65

681E

+00

002

Ela

stic

4.

7580

9E+0

0 5.

3706

0E+0

0 1.

1287

4 5.

7867

9E+0

1 4.

9757

7E+0

0 3.

1962

9E+0

0 10

2 n,

gam

ma

2.00

007E

-03

2.00

060E

-03

1.00

028

8.99

657E

-04

6.36

469E

-04

1.90

163E

-03

106

Page 107: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=53

25:I

-127

001

Tot

al

8.94

822E

+00

9.35

370E

+00

1.04

531

2.58

412E

+02

5.89

173E

+00

4.72

889E

+00

002

Ela

stic

3.

1480

0E+0

0 3.

5520

0E+0

0 1.

1283

5 1.

0502

6E+0

2 4.

3496

2E+0

0 2.

5403

4E+0

0 10

2 n,

gam

ma

5.80

022E

+00

5.80

160E

+00

1.00

024

1.53

326E

+02

7.27

073E

-02

1.56

014E

-03

Mat

eria

l(M

AT

)=53

31:I

-129

001

Tot

al

3.69

180E

+01

3.74

860E

+01

1.01

539

1.02

265E

+02

5.86

811E

+00

4.73

354E

+00

002

Ela

stic

4.

3889

5E+0

0 4.

9537

0E+0

0 1.

1286

7 6.

8494

0E+0

1 4.

5256

8E+0

0 2.

5466

0E+0

0 10

2 n,

gam

ma

3.25

291E

+01

3.25

330E

+01

1.00

011

3.35

656E

+01

4.46

819E

-02

1.35

268E

-03

Mat

eria

l(M

AT

)=53

34:I

-130

001

Tot

al

2.27

318E

+01

2.33

730E

+01

1.02

819

3.00

436E

+02

5.69

450E

+00

4.65

731E

+00

002

Ela

stic

4.

7312

2E+0

0 5.

3671

0E+0

0 1.

1344

0 1.

2008

4E+0

2 4.

1531

4E+0

0 3.

1286

2E+0

0 10

2 n,

gam

ma

1.80

006E

+01

1.80

060E

+01

1.00

027

1.80

314E

+02

3.37

972E

-02

2.51

133E

-03

Mat

eria

l(M

AT

)=53

37:I

-131

001

Tot

al

5.43

416E

+00

6.04

400E

+00

1.11

223

1.03

201E

+02

5.71

537E

+00

4.65

677E

+00

002

Ela

stic

4.

7341

3E+0

0 5.

3438

0E+0

0 1.

1287

8 9.

5288

1E+0

1 4.

5531

4E+0

0 3.

1433

6E+0

0 10

2 n,

gam

ma

7.00

024E

-01

7.00

220E

-01

1.00

027

7.91

291E

+00

1.32

668E

-02

2.10

204E

-03

Mat

eria

l(M

AT

)=53

49:I

-135

001

Tot

al

4.84

995E

+00

5.47

160E

+00

1.12

818

6.31

293E

+01

5.77

496E

+00

4.65

687E

+00

002

Ela

stic

4.

8299

5E+0

0 5.

4516

0E+0

0 1.

1287

1 6.

3117

2E+0

1 5.

2967

0E+0

0 3.

2456

7E+0

0 10

2 n,

gam

ma

2.00

007E

-02

2.00

060E

-02

1.00

028

1.20

092E

-02

4.67

003E

-04

1.63

037E

-03

Mat

eria

l(M

AT

)=54

25:X

e-12

4

001

Tot

al

1.68

867E

+02

1.70

050E

+02

1.00

703

3.81

479E

+03

5.87

956E

+00

4.80

510E

+00

002

Ela

stic

4.

3171

9E+0

0 4.

8672

0E+0

0 1.

1274

1 7.

6108

5E+0

2 4.

3998

5E+0

0 3.

0958

1E+0

0 10

2 n,

gam

ma

1.64

549E

+02

1.65

190E

+02

1.00

387

3.05

370E

+03

1.06

822E

-01

0.00

000E

+00

Mat

eria

l(M

AT

)=54

31:X

e-12

6

001

Tot

al

6.52

843E

+00

7.08

520E

+00

1.08

528

1.85

649E

+02

5.90

447E

+00

4.84

850E

+00

002

Ela

stic

4.

3280

0E+0

0 4.

8845

0E+0

0 1.

1285

9 1.

4184

7E+0

2 4.

5143

5E+0

0 2.

8429

8E+0

0 10

2 n,

gam

ma

2.20

042E

+00

2.20

060E

+00

1.00

009

4.38

015E

+01

7.26

523E

-02

0.00

000E

+00

Mat

eria

l(M

AT

)=54

37:X

e-12

8

001

Tot

al

9.67

778E

+00

1.02

210E

+01

1.05

610

1.29

311E

+02

5.93

538E

+00

4.88

760E

+00

002

Ela

stic

4.

3168

7E+0

0 4.

8713

0E+0

0 1.

1284

3 1.

1833

4E+0

2 4.

5419

1E+0

0 2.

6550

3E+0

0 10

2 n,

gam

ma

5.36

091E

+00

5.34

940E

+00

0.99

786

1.09

762E

+01

4.93

088E

-02

0.00

000E

+00

Mat

eria

l(M

AT

)=54

40:X

e-12

9

001

Tot

al

2.23

205E

+01

2.28

880E

+01

1.02

541

3.90

332E

+02

5.94

671E

+00

4.90

550E

+00

002

Ela

stic

4.

3166

2E+0

0 4.

8687

0E+0

0 1.

1279

0 1.

3467

2E+0

2 4.

1312

5E+0

0 2.

9249

5E+0

0 10

2 n,

gam

ma

1.80

039E

+01

1.80

190E

+01

1.00

084

2.55

221E

+02

6.54

917E

-02

0.00

000E

+00

107

Page 108: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=54

43:X

e-13

0

001

Tot

al

1.04

985E

+01

1.10

370E

+01

1.05

125

8.51

622E

+01

5.97

361E

+00

4.90

941E

+00

002

Ela

stic

4.

2976

7E+0

0 4.

8495

0E+0

0 1.

1284

0 8.

0863

0E+0

1 4.

6261

0E+0

0 2.

9401

7E+0

0 10

2 n,

gam

ma

6.20

080E

+00

6.18

700E

+00

0.99

778

4.29

919E

+00

4.04

340E

-02

0.00

000E

+00

Mat

eria

l(M

AT

)=54

46:X

e-13

1

001

Tot

al

1.09

431E

+02

1.12

710E

+02

1.02

994

2.96

005E

+03

5.99

052E

+00

4.93

780E

+00

002

Ela

stic

2.

4434

0E+0

1 2.

7579

0E+0

1 1.

1287

3 2.

0692

5E+0

3 4.

1723

1E+0

0 2.

9490

1E+0

0 10

2 n,

gam

ma

8.49

965E

+01

8.51

270E

+01

1.00

154

8.90

777E

+02

2.58

103E

-02

1.00

010E

-08

Mat

eria

l(M

AT

)=54

49:X

e-13

2

001

Tot

al

4.21

487E

+00

4.69

960E

+00

1.11

500

8.99

479E

+01

6.02

482E

+00

4.94

166E

+00

002

Ela

stic

3.

7661

8E+0

0 4.

2508

0E+0

0 1.

1286

9 8.

8460

2E+0

1 4.

7697

6E+0

0 2.

9737

3E+0

0 10

2 n,

gam

ma

4.48

690E

-01

4.48

740E

-01

1.00

011

1.48

772E

+00

2.27

543E

-02

1.00

000E

-08

Mat

eria

l(M

AT

)=54

52:X

e-13

3

001

Tot

al

1.94

976E

+02

1.96

510E

+02

1.00

786

4.55

057E

+02

5.75

415E

+00

4.65

695E

+00

002

Ela

stic

4.

9715

7E+0

0 6.

4668

0E+0

0 1.

3007

6 9.

7857

2E+0

1 4.

6157

2E+0

0 3.

1542

3E+0

0 10

2 n,

gam

ma

1.90

004E

+02

1.90

040E

+02

1.00

020

3.57

200E

+02

9.01

661E

-03

2.53

768E

-03

Mat

eria

l(M

AT

)=54

55:X

e-13

4

001

Tot

al

4.61

203E

+00

5.17

330E

+00

1.12

169

8.58

919E

+01

6.08

424E

+00

4.97

715E

+00

002

Ela

stic

4.

3626

0E+0

0 4.

9241

0E+0

0 1.

1287

0 8.

5323

0E+0

1 4.

9950

2E+0

0 2.

9653

9E+0

0 10

2 n,

gam

ma

2.49

421E

-01

2.49

220E

-01

0.99

921

5.68

949E

-01

1.24

418E

-02

1.00

000E

-08

Mat

eria

l(M

AT

)=54

58:X

e-13

5

001

Tot

al

2.95

223E

+06

3.50

200E

+06

1.18

624

1.28

620E

+04

5.82

116E

+00

4.65

543E

+00

002

Ela

stic

2.

9958

6E+0

5 4.

3322

0E+0

5 1.

4460

6 5.

2104

4E+0

3 5.

0403

1E+0

0 3.

4386

4E+0

0 10

2 n,

gam

ma

2.65

264E

+06

3.06

880E

+06

1.15

689

7.65

162E

+03

7.63

153E

-04

2.37

589E

-03

Mat

eria

l(M

AT

)=54

61:X

e-13

6

001

Tot

al

4.47

647E

+00

5.03

210E

+00

1.12

412

1.06

937E

+02

6.13

927E

+00

4.98

479E

+00

002

Ela

stic

4.

3164

7E+0

0 4.

8720

0E+0

0 1.

1287

1 1.

0681

8E+0

2 5.

3059

8E+0

0 2.

9613

6E+0

0 10

2 n,

gam

ma

1.60

005E

-01

1.60

050E

-01

1.00

027

1.19

365E

-01

1.05

566E

-03

0.00

000E

+00

Mat

eria

l(M

AT

)=55

25:C

s-13

3

001

Tot

al

3.29

728E

+01

3.35

600E

+01

1.01

781

5.34

791E

+02

5.97

643E

+00

4.84

785E

+00

002

Ela

stic

3.

9705

8E+0

0 4.

4773

0E+0

0 1.

1276

1 1.

1395

0E+0

2 4.

1517

1E+0

0 3.

0731

2E+0

0 10

2 n,

gam

ma

2.90

023E

+01

2.90

830E

+01

1.00

278

4.20

812E

+02

6.33

581E

-02

1.49

523E

-03

Mat

eria

l(M

AT

)=55

28:C

s-13

4

001

Tot

al

1.62

111E

+02

1.64

730E

+02

1.01

613

2.19

635E

+02

5.77

371E

+00

4.65

735E

+00

002

Ela

stic

2.

2427

1E+0

1 2.

5255

0E+0

1 1.

1260

7 1.

4012

6E+0

2 3.

9887

5E+0

0 3.

1579

9E+0

0 10

2 n,

gam

ma

1.39

684E

+02

1.39

470E

+02

0.99

848

7.87

740E

+01

3.31

913E

-02

2.70

517E

-03

108

Page 109: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=55

31:C

s-13

5

001

Tot

al

1.40

851E

+01

1.47

300E

+01

1.04

579

1.88

934E

+02

6.01

834E

+00

4.93

401E

+00

002

Ela

stic

5.

0787

9E+0

0 5.

7305

0E+0

0 1.

1283

1 1.

2789

0E+0

2 4.

5421

7E+0

0 2.

8981

1E+0

0 10

2 n,

gam

ma

9.00

631E

+00

8.99

960E

+00

0.99

926

6.10

443E

+01

2.77

431E

-02

9.20

974E

-04

Mat

eria

l(M

AT

)=55

34:C

s-13

6

001

Tot

al

5.21

561E

+00

5.71

990E

+00

1.09

670

2.18

762E

+02

5.82

570E

+00

4.65

802E

+00

002

Ela

stic

3.

9152

5E+0

0 4.

4190

0E+0

0 1.

1286

6 1.

8034

9E+0

2 4.

7631

3E+0

0 3.

1795

5E+0

0 10

2 n,

gam

ma

1.30

036E

+00

1.30

090E

+00

1.00

045

3.84

132E

+01

2.77

777E

-02

2.55

253E

-03

Mat

eria

l(M

AT

)=55

37:C

s-13

7

001

Tot

al

2.65

855E

+00

2.98

250E

+00

1.12

187

8.98

314E

+01

6.06

730E

+00

4.97

952E

+00

002

Ela

stic

2.

5170

9E+0

0 2.

8411

0E+0

0 1.

1287

1 8.

9232

5E+0

1 5.

0732

1E+0

0 2.

9216

5E+0

0 10

2 n,

gam

ma

1.41

456E

-01

1.41

480E

-01

1.00

019

5.99

005E

-01

6.83

079E

-03

8.95

581E

-04

Mat

eria

l(M

AT

)=56

25:B

a-13

0

001

Tot

al

1.44

323E

+01

1.48

380E

+01

1.02

810

4.82

943E

+02

6.23

443E

+00

5.07

875E

+00

002

Ela

stic

3.

1378

4E+0

0 3.

5401

0E+0

0 1.

1282

0 3.

0780

9E+0

2 4.

6415

4E+0

0 2.

6782

9E+0

0 10

2 n,

gam

ma

1.12

944E

+01

1.12

980E

+01

1.00

029

1.75

133E

+02

5.24

792E

-01

1.64

038E

-02

Mat

eria

l(M

AT

)=56

31:B

a-13

2

001

Tot

al

1.03

128E

+01

1.07

450E

+01

1.04

195

9.60

675E

+01

6.23

172E

+00

5.07

830E

+00

002

Ela

stic

3.

3126

1E+0

0 3.

7433

0E+0

0 1.

1300

3 6.

5936

7E+0

1 4.

8649

3E+0

0 2.

7451

1E+0

0 10

2 n,

gam

ma

7.00

023E

+00

7.00

210E

+00

1.00

027

3.01

307E

+01

2.73

084E

-01

3.81

271E

-03

Mat

eria

l(M

AT

)=56

37:B

a-13

4

001

Tot

al

5.44

145E

+00

5.88

400E

+00

1.08

133

1.15

133E

+02

6.24

948E

+00

5.07

826E

+00

002

Ela

stic

3.

4393

3E+0

0 3.

8816

0E+0

0 1.

1286

0 9.

0926

1E+0

1 5.

0641

0E+0

0 2.

7749

6E+0

0 10

2 n,

gam

ma

2.00

213E

+00

2.00

240E

+00

1.00

013

2.42

066E

+01

1.37

749E

-01

1.50

557E

-03

Mat

eria

l(M

AT

)=56

40:B

a-13

5

001

Tot

al

7.60

122E

+00

7.83

470E

+00

1.03

072

2.88

052E

+02

6.23

955E

+00

5.06

948E

+00

002

Ela

stic

1.

8043

9E+0

0 2.

0359

0E+0

0 1.

1283

0 1.

5728

6E+0

2 4.

9694

2E+0

0 2.

9008

8E+0

0 10

2 n,

gam

ma

5.79

684E

+00

5.79

890E

+00

1.00

035

1.30

766E

+02

9.71

956E

-02

1.00

650E

-03

Mat

eria

l(M

AT

)=56

43:B

a-13

6

001

Tot

al

2.97

403E

+00

3.30

530E

+00

1.11

140

5.95

491E

+01

6.24

670E

+00

5.07

790E

+00

002

Ela

stic

2.

5738

8E+0

0 2.

9051

0E+0

0 1.

1286

9 5.

7642

2E+0

1 5.

2953

6E+0

0 2.

8396

6E+0

0 10

2 n,

gam

ma

4.00

153E

-01

4.00

220E

-01

1.00

017

1.90

697E

+00

3.67

517E

-02

1.01

614E

-03

Mat

eria

l(M

AT

)=56

46:B

a-13

7

001

Tot

al

9.01

835E

+00

9.51

460E

+00

1.05

503

7.26

831E

+01

6.24

176E

+00

5.06

345E

+00

002

Ela

stic

3.

8957

9E+0

0 4.

3957

0E+0

0 1.

1283

2 6.

8007

8E+0

1 5.

3768

9E+0

0 2.

8947

3E+0

0 10

2 n,

gam

ma

5.12

256E

+00

5.11

890E

+00

0.99

928

4.67

542E

+00

1.48

479E

-02

1.00

497E

-03

109

Page 110: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=56

49:B

a-13

8

001

Tot

al

5.92

926E

+00

6.64

640E

+00

1.12

094

6.03

901E

+01

6.23

190E

+00

5.07

772E

+00

002

Ela

stic

5.

5701

4E+0

0 6.

2871

0E+0

0 1.

1287

2 6.

0137

1E+0

1 5.

5740

6E+0

0 2.

8889

2E+0

0 10

2 n,

gam

ma

3.59

127E

-01

3.59

220E

-01

1.00

026

2.53

072E

-01

2.97

335E

-03

1.35

041E

-03

Mat

eria

l(M

AT

)=56

55:B

a-14

0

001

Tot

al

3.49

423E

+00

3.73

890E

+00

1.07

003

4.01

657E

+02

6.14

570E

+00

5.03

570E

+00

002

Ela

stic

1.

8995

1E+0

0 2.

1435

0E+0

0 1.

1284

7 3.

8732

6E+0

2 5.

2886

8E+0

0 2.

9390

5E+0

0 10

2 n,

gam

ma

1.59

472E

+00

1.59

540E

+00

1.00

043

1.43

308E

+01

6.54

869E

-03

9.70

605E

-04

Mat

eria

l(M

AT

)=57

25:L

a-13

8

001

Tot

al

7.01

184E

+01

7.18

860E

+01

1.02

521

4.91

670E

+02

6.17

162E

+00

5.04

681E

+00

002

Ela

stic

1.

3023

7E+0

1 1.

4675

0E+0

1 1.

1268

0 1.

2737

8E+0

2 4.

8620

1E+0

0 2.

9053

4E+0

0 10

2 n,

gam

ma

5.70

947E

+01

5.72

110E

+01

1.00

204

3.64

288E

+02

3.44

466E

-02

1.00

535E

-03

Mat

eria

l(M

AT

)=57

28:L

a-13

9

001

Tot

al

1.94

823E

+01

2.08

320E

+01

1.06

925

1.01

627E

+02

6.07

183E

+00

5.04

607E

+00

002

Ela

stic

1.

0549

9E+0

1 1.

1901

0E+0

1 1.

1280

9 8.

9718

6E+0

1 4.

8400

1E+0

0 2.

9660

3E+0

0 10

2 n,

gam

ma

8.93

241E

+00

8.93

040E

+00

0.99

977

1.19

081E

+01

5.47

889E

-03

7.08

895E

-04

Mat

eria

l(M

AT

)=57

31:L

a-14

0

001

Tot

al

7.65

319E

+00

8.29

450E

+00

1.08

380

2.90

795E

+02

5.93

506E

+00

4.67

091E

+00

002

Ela

stic

4.

9531

0E+0

0 5.

5937

0E+0

0 1.

1293

3 2.

2535

3E+0

2 4.

1708

9E+0

0 2.

9961

2E+0

0 10

2 n,

gam

ma

2.70

009E

+00

2.70

080E

+00

1.00

028

6.51

025E

+01

3.37

906E

-02

2.33

503E

-03

Mat

eria

l(M

AT

)=58

37:C

e-14

0

001

Tot

al

3.85

005E

+00

4.27

150E

+00

1.10

945

4.89

394E

+01

5.93

011E

+00

4.66

965E

+00

002

Ela

stic

3.

2754

5E+0

0 3.

6970

0E+0

0 1.

1286

9 4.

8657

7E+0

1 5.

3998

3E+0

0 3.

2294

9E+0

0 10

2 n,

gam

ma

5.74

596E

-01

5.74

480E

-01

0.99

979

2.81

670E

-01

1.47

860E

-02

2.14

120E

-03

Mat

eria

l(M

AT

)=58

40:C

e-14

1

001

Tot

al

3.61

496E

+01

3.65

950E

+01

1.01

233

3.87

723E

+02

6.16

796E

+00

5.05

050E

+00

002

Ela

stic

3.

4121

4E+0

0 3.

8514

0E+0

0 1.

1287

3 2.

2289

0E+0

2 5.

1163

9E+0

0 2.

9369

2E+0

0 10

2 n,

gam

ma

3.27

374E

+01

3.27

440E

+01

1.00

020

1.64

833E

+02

7.77

741E

-02

1.47

177E

-03

Mat

eria

l(M

AT

)=58

43:C

e-14

2

001

Tot

al

4.68

385E

+00

5.17

100E

+00

1.10

401

2.00

383E

+02

6.19

879E

+00

5.06

962E

+00

002

Ela

stic

3.

7833

7E+0

0 4.

2704

0E+0

0 1.

1287

2 1.

9945

2E+0

2 4.

9756

9E+0

0 2.

9435

3E+0

0 10

2 n,

gam

ma

9.00

478E

-01

9.00

650E

-01

1.00

019

9.30

422E

-01

1.73

754E

-02

1.05

978E

-03

Mat

eria

l(M

AT

)=58

46:C

e-14

3

001

Tot

al

1.10

338E

+01

1.17

090E

+01

1.06

119

2.75

137E

+02

6.00

877E

+00

4.67

563E

+00

002

Ela

stic

5.

0336

0E+0

0 5.

7071

0E+0

0 1.

1338

0 2.

3356

4E+0

2 5.

0766

3E+0

0 3.

2408

0E+0

0 10

2 n,

gam

ma

6.00

020E

+00

6.00

180E

+00

1.00

027

4.15

728E

+01

1.28

590E

-02

2.41

014E

-03

113 110

Page 111: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=58

49:C

e-14

4

001

Tot

al

4.53

046E

+00

4.96

850E

+00

1.09

670

2.75

337E

+02

6.29

028E

+00

5.10

378E

+00

002

Ela

stic

3.

4018

6E+0

0 3.

8397

0E+0

0 1.

1287

1 2.

7253

4E+0

2 4.

4603

4E+0

0 2.

9581

0E+0

0 10

2 n,

gam

ma

1.12

860E

+00

1.12

880E

+00

1.00

020

2.80

294E

+00

7.89

206E

-03

9.46

987E

-04

Mat

eria

l(M

AT

)=59

25:P

r-14

1

001

Tot

al

1.40

797E

+01

1.44

060E

+01

1.02

319

2.33

638E

+02

6.11

865E

+00

5.06

028E

+00

002

Ela

stic

2.

5964

9E+0

0 2.

9279

0E+0

0 1.

1276

6 2.

1576

5E+0

2 4.

7156

9E+0

0 2.

9697

4E+0

0 10

2 n,

gam

ma

1.14

832E

+01

1.14

780E

+01

0.99

957

1.78

731E

+01

1.54

860E

-02

2.72

698E

-03

Mat

eria

l(M

AT

)=59

28:P

r-14

2

001

Tot

al

2.50

162E

+01

2.56

930E

+01

1.02

707

4.99

554E

+02

5.98

729E

+00

4.67

107E

+00

002

Ela

stic

5.

0155

5E+0

0 5.

6872

0E+0

0 1.

1339

2 3.

5448

7E+0

2 4.

8166

3E+0

0 3.

2338

3E+0

0 10

2 n,

gam

ma

2.00

007E

+01

2.00

060E

+01

1.00

027

1.45

068E

+02

2.91

781E

-02

2.57

024E

-03

Mat

eria

l(M

AT

)=59

31:P

r-14

3

001

Tot

al

9.40

948E

+01

9.50

000E

+01

1.00

962

5.92

578E

+02

6.02

221E

+00

4.67

591E

+00

002

Ela

stic

5.

0918

0E+0

0 5.

9729

0E+0

0 1.

1730

4 4.

0292

7E+0

2 4.

8259

1E+0

0 3.

5964

6E+0

0 10

2 n,

gam

ma

8.90

030E

+01

8.90

280E

+01

1.00

028

1.89

542E

+02

5.67

475E

-02

2.24

774E

-03

Mat

eria

l(M

AT

)=60

25:N

d-14

2

001

Tot

al

2.71

825E

+01

2.82

520E

+01

1.03

936

8.67

610E

+01

5.98

653E

+00

4.67

566E

+00

002

Ela

stic

8.

5460

8E+0

0 9.

6367

0E+0

0 1.

1276

2 8.

0680

3E+0

1 5.

3906

0E+0

0 3.

2911

5E+0

0 10

2 n,

gam

ma

1.86

364E

+01

1.86

160E

+01

0.99

889

6.08

074E

+00

2.43

200E

-02

2.41

992E

-03

Mat

eria

l(M

AT

)=60

28:N

d-14

3

001

Tot

al

4.22

821E

+02

4.32

060E

+02

1.02

186

7.40

712E

+02

6.33

797E

+00

4.94

350E

+00

002

Ela

stic

8.

6880

5E+0

1 9.

7345

0E+0

1 1.

1204

4 6.

0814

8E+0

2 5.

1721

3E+0

0 2.

7718

8E+0

0 10

2 n,

gam

ma

3.35

941E

+02

3.34

720E

+02

0.99

636

1.32

564E

+02

7.75

738E

-02

1.07

240E

-03

Mat

eria

l(M

AT

)=60

31:N

d-14

4

001

Tot

al

3.84

361E

+00

3.87

670E

+00

1.00

861

6.49

448E

+02

6.30

889E

+00

5.06

023E

+00

002

Ela

stic

2.

6032

5E-0

1 2.

9340

0E-0

1 1.

1270

6 6.

4536

8E+0

2 5.

0595

9E+0

0 2.

9646

1E+0

0 10

2 n,

gam

ma

3.58

329E

+00

3.58

330E

+00

1.00

000

4.07

978E

+00

2.60

662E

-02

9.13

997E

-04

Mat

eria

l(M

AT

)=60

34:N

d-14

5

001

Tot

al

6.01

845E

+01

6.25

000E

+01

1.03

847

7.97

907E

+02

6.33

924E

+00

5.05

685E

+00

002

Ela

stic

1.

8324

2E+0

1 2.

0641

0E+0

1 1.

1264

6 5.

6671

1E+0

2 4.

5789

4E+0

0 2.

9661

9E+0

0 10

2 n,

gam

ma

4.18

603E

+01

4.18

580E

+01

0.99

995

2.31

147E

+02

7.39

299E

-02

1.00

200E

-03

Mat

eria

l(M

AT

)=60

37:N

d-14

6

001

Tot

al

5.78

161E

+00

6.34

460E

+00

1.09

737

1.67

751E

+02

6.36

724E

+00

5.07

162E

+00

002

Ela

stic

4.

3813

7E+0

0 4.

9446

0E+0

0 1.

1285

6 1.

6508

7E+0

2 4.

8572

7E+0

0 2.

9800

0E+0

0 10

2 n,

gam

ma

1.40

023E

+00

1.39

990E

+00

0.99

979

2.66

392E

+00

2.92

585E

-02

8.94

296E

-04

111

Page 112: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=60

40:N

d-14

7

001

Tot

al

5.45

976E

+02

5.56

630E

+02

1.01

951

1.13

767E

+03

6.14

100E

+00

4.69

762E

+00

002

Ela

stic

1.

0602

9E+0

2 1.

1867

0E+0

2 1.

1192

7 5.

3176

9E+0

2 4.

3590

1E+0

0 3.

2737

2E+0

0 10

2 n,

gam

ma

4.39

947E

+02

4.37

950E

+02

0.99

546

6.05

838E

+02

7.11

493E

-02

2.59

846E

-03

Mat

eria

l(M

AT

)=60

43:N

d-14

8

001

Tot

al

3.16

554E

+00

3.25

180E

+00

1.02

724

5.77

600E

+02

6.45

512E

+00

5.24

066E

+00

002

Ela

stic

6.

6514

0E-0

1 7.

5043

0E-0

1 1.

1282

3 5.

5788

6E+0

2 4.

8357

7E+0

0 3.

0860

0E+0

0 10

2 n,

gam

ma

2.50

040E

+00

2.50

130E

+00

1.00

037

1.97

140E

+01

3.57

942E

-02

8.73

797E

-04

Mat

eria

l(M

AT

)=60

49:N

d-15

0

001

Tot

al

5.94

153E

+00

6.55

300E

+00

1.10

292

1.85

212E

+02

6.81

981E

+00

5.24

139E

+00

002

Ela

stic

4.

7546

7E+0

0 5.

3663

0E+0

0 1.

1286

3 1.

6958

9E+0

2 4.

6652

9E+0

0 2.

7225

6E+0

0 10

2 n,

gam

ma

1.18

685E

+00

1.18

670E

+00

0.99

988

1.56

227E

+01

3.15

871E

-02

8.76

310E

-04

Mat

eria

l(M

AT

)=61

49:P

m-1

47

00

1 T

otal

1.

8254

5E+0

2 1.

8202

0E+0

2 0.

9971

1 3.

3067

5E+0

3 6.

4671

2E+0

0 5.

1726

3E+0

0 00

2 E

last

ic

1.96

463E

+00

2.21

570E

+00

1.12

777

1.16

419E

+03

4.51

550E

+00

3.03

016E

+00

102

n,ga

mm

a 1.

8058

1E+0

2 1.

7980

0E+0

2 0.

9956

8 2.

1425

5E+0

3 1.

8772

9E-0

1 9.

5699

7E-0

4

Mat

eria

l(M

AT

)=61

52:P

m-1

48

00

1 T

otal

2.

0052

0E+0

3 2.

0065

0E+0

3 1.

0006

7 4.

0003

3E+0

4 6.

1624

8E+0

0 4.

7023

5E+0

0 00

2 E

last

ic

5.13

441E

+00

5.79

530E

+00

1.12

872

1.44

303E

+02

3.68

168E

+00

3.28

807E

+00

102

n,ga

mm

a 2.

0000

7E+0

3 2.

0007

0E+0

3 1.

0003

4 3.

9859

0E+0

4 6.

2757

7E-0

1 2.

6486

9E-0

3

Mat

eria

l(M

AT

)=61

53:P

m-1

48M

001

Tot

al

1.07

024E

+04

1.58

550E

+04

1.48

142

3.80

209E

+03

6.16

253E

+00

4.70

235E

+00

002

Ela

stic

3.

5704

7E+0

1 7.

1299

0E+0

1 1.

9969

1 1.

5700

3E+0

2 3.

6817

4E+0

0 3.

2880

7E+0

0 10

2 n,

gam

ma

1.06

666E

+04

1.57

830E

+04

1.47

970

3.64

509E

+03

6.27

577E

-01

2.64

869E

-03

Mat

eria

l(M

AT

)=61

55:P

m-1

49

00

1 T

otal

1.

4054

2E+0

3 1.

4076

0E+0

3 1.

0015

6 9.

9799

2E+0

2 6.

1952

3E+0

0 4.

7068

1E+0

0 00

2 E

last

ic

5.37

613E

+00

7.18

760E

+00

1.33

694

2.00

290E

+02

3.96

386E

+00

3.31

971E

+00

102

n,ga

mm

a 1.

4000

5E+0

3 1.

4004

0E+0

3 1.

0002

7 7.

9770

3E+0

2 6.

1284

9E-0

1 2.

2651

8E-0

3

Mat

eria

l(M

AT

)=61

61:P

m-1

51

00

1 T

otal

7.

0550

2E+0

2 7.

0804

0E+0

2 1.

0036

0 2.

1474

3E+0

3 6.

2580

1E+0

0 4.

7170

1E+0

0 00

2 E

last

ic

5.48

119E

+00

7.85

500E

+00

1.43

308

1.38

791E

+02

4.61

059E

+00

3.27

933E

+00

102

n,ga

mm

a 7.

0002

0E+0

2 7.

0019

0E+0

2 1.

0002

4 2.

0086

4E+0

3 1.

9179

3E-0

3 2.

3263

2E-0

3

Mat

eria

l(M

AT

)=62

25:S

m-1

44

00

1 T

otal

5.

4603

0E+0

0 6.

2662

0E+0

0 1.

1475

9 2.

4620

8E+0

2 6.

7553

0E+0

0 7.

8821

0E+0

0 00

2 E

last

ic

4.76

451E

+00

5.57

060E

+00

1.16

919

2.27

331E

+02

5.86

841E

+00

5.99

188E

+00

102

n,ga

mm

a 6.

9579

5E-0

1 6.

9558

0E-0

1 0.

9996

9 1.

8876

9E+0

1 2.

1204

0E-0

1 2.

0700

0E-0

3

112

Page 113: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=62

34:S

m-1

47

00

1 T

otal

9.

7206

7E+0

1 1.

0236

0E+0

2 1.

0530

1 1.

6388

4E+0

3 6.

9284

9E+0

0 5.

0360

7E+0

0 00

2 E

last

ic

4.00

190E

+01

4.51

040E

+01

1.12

707

8.45

200E

+02

4.76

666E

+00

2.95

475E

+00

102

n,ga

mm

a 5.

7187

7E+0

1 5.

7255

0E+0

1 1.

0011

8 7.

9364

1E+0

2 2.

0786

2E-0

1 1.

1960

0E-0

3

Mat

eria

l(M

AT

)=62

37:S

m-1

48

00

1 T

otal

7.

8388

2E+0

0 8.

5042

0E+0

0 1.

0848

9 3.

7192

7E+0

2 6.

1708

0E+0

0 4.

7003

6E+0

0 00

2 E

last

ic

5.13

872E

+00

5.80

340E

+00

1.12

935

3.45

001E

+02

4.92

006E

+00

3.35

836E

+00

102

n,ga

mm

a 2.

7000

9E+0

0 2.

7008

0E+0

0 1.

0002

8 2.

6926

7E+0

1 1.

9458

8E-0

1 2.

4260

6E-0

3

Mat

eria

l(M

AT

)=62

40:S

m-1

49

00

1 T

otal

4.

1931

5E+0

4 7.

2132

0E+0

4 1.

7202

3 4.

0248

3E+0

3 7.

0755

2E+0

0 5.

2006

6E+0

0 00

2 E

last

ic

2.05

356E

+02

4.92

560E

+02

2.39

858

5.38

733E

+02

4.47

441E

+00

3.06

700E

+00

102

n,ga

mm

a 4.

1726

1E+0

4 7.

1639

0E+0

4 1.

7168

9 3.

4857

1E+0

3 1.

9114

1E-0

1 1.

6588

1E-0

3

Mat

eria

l(M

AT

)=62

43:S

m-1

50

00

1 T

otal

1.

2460

2E+0

2 1.

2705

0E+0

2 1.

0196

3 8.

4055

1E+0

2 6.

2317

3E+0

0 4.

7105

8E+0

0 00

2 E

last

ic

2.12

547E

+01

2.39

030E

+01

1.12

460

5.01

624E

+02

4.66

629E

+00

3.35

046E

+00

102

n,ga

mm

a 1.

0334

7E+0

2 1.

0314

0E+0

2 0.

9980

4 3.

3892

8E+0

2 1.

4289

5E-0

1 2.

3340

5E-0

3

Mat

eria

l(M

AT

)=62

46:S

m-1

51

00

1 T

otal

1.

5222

0E+0

4 1.

4114

0E+0

4 0.

9272

4 3.

7661

0E+0

3 6.

7770

6E+0

0 5.

0028

1E+0

0 00

2 E

last

ic

3.92

486E

+01

3.65

600E

+01

0.93

151

2.97

566E

+02

3.81

745E

+00

2.77

746E

+00

102

n,ga

mm

a 1.

5182

8E+0

4 1.

4078

0E+0

4 0.

9272

3 3.

4651

0E+0

3 1.

6779

4E-0

1 1.

6269

0E-0

3

Mat

eria

l(M

AT

)=62

49:S

m-1

52

00

1 T

otal

2.

0894

5E+0

2 2.

1008

0E+0

2 1.

0054

4 9.

0537

8E+0

3 7.

0342

3E+0

0 5.

0146

3E+0

0 00

2 E

last

ic

2.94

540E

+00

3.38

580E

+00

1.14

951

6.07

396E

+03

4.69

268E

+00

2.95

200E

+00

102

n,ga

mm

a 2.

0600

0E+0

2 2.

0670

0E+0

2 1.

0033

8 2.

9798

1E+0

3 9.

1017

7E-0

2 9.

2959

7E-0

4

Mat

eria

l(M

AT

)=62

52:S

m-1

53

00

1 T

otal

3.

3545

9E+0

2 3.

3724

0E+0

2 1.

0053

1 3.

1194

1E+0

3 6.

3113

7E+0

0 4.

7275

6E+0

0 00

2 E

last

ic

5.44

481E

+00

7.11

190E

+00

1.30

618

2.47

906E

+02

4.17

776E

+00

3.28

170E

+00

102

n,ga

mm

a 3.

3001

4E+0

2 3.

3013

0E+0

2 1.

0003

5 2.

8689

2E+0

3 5.

9456

5E-0

4 2.

7852

9E-0

3

Mat

eria

l(M

AT

)=62

55:S

m-1

54

00

1 T

otal

1.

9437

2E+0

1 2.

0853

0E+0

1 1.

0728

3 2.

6925

3E+0

2 6.

3427

9E+0

0 4.

7326

4E+0

0 00

2 E

last

ic

1.10

358E

+01

1.24

530E

+01

1.12

841

2.35

970E

+02

4.73

673E

+00

3.33

461E

+00

102

n,ga

mm

a 8.

4014

1E+0

0 8.

4001

0E+0

0 0.

9998

4 3.

3271

5E+0

1 6.

0107

5E-0

2 2.

3179

1E-0

3

Mat

eria

l(M

AT

)=63

25:E

u-15

1

001

Tot

al

9.16

842E

+03

8.25

860E

+03

0.90

076

3.60

364E

+03

7.03

903E

+00

5.12

993E

+00

002

Ela

stic

3.

3937

4E+0

0 3.

1805

0E+0

0 0.

9371

6 2.

5158

1E+0

2 4.

4506

1E+0

0 2.

8473

8E+0

0 10

2 n,

gam

ma

9.16

502E

+03

8.25

540E

+03

0.90

075

3.35

117E

+03

4.61

639E

-01

1.40

000E

-03

113

Page 114: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=63

28:E

u-15

2

001

Tot

al

1.27

777E

+04

1.18

250E

+04

0.92

544

2.67

100E

+03

6.54

564E

+00

5.05

046E

+00

002

Ela

stic

2.

9085

6E+0

1 2.

9362

0E+0

1 1.

0094

9 5.

0343

3E+0

2 4.

2416

9E+0

0 3.

2812

2E+0

0 10

2 n,

gam

ma

1.27

486E

+04

1.17

960E

+04

0.92

524

2.16

755E

+03

5.27

810E

-01

1.00

593E

-03

Mat

eria

l(M

AT

)=63

31:E

u-15

3

001

Tot

al

3.22

975E

+02

3.20

080E

+02

0.99

102

1.60

556E

+03

6.87

232E

+00

5.21

414E

+00

002

Ela

stic

1.

0362

1E+0

1 1.

1548

0E+0

1 1.

1144

9 1.

9633

2E+0

2 4.

5775

1E+0

0 2.

8793

0E+0

0 10

2 n,

gam

ma

3.12

613E

+02

3.08

530E

+02

0.98

693

1.40

921E

+03

2.63

953E

-01

1.00

476E

-03

Mat

eria

l(M

AT

)=63

34:E

u-15

4

001

Tot

al

1.85

151E

+03

2.20

840E

+03

1.19

273

1.52

618E

+03

6.57

906E

+00

4.96

817E

+00

002

Ela

stic

6.

6462

1E+0

0 7.

4220

0E+0

0 1.

1167

2 1.

6846

0E+0

2 3.

7614

4E+0

0 2.

6103

5E+0

0 10

2 n,

gam

ma

1.84

487E

+03

2.20

090E

+03

1.19

300

1.35

770E

+03

2.21

942E

-01

2.60

257E

-03

Mat

eria

l(M

AT

)=63

37:E

u-15

5

001

Tot

al

3.77

531E

+03

3.87

080E

+03

1.02

530

1.60

405E

+04

6.84

272E

+00

5.39

196E

+00

002

Ela

stic

1.

7676

3E+0

1 2.

0489

0E+0

1 1.

1591

2 7.

5888

2E+0

2 4.

5907

2E+0

0 2.

9933

2E+0

0 10

2 n,

gam

ma

3.75

764E

+03

3.85

040E

+03

1.02

467

1.52

815E

+04

2.02

071E

-01

1.26

829E

-03

Mat

eria

l(M

AT

)=63

40:E

u-15

6

001

Tot

al

4.87

636E

+02

4.90

370E

+02

1.00

561

1.64

423E

+03

6.38

714E

+00

4.74

149E

+00

002

Ela

stic

5.

5932

3E+0

0 7.

9979

0E+0

0 1.

4299

3 1.

5030

4E+0

2 4.

1757

8E+0

0 3.

2812

2E+0

0 10

2 n,

gam

ma

4.82

043E

+02

4.82

380E

+02

1.00

069

1.49

225E

+03

2.02

713E

-03

2.78

996E

-03

Mat

eria

l(M

AT

)=63

43:E

u-15

7

001

Tot

al

1.95

328E

+02

1.95

930E

+02

1.00

310

1.42

875E

+03

6.40

340E

+00

4.74

570E

+00

002

Ela

stic

5.

3390

7E+0

0 6.

0262

0E+0

0 1.

1287

0 1.

2646

4E+0

2 4.

9742

3E+0

0 3.

2767

7E+0

0 10

2 n,

gam

ma

1.89

989E

+02

1.89

910E

+02

0.99

957

1.30

225E

+03

4.35

298E

-03

2.33

843E

-03

Mat

eria

l(M

AT

)=64

25:G

d-15

2

001

Tot

al

1.06

992E

+03

1.06

940E

+03

0.99

949

1.58

152E

+03

7.01

419E

+00

5.68

473E

+00

002

Ela

stic

1.

3962

0E+0

1 1.

5695

0E+0

1 1.

1241

5 5.

9344

4E+0

2 5.

1511

8E+0

0 3.

4019

2E+0

0 10

2 n,

gam

ma

1.05

595E

+03

1.05

370E

+03

0.99

784

9.88

018E

+02

2.94

815E

-01

1.02

599E

-03

Mat

eria

l(M

AT

)=64

31:G

d-15

4

001

Tot

al

8.85

890E

+01

8.90

750E

+01

1.00

549

5.36

009E

+02

6.33

383E

+00

4.73

239E

+00

002

Ela

stic

3.

5850

2E+0

0 4.

0457

0E+0

0 1.

1284

9 2.

8957

6E+0

2 4.

6356

6E+0

0 3.

3610

3E+0

0 10

2 n,

gam

ma

8.50

040E

+01

8.50

300E

+01

1.00

030

2.46

433E

+02

3.07

980E

-01

2.61

100E

-03

Mat

eria

l(M

AT

)=64

34:G

d-15

5

001

Tot

al

6.07

915E

+04

5.13

060E

+04

0.84

396

1.70

604E

+03

6.98

683E

+00

5.68

006E

+00

002

Ela

stic

5.

9025

3E+0

1 5.

7334

0E+0

1 0.

9713

4 1.

6182

2E+0

2 4.

5160

8E+0

0 3.

2425

7E+0

0 10

2 n,

gam

ma

6.07

325E

+04

5.12

480E

+04

0.84

384

1.54

415E

+03

3.48

948E

-01

2.07

595E

-05

114

Page 115: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=64

37:G

d-15

6

001

Tot

al

7.10

870E

+00

7.82

650E

+00

1.10

097

3.08

778E

+02

6.71

988E

+00

5.38

375E

+00

002

Ela

stic

5.

5726

8E+0

0 6.

2894

0E+0

0 1.

1286

1 2.

0856

7E+0

2 4.

7610

7E+0

0 3.

0723

0E+0

0 10

2 n,

gam

ma

1.53

602E

+00

1.53

710E

+00

1.00

071

1.00

206E

+02

1.19

318E

-01

1.77

620E

-03

Mat

eria

l(M

AT

)=64

40:G

d-15

7

001

Tot

al

2.55

015E

+05

2.17

300E

+05

0.85

209

9.44

337E

+02

6.70

060E

+00

5.39

500E

+00

002

Ela

stic

1.

7602

8E+0

3 1.

6026

0E+0

3 0.

9104

2 1.

8205

4E+0

2 4.

4780

3E+0

0 3.

0898

4E+0

0 10

2 n,

gam

ma

2.53

255E

+05

2.15

690E

+05

0.85

169

7.61

984E

+02

2.04

190E

-01

7.61

219E

-05

Mat

eria

l(M

AT

)=64

43:G

d-15

8

001

Tot

al

6.01

037E

+00

6.46

360E

+00

1.07

541

1.95

442E

+02

6.42

782E

+00

4.74

784E

+00

002

Ela

stic

3.

5097

5E+0

0 3.

9612

0E+0

0 1.

1286

2 1.

3264

8E+0

2 4.

8355

9E+0

0 3.

2969

8E+0

0 10

2 n,

gam

ma

2.50

062E

+00

2.50

240E

+00

1.00

072

6.27

807E

+01

5.57

585E

-02

2.88

859E

-03

Mat

eria

l(M

AT

)=64

49:G

d-16

0

001

Tot

al

4.49

666E

+00

4.97

650E

+00

1.10

670

1.65

552E

+02

6.46

297E

+00

4.75

316E

+00

002

Ela

stic

3.

7265

6E+0

0 4.

2061

0E+0

0 1.

1287

0 1.

5731

1E+0

2 4.

8906

7E+0

0 3.

2820

9E+0

0 10

2 n,

gam

ma

7.70

102E

-01

7.70

310E

-01

1.00

027

8.22

007E

+00

8.00

632E

-02

2.34

045E

-03

Mat

eria

l(M

AT

)=65

25:T

b-15

9

001

Tot

al

2.97

831E

+01

3.06

330E

+01

1.02

855

6.06

881E

+02

6.71

619E

+00

5.00

964E

+00

002

Ela

stic

6.

5707

4E+0

0 7.

4164

0E+0

0 1.

1287

1 1.

9368

2E+0

2 4.

0321

6E+0

0 2.

4992

4E+0

0 10

2 n,

gam

ma

2.32

124E

+01

2.32

170E

+01

1.00

019

4.12

930E

+02

1.59

049E

-01

1.77

106E

-03

Mat

eria

l(M

AT

)=65

28:T

b-16

0

001

Tot

al

5.30

385E

+02

5.30

920E

+02

1.00

101

1.31

478E

+03

6.46

066E

+00

4.75

429E

+00

002

Ela

stic

5.

4069

6E+0

0 6.

1029

0E+0

0 1.

1287

1 1.

8009

8E+0

2 4.

3376

5E+0

0 3.

2541

0E+0

0 10

2 n,

gam

ma

5.24

978E

+02

5.24

820E

+02

0.99

969

1.13

468E

+03

4.41

010E

-03

2.92

251E

-03

Mat

eria

l(M

AT

)=66

37:D

y-16

0

001

Tot

al

6.33

488E

+01

6.41

790E

+01

1.01

311

2.31

679E

+03

6.45

683E

+00

4.75

434E

+00

002

Ela

stic

2.

3158

4E+0

0 2.

6032

0E+0

0 1.

1241

1 6.

4065

6E+0

2 4.

6720

0E+0

0 3.

6568

7E+0

0 10

2 n,

gam

ma

6.10

330E

+01

6.15

760E

+01

1.00

889

1.67

613E

+03

7.66

040E

-01

2.67

380E

-03

Mat

eria

l(M

AT

)=66

40:D

y-16

1

001

Tot

al

6.16

906E

+02

6.12

950E

+02

0.99

359

1.24

958E

+03

7.13

719E

+00

5.18

371E

+00

002

Ela

stic

1.

6595

7E+0

1 1.

8468

0E+0

1 1.

1127

9 1.

6227

6E+0

2 5.

3357

7E+0

0 3.

7059

6E+0

0 10

2 n,

gam

ma

6.00

310E

+02

5.94

480E

+02

0.99

030

1.08

681E

+03

1.35

669E

-01

3.08

394E

-03

Mat

eria

l(M

AT

)=66

43:D

y-16

2

001

Tot

al

1.93

849E

+02

1.94

790E

+02

1.00

488

3.51

660E

+03

7.14

106E

+00

5.18

370E

+00

002

Ela

stic

1.

2368

6E-0

2 1.

2476

0E-0

2 1.

0086

6 7.

6887

6E+0

2 5.

7222

2E+0

0 3.

7569

6E+0

0 10

2 n,

gam

ma

1.93

836E

+02

1.94

780E

+02

1.00

488

2.74

771E

+03

7.15

063E

-02

1.33

693E

-03

115

Page 116: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=66

46:D

y-16

3

001

Tot

al

1.27

615E

+02

1.29

430E

+02

1.01

425

1.71

747E

+03

7.13

464E

+00

5.18

371E

+00

002

Ela

stic

3.

3890

5E+0

0 3.

8046

0E+0

0 1.

1226

2 2.

2780

2E+0

2 5.

1433

4E+0

0 3.

6537

6E+0

0 10

2 n,

gam

ma

1.24

226E

+02

1.25

630E

+02

1.01

130

1.48

945E

+03

9.51

243E

-02

2.90

953E

-03

Mat

eria

l(M

AT

)=66

49:D

y-16

4

001

Tot

al

2.97

751E

+03

2.97

920E

+03

1.00

057

8.86

309E

+02

7.22

037E

+00

5.26

036E

+00

002

Ela

stic

3.

2689

9E+0

2 3.

6074

0E+0

2 1.

1035

2 5.

4365

1E+0

2 4.

8804

8E+0

0 3.

0131

6E+0

0 10

2 n,

gam

ma

2.65

061E

+03

2.61

850E

+03

0.98

788

3.42

589E

+02

2.99

838E

-02

1.34

147E

-03

Mat

eria

l(M

AT

)=67

25:H

o-16

5

001

Tot

al

7.22

400E

+01

7.34

850E

+01

1.01

723

9.15

277E

+02

6.88

753E

+00

5.32

534E

+00

002

Ela

stic

8.

7957

8E+0

0 9.

9220

0E+0

0 1.

1280

4 2.

4035

0E+0

2 4.

2377

3E+0

0 2.

8754

4E+0

0 10

2 n,

gam

ma

6.34

442E

+01

6.35

630E

+01

1.00

187

6.74

922E

+02

1.22

018E

-01

1.27

051E

-03

Mat

eria

l(M

AT

)=68

25:E

r-16

2

001

Tot

al

2.69

420E

+01

2.79

900E

+01

1.03

891

6.94

011E

+02

6.74

843E

+00

5.42

452E

+00

002

Ela

stic

8.

0272

2E+0

0 9.

0544

0E+0

0 1.

1279

6 2.

4299

1E+0

2 4.

8070

4E+0

0 2.

6786

0E+0

0 10

2 n,

gam

ma

1.89

148E

+01

1.89

360E

+01

1.00

112

4.51

020E

+02

1.81

869E

-01

1.63

762E

-03

Mat

eria

l(M

AT

)=68

31:E

r-16

4

001

Tot

al

2.20

816E

+01

2.32

510E

+01

1.05

296

3.40

948E

+02

6.78

852E

+00

5.45

805E

+00

002

Ela

stic

9.

1277

9E+0

0 1.

0298

0E+0

1 1.

1282

3 1.

7441

8E+0

2 4.

6745

3E+0

0 2.

7004

8E+0

0 10

2 n,

gam

ma

1.29

538E

+01

1.29

530E

+01

0.99

992

1.66

528E

+02

3.75

123E

-01

1.63

762E

-03

Mat

eria

l(M

AT

)=68

37:E

r-16

6

001

Tot

al

2.92

535E

+01

3.08

500E

+01

1.05

458

3.65

356E

+02

6.82

014E

+00

5.50

210E

+00

002

Ela

stic

1.

2485

8E+0

1 1.

4086

0E+0

1 1.

1281

2 2.

5364

7E+0

2 4.

6535

3E+0

0 2.

7553

2E+0

0 10

2 n,

gam

ma

1.67

677E

+01

1.67

650E

+01

0.99

982

1.11

693E

+02

9.57

374E

-02

1.93

330E

-03

Mat

eria

l(M

AT

)=68

40:E

r-16

7

001

Tot

al

6.44

406E

+02

6.88

930E

+02

1.06

909

3.45

779E

+03

6.83

830E

+00

5.51

464E

+00

002

Ela

stic

1.

3375

8E+0

0 1.

4130

0E+0

0 1.

0563

9 4.

8476

7E+0

2 4.

3261

0E+0

0 2.

7195

9E+0

0 10

2 n,

gam

ma

6.43

069E

+02

6.87

520E

+02

1.06

912

2.97

299E

+03

9.42

873E

-02

1.97

240E

-03

Mat

eria

l(M

AT

)=68

43:E

r-16

8

001

Tot

al

1.17

142E

+01

1.28

700E

+01

1.09

865

2.36

914E

+02

6.85

496E

+00

5.53

530E

+00

002

Ela

stic

8.

9847

6E+0

0 1.

0140

0E+0

1 1.

1285

8 1.

9879

5E+0

2 4.

6798

9E+0

0 2.

7697

5E+0

0 10

2 n,

gam

ma

2.72

949E

+00

2.72

990E

+00

1.00

014

3.81

001E

+01

3.59

995E

-02

1.89

858E

-03

Mat

eria

l(M

AT

)=68

49:E

r-17

0

001

Tot

al

1.77

795E

+01

1.93

240E

+01

1.08

684

6.15

132E

+02

6.81

984E

+00

5.50

199E

+00

002

Ela

stic

1.

2002

4E+0

1 1.

3544

0E+0

1 1.

1284

7 5.

6998

3E+0

2 4.

6089

7E+0

0 2.

7214

9E+0

0 10

2 n,

gam

ma

5.77

708E

+00

5.77

920E

+00

1.00

036

4.51

291E

+01

2.29

469E

-02

1.86

103E

-03

116

Page 117: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=71

25:L

u-17

5

001

Tot

al

2.95

134E

+01

3.03

920E

+01

1.02

976

8.02

165E

+02

7.22

216E

+00

5.25

740E

+00

002

Ela

stic

6.

4359

8E+0

0 7.

2553

0E+0

0 1.

1273

0 1.

8148

6E+0

2 5.

0741

7E+0

0 3.

0207

5E+0

0 10

2 n,

gam

ma

2.30

775E

+01

2.31

360E

+01

1.00

255

6.20

680E

+02

1.63

859E

-01

2.25

000E

-03

Mat

eria

l(M

AT

)=71

28:L

u-17

6

001

Tot

al

2.09

953E

+03

3.59

380E

+03

1.71

170

1.07

081E

+03

7.22

920E

+00

5.26

000E

+00

002

Ela

stic

2.

5152

9E+0

0 4.

2064

0E+0

0 1.

6723

2 1.

5106

3E+0

2 5.

0440

3E+0

0 2.

9525

2E+0

0 10

2 n,

gam

ma

2.09

701E

+03

3.58

960E

+03

1.71

175

9.19

744E

+02

2.05

325E

-01

3.08

394E

-03

Mat

eria

l(M

AT

)=72

25:H

f-17

4

001

Tot

al

5.97

764E

+02

5.95

910E

+02

0.99

690

1.11

876E

+03

7.14

368E

+00

5.32

588E

+00

002

Ela

stic

4.

8119

6E+0

1 5.

3708

0E+0

1 1.

1161

4 6.

7802

7E+0

2 4.

6065

2E+0

0 2.

7415

5E+0

0 10

2 n,

gam

ma

5.49

645E

+02

5.42

200E

+02

0.98

646

4.40

732E

+02

2.76

722E

-01

4.18

124E

-06

Mat

eria

l(M

AT

)=72

31:H

f-17

6

001

Tot

al

2.68

569E

+01

2.76

080E

+01

1.02

798

1.12

105E

+03

7.14

374E

+00

5.36

465E

+00

002

Ela

stic

5.

5294

7E+0

0 6.

2316

0E+0

0 1.

1269

8 4.

2708

4E+0

2 4.

6866

6E+0

0 2.

7509

4E+0

0 10

2 n,

gam

ma

2.13

274E

+01

2.13

770E

+01

1.00

231

6.93

962E

+02

9.37

184E

-02

4.21

718E

-07

Mat

eria

l(M

AT

)=72

34:H

f-17

7

001

Tot

al

3.72

003E

+02

3.79

470E

+02

1.02

006

8.01

142E

+03

7.12

749E

+00

5.37

822E

+00

002

Ela

stic

3.

6152

7E-0

2 4.

3480

0E-0

2 1.

2026

8 7.

9930

4E+0

2 4.

5637

7E+0

0 2.

8840

1E+0

0 10

2 n,

gam

ma

3.71

967E

+02

3.79

420E

+02

1.02

004

7.21

212E

+03

1.63

819E

-01

1.93

670E

-07

Mat

eria

l(M

AT

)=72

37:H

f-17

8

001

Tot

al

9.05

826E

+01

9.16

380E

+01

1.01

165

3.93

222E

+03

7.14

114E

+00

5.50

544E

+00

002

Ela

stic

6.

6257

8E+0

0 7.

4331

0E+0

0 1.

1218

4 2.

0603

3E+0

3 4.

6723

1E+0

0 3.

0796

0E+0

0 10

2 n,

gam

ma

8.39

568E

+01

8.42

050E

+01

1.00

295

1.87

188E

+03

5.55

173E

-02

7.33

680E

-10

Mat

eria

l(M

AT

)=72

40:H

f-17

9

001

Tot

al

4.85

817E

+01

4.94

760E

+01

1.01

841

7.78

365E

+02

7.12

497E

+00

5.40

086E

+00

002

Ela

stic

7.

7944

4E+0

0 8.

7739

0E+0

0 1.

1256

7 2.

7009

3E+0

2 4.

6411

7E+0

0 2.

9361

6E+0

0 10

2 n,

gam

ma

4.07

873E

+01

4.07

020E

+01

0.99

791

5.08

273E

+02

1.05

363E

-01

7.51

594E

-08

Mat

eria

l(M

AT

)=72

43:H

f-18

0

001

Tot

al

3.54

024E

+01

3.82

670E

+01

1.08

091

2.90

435E

+02

7.14

400E

+00

5.47

607E

+00

002

Ela

stic

2.

2304

8E+0

1 2.

5169

0E+0

1 1.

1284

0 2.

6083

9E+0

2 4.

7146

8E+0

0 2.

7955

4E+0

0 10

2 n,

gam

ma

1.30

976E

+01

1.30

980E

+01

1.00

003

2.95

910E

+01

3.28

680E

-02

4.12

239E

-06

Mat

eria

l(M

AT

)=73

28:T

a-18

1

001

Tot

al

2.63

431E

+01

2.71

260E

+01

1.02

973

8.90

488E

+02

6.99

496E

+00

5.35

709E

+00

002

Ela

stic

5.

6659

9E+0

0 6.

3850

0E+0

0 1.

1269

0 2.

2995

7E+0

2 4.

6211

9E+0

0 2.

9781

8E+0

0 10

2 n,

gam

ma

2.06

771E

+01

2.07

410E

+01

1.00

310

6.59

489E

+02

8.74

364E

-02

2.05

527E

-07

117

Page 118: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=73

31:T

a-18

2

001

Tot

al

8.31

941E

+03

1.36

640E

+04

1.64

241

1.32

945E

+03

6.78

987E

+00

5.36

137E

+00

002

Ela

stic

3.

1151

8E+0

1 5.

3993

0E+0

1 1.

7332

1 2.

8634

8E+0

2 3.

7692

1E+0

0 2.

7402

7E+0

0 10

2 n,

gam

ma

8.28

826E

+03

1.36

100E

+04

1.64

207

1.04

310E

+03

6.79

110E

-02

4.19

999E

-03

Mat

eria

l(M

AT

)=74

31:W

-182

001

Tot

al

2.95

817E

+01

3.07

720E

+01

1.04

022

1.10

207E

+03

6.80

930E

+00

5.19

820E

+00

002

Ela

stic

8.

8683

6E+0

0 9.

9933

0E+0

0 1.

1268

5 4.

7390

3E+0

2 4.

4006

2E+0

0 2.

5424

8E+0

0 10

2 n,

gam

ma

2.07

133E

+01

2.07

780E

+01

1.00

314

6.28

168E

+02

6.62

525E

-02

1.00

365E

-03

Mat

eria

l(M

AT

)=74

34:W

-183

001

Tot

al

1.25

024E

+01

1.28

210E

+01

1.02

548

8.00

412E

+02

6.82

503E

+00

5.20

403E

+00

002

Ela

stic

2.

3881

0E+0

0 2.

6934

0E+0

0 1.

1278

5 4.

6547

8E+0

2 3.

9378

1E+0

0 2.

8405

9E+0

0 10

2 n,

gam

ma

1.01

143E

+01

1.01

280E

+01

1.00

131

3.34

524E

+02

5.02

757E

-02

1.00

000E

-03

Mat

eria

l(M

AT

)=74

37:W

-184

001

Tot

al

9.07

071E

+00

1.00

190E

+01

1.10

457

3.07

775E

+02

6.73

050E

+00

5.21

498E

+00

002

Ela

stic

7.

3728

8E+0

0 8.

3209

0E+0

0 1.

1285

9 2.

9174

7E+0

2 4.

2807

7E+0

0 2.

5379

9E+0

0 10

2 n,

gam

ma

1.69

783E

+00

1.69

830E

+00

1.00

028

1.60

286E

+01

3.75

970E

-02

1.00

382E

-03

Mat

eria

l(M

AT

)=74

43:W

-186

001

Tot

al

4.03

905E

+01

4.05

810E

+01

1.00

472

3.57

154E

+03

6.72

157E

+00

5.21

980E

+00

002

Ela

stic

9.

3379

9E-0

1 1.

0626

0E+0

0 1.

1379

1 3.

0426

7E+0

3 4.

2804

6E+0

0 2.

8097

2E+0

0 10

2 n,

gam

ma

3.94

567E

+01

3.95

190E

+01

1.00

157

5.28

861E

+02

3.59

600E

-02

1.00

418E

-03

Mat

eria

l(M

AT

)=75

25:R

e-18

5

001

Tot

al

1.21

064E

+02

1.22

680E

+02

1.01

337

2.00

825E

+03

6.78

826E

+00

5.31

250E

+00

002

Ela

stic

8.

8912

9E+0

0 9.

9569

0E+0

0 1.

1198

5 2.

7888

9E+0

2 4.

2394

6E+0

0 2.

6787

0E+0

0 10

2 n,

gam

ma

1.12

172E

+02

1.12

720E

+02

1.00

492

1.72

936E

+03

1.81

562E

-01

1.10

000E

-03

Mat

eria

l(M

AT

)=75

31:R

e-18

7

001

Tot

al

8.66

662E

+01

8.74

780E

+01

1.00

937

5.30

616E

+02

6.78

742E

+00

5.32

780E

+00

002

Ela

stic

9.

9623

3E+0

0 1.

1190

0E+0

1 1.

1232

1 2.

3718

0E+0

2 4.

1818

1E+0

0 2.

6985

2E+0

0 10

2 n,

gam

ma

7.67

039E

+01

7.62

880E

+01

0.99

458

2.93

436E

+02

1.17

055E

-01

1.08

200E

-03

Mat

eria

l(M

AT

)=76

00:O

s-N

at

00

1 T

otal

3.

1397

2E+0

1 3.

3276

0E+0

1 1.

0598

4 5.

1855

8E+0

2 6.

8650

4E+0

0 5.

1251

1E+0

0 00

2 E

last

ic

1.54

613E

+01

1.74

420E

+01

1.12

812

3.37

977E

+02

4.56

026E

+00

2.68

762E

+00

102

n,ga

mm

a 1.

5935

9E+0

1 1.

5834

0E+0

1 0.

9935

9 1.

8050

9E+0

2 7.

7074

6E-0

2 1.

0000

0E-0

3

Mat

eria

l(M

AT

)=77

25:I

r-19

1

001

Tot

al

9.68

343E

+02

9.66

440E

+02

0.99

803

3.86

285E

+03

6.66

963E

+00

5.21

126E

+00

002

Ela

stic

1.

3955

1E+0

1 1.

5204

0E+0

1 1.

0894

9 3.

0675

5E+0

2 4.

0116

7E+0

0 2.

7930

7E+0

0 10

2 n,

gam

ma

9.54

388E

+02

9.51

240E

+02

0.99

670

3.55

608E

+03

1.85

196E

-01

6.08

002E

-03

122 118

Page 119: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=77

31:I

r-19

3

001

Tot

al

1.31

430E

+02

1.35

740E

+02

1.03

279

1.67

601E

+03

6.67

738E

+00

5.21

157E

+00

002

Ela

stic

1.

9385

1E+0

1 2.

1805

0E+0

1 1.

1248

2 3.

0070

0E+0

2 4.

1390

9E+0

0 2.

7967

2E+0

0 10

2 n,

gam

ma

1.12

044E

+02

1.13

930E

+02

1.01

687

1.37

527E

+03

9.15

473E

-02

2.75

201E

-03

Mat

eria

l(M

AT

)=78

00:P

t-N

at

00

1 T

otal

2.

0032

4E+0

1 2.

1558

0E+0

1 1.

0761

7 2.

6999

5E+0

2 6.

2632

2E+0

0 5.

3670

6E+0

0 00

2 E

last

ic

1.20

310E

+01

1.35

790E

+01

1.12

870

1.58

395E

+02

4.56

523E

+00

3.00

000E

+00

102

n,ga

mm

a 8.

0014

6E+0

0 7.

9789

0E+0

0 0.

9971

8 1.

1160

0E+0

2 6.

7797

0E-0

2 3.

9694

6E-0

4

Mat

eria

l(M

AT

)=79

25:A

u-19

7

001

Tot

al

1.05

592E

+02

1.06

960E

+02

1.01

293

1.93

816E

+03

6.65

283E

+00

5.30

290E

+00

002

Ela

stic

6.

8559

8E+0

0 7.

7168

0E+0

0 1.

1255

6 3.

7504

8E+0

2 4.

6532

1E+0

0 2.

6361

7E+0

0 10

2 n,

gam

ma

9.87

362E

+01

9.92

400E

+01

1.00

511

1.56

309E

+03

7.79

598E

-02

1.32

637E

-03

Mat

eria

l(M

AT

)=80

25:H

g-19

6

001

Tot

al

3.18

798E

+03

3.16

310E

+03

0.99

218

8.55

166E

+02

6.64

303E

+00

5.20

526E

+00

002

Ela

stic

1.

0981

6E+0

2 1.

2181

0E+0

2 1.

1092

2 4.

3488

1E+0

2 5.

1636

3E+0

0 2.

7430

4E+0

0 10

2 n,

gam

ma

3.07

817E

+03

3.04

120E

+03

0.98

801

4.20

284E

+02

6.15

329E

-03

1.45

443E

-08

Mat

eria

l(M

AT

)=80

31:H

g-19

8

001

Tot

al

1.47

998E

+01

1.64

500E

+01

1.11

153

3.17

602E

+02

6.64

053E

+00

5.22

630E

+00

002

Ela

stic

1.

2814

1E+0

1 1.

4463

0E+0

1 1.

1286

5 2.

4329

3E+0

2 5.

1155

4E+0

0 2.

7893

6E+0

0 10

2 n,

gam

ma

1.98

569E

+00

1.98

780E

+00

1.00

105

7.43

088E

+01

3.18

854E

-02

1.21

163E

-07

Mat

eria

l(M

AT

)=80

34:H

g-19

9

001

Tot

al

2.21

631E

+03

2.20

040E

+03

0.99

280

8.02

529E

+02

6.68

114E

+00

5.24

483E

+00

002

Ela

stic

6.

6696

4E+0

1 7.

4067

0E+0

1 1.

1105

1 3.

6383

6E+0

2 4.

6454

1E+0

0 2.

7712

6E+0

0 10

2 n,

gam

ma

2.14

962E

+03

2.12

630E

+03

0.98

915

4.38

692E

+02

3.05

981E

-02

1.96

322E

-07

Mat

eria

l(M

AT

)=80

37:H

g-20

0

001

Tot

al

1.60

035E

+01

1.78

780E

+01

1.11

711

2.06

389E

+02

6.65

760E

+00

5.25

734E

+00

002

Ela

stic

1.

4560

5E+0

1 1.

6434

0E+0

1 1.

1287

0 2.

0393

8E+0

2 5.

0809

5E+0

0 2.

7519

2E+0

0 10

2 n,

gam

ma

1.44

302E

+00

1.44

330E

+00

1.00

021

2.45

097E

+00

2.15

159E

-02

2.57

438E

-07

Mat

eria

l(M

AT

)=80

40:H

g-20

1

001

Tot

al

2.22

817E

+01

2.41

460E

+01

1.08

367

2.58

054E

+02

6.72

394E

+00

5.26

926E

+00

002

Ela

stic

1.

4497

7E+0

1 1.

6363

0E+0

1 1.

1286

4 2.

2175

4E+0

2 4.

6032

0E+0

0 2.

7875

7E+0

0 10

2 n,

gam

ma

7.78

400E

+00

7.78

330E

+00

0.99

992

3.43

704E

+01

2.02

538E

-02

4.21

484E

-07

Mat

eria

l(M

AT

)=80

43:H

g-20

2

001

Tot

al

1.95

614E

+01

2.14

410E

+01

1.09

611

1.83

390E

+02

6.66

376E

+00

5.27

444E

+00

002

Ela

stic

1.

4606

3E+0

1 1.

6486

0E+0

1 1.

1286

8 1.

8026

9E+0

2 5.

1133

1E+0

0 2.

8185

5E+0

0 10

2 n,

gam

ma

4.95

501E

+00

4.95

560E

+00

1.00

012

3.12

131E

+00

1.36

221E

-02

4.76

889E

-07

119

Page 120: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=80

49:H

g-20

4

001

Tot

al

2.98

988E

+01

3.37

440E

+01

1.12

859

3.11

622E

+02

6.67

551E

+00

5.30

762E

+00

002

Ela

stic

2.

9467

3E+0

1 3.

3265

0E+0

1 1.

1288

8 3.

0894

2E+0

2 5.

3246

1E+0

0 2.

8479

8E+0

0 10

2 n,

gam

ma

4.31

436E

-01

4.78

530E

-01

1.10

916

2.67

972E

+00

8.64

935E

-03

2.91

008E

-07

Mat

eria

l(M

AT

)=81

00:T

l-N

at

00

1 T

otal

1.

3626

7E+0

1 1.

5663

0E+0

1 1.

1494

4 2.

1442

4E+0

2 6.

5884

5E+0

0 5.

1700

3E+0

0 00

2 E

last

ic

1.00

346E

+01

1.13

260E

+01

1.12

870

2.00

676E

+02

4.86

679E

+00

2.58

451E

+00

102

n,ga

mm

a 3.

5920

8E+0

0 4.

3371

0E+0

0 1.

2074

0 1.

3748

4E+0

1 1.

2511

0E-0

2 9.

0035

7E-0

4

Mat

eria

l(M

AT

)=82

25:P

b-20

4

001

Tot

al

1.18

849E

+01

1.33

300E

+01

1.12

156

1.45

504E

+02

6.36

148E

+00

5.23

565E

+00

002

Ela

stic

1.

1224

2E+0

1 1.

2669

0E+0

1 1.

1287

0 1.

4372

7E+0

2 5.

1799

1E+0

0 2.

7248

6E+0

0 10

2 n,

gam

ma

6.60

683E

-01

6.60

870E

-01

1.00

028

1.77

749E

+00

1.21

825E

-02

2.26

710E

-03

Mat

eria

l(M

AT

)=82

31:P

b-20

6

001

Tot

al

1.12

938E

+01

1.27

430E

+01

1.12

836

1.29

231E

+02

6.18

956E

+00

5.26

210E

+00

002

Ela

stic

1.

1264

0E+0

1 1.

2714

0E+0

1 1.

1287

0 1.

2914

0E+0

2 5.

0402

7E+0

0 2.

7437

0E+0

0 10

2 n,

gam

ma

2.97

897E

-02

2.97

960E

-02

1.00

022

9.12

451E

-02

3.00

133E

-03

1.10

198E

-03

Mat

eria

l(M

AT

)=82

34:P

b-20

7

001

Tot

al

1.14

855E

+01

1.28

720E

+01

1.12

074

1.32

088E

+02

6.48

572E

+00

5.27

379E

+00

002

Ela

stic

1.

0773

5E+0

1 1.

2160

0E+0

1 1.

1287

0 1.

3171

0E+0

2 5.

4122

4E+0

0 2.

7515

9E+0

0 10

2 n,

gam

ma

7.11

997E

-01

7.12

170E

-01

1.00

025

3.77

978E

-01

2.36

486E

-03

1.33

946E

-03

Mat

eria

l(M

AT

)=82

37:P

b-20

8

001

Tot

al

1.13

994E

+01

1.28

660E

+01

1.12

869

1.38

569E

+02

6.48

581E

+00

5.39

161E

+00

002

Ela

stic

1.

1398

9E+0

1 1.

2866

0E+0

1 1.

1287

0 1.

3856

8E+0

2 6.

1146

1E+0

0 2.

8232

1E+0

0 10

2 n,

gam

ma

4.92

088E

-04

4.92

200E

-04

1.00

024

1.10

300E

-03

8.65

541E

-04

1.19

036E

-03

Mat

eria

l(M

AT

)=83

25:B

i-20

9

001

Tot

al

9.35

393E

+00

1.05

530E

+01

1.12

822

1.44

197E

+02

6.50

480E

+00

5.33

433E

+00

002

Ela

stic

9.

3199

4E+0

0 1.

0519

0E+0

1 1.

1286

9 1.

4400

7E+0

2 5.

7854

5E+0

0 2.

7394

3E+0

0 10

2 n,

gam

ma

3.38

443E

-02

3.38

520E

-02

1.00

023

1.91

082E

-01

3.12

345E

-03

1.60

094E

-03

Mat

eria

l(M

AT

)=88

25:R

a-22

3

001

Tot

al

1.43

132E

+02

1.44

770E

+02

1.01

143

8.70

886E

+02

7.55

826E

+00

6.17

677E

+00

002

Ela

stic

1.

2428

0E+0

1 1.

4027

0E+0

1 1.

1287

0 4.

3354

6E+0

2 5.

2463

7E+0

0 3.

1168

8E+0

0 01

8 Fi

ssio

n 7.

0002

3E-0

1 7.

0021

0E-0

1 1.

0002

7 7.

6637

2E-0

1 5.

5699

7E-0

2 5.

5700

0E-0

2 10

2 n,

gam

ma

1.30

004E

+02

1.30

040E

+02

1.00

028

4.36

318E

+02

4.61

810E

-02

3.75

182E

-06

120

Page 121: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=88

28:R

a-22

4

001

Tot

al

2.45

285E

+01

2.61

440E

+01

1.06

587

3.52

674E

+02

7.55

845E

+00

6.13

193E

+00

002

Ela

stic

1.

2528

1E+0

1 1.

4140

0E+0

1 1.

1287

0 3.

2376

4E+0

2 5.

5184

0E+0

0 3.

1207

2E+0

0 10

2 n,

gam

ma

1.20

004E

+01

1.20

040E

+01

1.00

027

2.88

986E

+01

3.15

041E

-02

2.74

345E

-06

Mat

eria

l(M

AT

)=88

31:R

a-22

5

001

Tot

al

1.12

426E

+02

1.14

010E

+02

1.01

406

9.84

561E

+02

7.57

423E

+00

6.14

293E

+00

002

Ela

stic

1.

2427

7E+0

1 1.

4027

0E+0

1 1.

1287

0 3.

8930

2E+0

2 5.

2756

1E+0

0 3.

1246

0E+0

0 10

2 n,

gam

ma

9.99

983E

+01

9.99

800E

+01

0.99

981

5.94

560E

+02

5.06

573E

-02

1.57

332E

-06

Mat

eria

l(M

AT

)=88

34:R

a-22

6

001

Tot

al

2.26

138E

+01

2.46

960E

+01

1.09

207

4.95

187E

+02

7.57

081E

+00

6.15

378E

+00

002

Ela

stic

9.

8224

3E+0

0 1.

1066

0E+0

1 1.

1265

8 2.

1327

2E+0

2 5.

5158

9E+0

0 3.

1282

8E+0

0 01

8 Fi

ssio

n 6.

9999

6E-0

6 6.

9994

0E-0

6 0.

9999

2 5.

6629

3E-0

6 3.

4911

5E-0

4 1.

1500

1E-0

2 10

2 n,

gam

ma

1.27

913E

+01

1.36

300E

+01

1.06

558

2.81

874E

+02

1.08

481E

-01

3.21

174E

-05

Mat

eria

l(M

AT

)=89

25:A

c-22

5

001

Tot

al

1.01

246E

+03

1.01

430E

+03

1.00

183

1.86

205E

+03

7.56

480E

+00

6.14

287E

+00

002

Ela

stic

1.

2427

7E+0

1 1.

4027

0E+0

1 1.

1287

0 2.

7134

8E+0

2 5.

2343

2E+0

0 3.

1246

0E+0

0 10

2 n,

gam

ma

1.00

003E

+03

1.00

030E

+03

1.00

025

1.59

042E

+03

1.71

229E

-01

3.76

429E

-06

Mat

eria

l(M

AT

)=89

28:A

c-22

6

001

Tot

al

1.12

431E

+02

1.14

060E

+02

1.01

450

1.91

552E

+03

7.56

141E

+00

5.61

669E

+00

002

Ela

stic

1.

2427

6E+0

1 1.

4027

0E+0

1 1.

1286

9 2.

3338

4E+0

2 5.

2147

9E+0

0 3.

1744

5E+0

0 10

2 n,

gam

ma

1.00

003E

+02

1.00

030E

+02

1.00

031

1.68

213E

+03

1.75

222E

-01

5.72

558E

-09

Mat

eria

l(M

AT

)=89

31:A

c-22

7

001

Tot

al

9.14

049E

+02

1.04

340E

+03

1.14

148

1.98

721E

+03

7.62

148E

+00

6.17

021E

+00

002

Ela

stic

1.

2427

5E+0

1 1.

4027

0E+0

1 1.

1287

0 3.

2891

3E+0

2 5.

3116

6E+0

0 3.

1374

7E+0

0 01

8 Fi

ssio

n 2.

9001

0E-0

4 2.

9010

0E-0

4 1.

0003

0 1.

7632

2E-0

4 1.

2657

2E-0

2 1.

2400

0E-0

1 10

2 n,

gam

ma

9.01

621E

+02

1.02

930E

+03

1.14

166

1.65

734E

+03

3.55

656E

-03

1.38

926E

-09

Mat

eria

l(M

AT

)=90

25:T

h-22

7

001

Tot

al

1.74

949E

+03

1.75

160E

+03

1.00

120

1.84

870E

+03

7.58

441E

+00

5.62

352E

+00

002

Ela

stic

1.

2427

5E+0

1 1.

4027

0E+0

1 1.

1286

9 2.

2434

2E+0

2 5.

2313

7E+0

0 3.

1729

1E+0

0 01

8 Fi

ssio

n 2.

0200

7E+0

2 2.

0206

0E+0

2 1.

0002

9 2.

0632

5E+0

2 4.

8396

4E-0

1 2.

0500

0E+0

0 10

2 n,

gam

ma

1.53

505E

+03

1.53

550E

+03

1.00

028

1.41

797E

+03

1.97

199E

-01

5.01

486E

-08

Mat

eria

l(M

AT

)=90

28:T

h-22

8

001

Tot

al

1.33

008E

+02

1.35

040E

+02

1.01

526

1.58

426E

+03

7.58

646E

+00

5.64

353E

+00

002

Ela

stic

1.

2833

2E+0

1 1.

4455

0E+0

1 1.

1263

9 4.

1491

2E+0

2 5.

4768

3E+0

0 3.

1843

9E+0

0 01

8 Fi

ssio

n 3.

0000

9E-0

1 3.

0008

0E-0

1 1.

0002

5 1.

3331

4E-0

1 1.

0503

5E-0

1 5.

4900

1E-0

1 10

2 n,

gam

ma

1.19

875E

+02

1.20

280E

+02

1.00

340

1.16

914E

+03

8.03

674E

-02

2.40

360E

-10

121

Page 122: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=90

31:T

h-22

9

001

Tot

al

1.04

164E

+02

1.08

670E

+02

1.04

326

1.85

545E

+03

7.62

080E

+00

6.18

694E

+00

002

Ela

stic

9.

9592

7E+0

0 1.

1175

0E+0

1 1.

1220

3 1.

7756

0E+0

2 5.

1563

0E+0

0 3.

1394

7E+0

0 01

8 Fi

ssio

n 3.

0820

9E+0

1 3.

1355

0E+0

1 1.

0173

3 4.

4046

0E+0

2 4.

8396

4E-0

1 2.

0500

0E+0

0 10

2 n,

gam

ma

6.33

838E

+01

6.61

400E

+01

1.04

349

1.23

525E

+03

2.09

081E

-01

7.86

926E

-06

Mat

eria

l(M

AT

)=90

34:T

h-23

0

001

Tot

al

2.91

775E

+01

3.00

750E

+01

1.03

075

1.22

375E

+03

8.45

268E

+00

6.30

469E

+00

002

Ela

stic

6.

0928

0E+0

0 6.

8507

0E+0

0 1.

1244

0 3.

7217

7E+0

2 5.

3974

3E+0

0 3.

5205

6E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 4.

8089

7E-0

3 1.

7964

4E-0

1 6.

4999

9E-0

1 10

2 n,

gam

ma

2.30

847E

+01

2.32

240E

+01

1.00

603

8.51

349E

+02

1.99

949E

-02

1.10

289E

-02

Mat

eria

l(M

AT

)=90

40:T

h-23

2

001

Tot

al

2.03

780E

+01

2.19

990E

+01

1.07

955

3.03

115E

+02

7.77

239E

+00

5.84

382E

+00

002

Ela

stic

1.

2974

6E+0

1 1.

4607

0E+0

1 1.

1258

2 2.

1730

4E+0

2 4.

8195

3E+0

0 2.

7587

1E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 3.

3094

6E-0

6 7.

7958

4E-0

2 3.

4594

6E-0

1 10

2 n,

gam

ma

7.40

345E

+00

7.39

220E

+00

0.99

848

8.56

465E

+01

9.01

425E

-02

1.00

002E

-03

Mat

eria

l(M

AT

)=90

43:T

h-23

3

001

Tot

al

1.47

808E

+03

1.48

020E

+03

1.00

145

8.61

895E

+02

7.63

938E

+00

5.67

011E

+00

002

Ela

stic

1.

3028

1E+0

1 1.

4708

0E+0

1 1.

1289

1 2.

0730

1E+0

2 5.

3369

3E+0

0 3.

1673

1E+0

0 01

8 Fi

ssio

n 1.

5004

2E+0

1 1.

5060

0E+0

1 1.

0037

3 1.

0268

4E+0

1 1.

1138

8E-0

1 4.

0999

9E-0

1 10

2 n,

gam

ma

1.45

005E

+03

1.45

050E

+03

1.00

028

6.43

523E

+02

8.86

580E

-02

6.07

111E

-09

Mat

eria

l(M

AT

)=90

46:T

h-23

4

001

Tot

al

1.47

780E

+01

1.64

550E

+01

1.11

350

3.86

105E

+02

7.67

125E

+00

5.67

955E

+00

002

Ela

stic

1.

3028

0E+0

1 1.

4705

0E+0

1 1.

1287

3 2.

9250

2E+0

2 5.

5445

2E+0

0 3.

1679

9E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 0.

0000

0E+0

0 3.

6295

0E-0

2 1.

5000

0E-0

1 10

2 n,

gam

ma

1.75

003E

+00

1.75

030E

+00

1.00

014

9.34

817E

+01

1.02

234E

-01

1.54

057E

-07

Mat

eria

l(M

AT

)=91

31:P

a-23

1

001

Tot

al

2.35

368E

+02

2.35

050E

+02

0.99

864

7.17

568E

+02

8.45

151E

+00

6.42

764E

+00

002

Ela

stic

8.

4570

2E+0

0 9.

3968

0E+0

0 1.

1111

2 1.

2208

8E+0

2 4.

7797

6E+0

0 2.

7715

2E+0

0 01

8 Fi

ssio

n 1.

0386

9E-0

2 1.

0546

0E-0

2 1.

0153

3 1.

2088

8E-0

1 9.

8106

6E-0

1 1.

9717

4E+0

0 10

2 n,

gam

ma

2.26

901E

+02

2.25

640E

+02

0.99

445

5.94

653E

+02

3.93

544E

-01

1.12

225E

-01

Mat

eria

l(M

AT

)=91

34:P

a-23

2

001

Tot

al

1.76

216E

+03

1.83

220E

+03

1.03

976

1.21

376E

+03

7.68

521E

+00

5.67

482E

+00

002

Ela

stic

3.

2744

8E+0

1 3.

6697

0E+0

1 1.

1206

9 2.

0314

9E+0

2 5.

1082

7E+0

0 3.

1816

3E+0

0 01

8 Fi

ssio

n 1.

5173

2E+0

3 1.

5718

0E+0

3 1.

0359

4 8.

6423

3E+0

2 1.

1025

0E+0

0 1.

3810

0E+0

0 10

2 n,

gam

ma

2.12

095E

+02

2.23

680E

+02

1.05

464

1.46

324E

+02

7.41

860E

-02

5.62

267E

-09

122

Page 123: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=91

37:P

a-23

3

001

Tot

al

4.98

816E

+01

5.00

990E

+01

1.00

436

9.89

572E

+02

7.32

459E

+00

5.42

088E

+00

002

Ela

stic

8.

4315

6E+0

0 9.

4914

0E+0

0 1.

1257

0 1.

3262

4E+0

2 4.

5049

3E+0

0 3.

0143

4E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 0.

0000

0E+0

0 4.

6009

4E-0

1 1.

5818

7E+0

0 10

2 n,

gam

ma

4.14

500E

+01

4.06

080E

+01

0.97

968

8.54

733E

+02

1.86

990E

-01

6.66

667E

-03

Mat

eria

l(M

AT

)=92

19:U

-232

001

Tot

al

1.57

196E

+02

1.54

300E

+02

0.98

159

8.75

547E

+02

8.58

339E

+00

6.38

921E

+00

002

Ela

stic

7.

5402

0E+0

0 8.

4664

0E+0

0 1.

1228

3 1.

4314

6E+0

2 4.

7159

0E+0

0 3.

0151

7E+0

0 01

8 Fi

ssio

n 7.

7085

8E+0

1 7.

5296

0E+0

1 0.

9767

9 4.

1589

4E+0

2 2.

4840

5E+0

0 1.

2381

4E+0

0 10

2 n,

gam

ma

7.25

705E

+01

7.05

390E

+01

0.97

201

3.16

405E

+02

1.04

713E

-01

5.60

544E

-02

Mat

eria

l(M

AT

)=92

22:U

-233

001

Tot

al

5.88

496E

+02

5.89

330E

+02

1.00

141

1.04

193E

+03

7.68

530E

+00

5.91

376E

+00

002

Ela

stic

1.

1992

9E+0

1 1.

3504

0E+0

1 1.

1259

9 1.

4150

5E+0

2 4.

5125

2E+0

0 3.

0195

1E+0

0 01

8 Fi

ssio

n 5.

3123

6E+0

2 5.

2916

0E+0

2 0.

9960

9 7.

6239

5E+0

2 1.

9113

7E+0

0 2.

3111

7E+0

0 10

2 n,

gam

ma

4.52

673E

+01

4.66

630E

+01

1.03

084

1.37

969E

+02

7.27

508E

-02

7.47

467E

-04

Mat

eria

l(M

AT

)=92

25:U

-234

001

Tot

al

1.19

273E

+02

1.20

580E

+02

1.01

100

9.39

733E

+02

7.80

521E

+00

5.86

053E

+00

002

Ela

stic

1.

9448

7E+0

1 2.

1758

0E+0

1 1.

1187

6 3.

0780

7E+0

2 4.

7080

4E+0

0 2.

8232

9E+0

0 01

8 Fi

ssio

n 6.

6964

2E-0

2 6.

6314

0E-0

2 0.

9903

0 8.

2171

2E-0

1 1.

1704

6E+0

0 1.

9783

7E+0

0 10

2 n,

gam

ma

9.97

569E

+01

9.87

590E

+01

0.99

000

6.30

902E

+02

1.11

551E

-01

1.00

005E

-03

Mat

eria

l(M

AT

)=92

28:U

-235

001

Tot

al

6.98

719E

+02

6.85

930E

+02

0.98

169

5.52

906E

+02

7.65

918E

+00

5.87

234E

+00

002

Ela

stic

1.

5115

3E+0

1 1.

6940

0E+0

1 1.

1206

9 1.

4407

9E+0

2 4.

4141

8E+0

0 2.

8523

0E+0

0 01

8 Fi

ssio

n 5.

8493

2E+0

2 5.

7119

0E+0

2 0.

9765

1 2.

6884

5E+0

2 1.

2185

1E+0

0 2.

0600

0E+0

0 10

2 n,

gam

ma

9.86

724E

+01

9.77

930E

+01

0.99

109

1.39

845E

+02

9.53

408E

-02

1.20

890E

-03

Mat

eria

l(M

AT

)=92

31:U

-236

001

Tot

al

1.37

120E

+01

1.47

920E

+01

1.07

873

6.02

388E

+02

7.69

863E

+00

5.86

721E

+00

002

Ela

stic

8.

3545

3E+0

0 9.

4235

0E+0

0 1.

1279

5 2.

5316

3E+0

2 4.

8288

7E+0

0 2.

7835

0E+0

0 01

8 Fi

ssio

n 6.

1298

3E-0

2 6.

1433

0E-0

2 1.

0022

0 4.

3352

6E+0

0 5.

9422

2E-0

1 1.

6311

5E+0

0 10

2 n,

gam

ma

5.29

616E

+00

5.30

660E

+00

1.00

198

3.44

749E

+02

7.61

704E

-02

2.55

198E

-03

Mat

eria

l(M

AT

)=92

34:U

-237

001

Tot

al

4.78

448E

+02

4.70

180E

+02

0.98

272

1.32

922E

+03

8.11

983E

+00

5.83

283E

+00

002

Ela

stic

2.

4435

4E+0

1 2.

6869

0E+0

1 1.

0995

8 2.

0080

6E+0

2 4.

5966

0E+0

0 2.

7066

3E+0

0 01

8 Fi

ssio

n 1.

7023

0E+0

0 1.

6732

0E+0

0 0.

9829

2 4.

4370

3E+0

1 8.

8687

5E-0

1 1.

5330

6E+0

0 10

2 n,

gam

ma

4.52

310E

+02

4.41

640E

+02

0.97

641

1.08

304E

+03

5.63

979E

-02

2.53

830E

-03

123

Page 124: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=92

37:U

-238

001

Tot

al

1.21

209E

+01

1.33

370E

+01

1.10

033

5.92

421E

+02

7.90

121E

+00

5.95

861E

+00

002

Ela

stic

9.

4372

2E+0

0 1.

0648

0E+0

1 1.

1282

8 3.

1728

5E+0

2 4.

9281

5E+0

0 2.

7751

4E+0

0 01

8 Fi

ssio

n 2.

6512

4E-0

5 2.

6539

0E-0

5 1.

0010

0 1.

2166

6E-0

3 3.

0125

3E-0

1 1.

1787

9E+0

0 10

2 n,

gam

ma

2.68

363E

+00

2.68

910E

+00

1.00

205

2.74

955E

+02

6.98

823E

-02

2.51

665E

-03

Mat

eria

l(M

AT

)=93

40:N

p-23

5

001

Tot

al

1.81

433E

+02

1.82

980E

+02

1.00

854

1.05

418E

+03

7.42

042E

+00

5.92

372E

+00

002

Ela

stic

1.

1424

4E+0

1 1.

2895

0E+0

1 1.

1287

2 1.

6572

0E+0

2 4.

3951

3E+0

0 2.

9716

0E+0

0 01

8 Fi

ssio

n 1.

9998

5E+0

1 1.

9984

0E+0

1 0.

9992

6 3.

6840

5E+0

1 1.

8871

6E+0

0 2.

4487

1E+0

0 10

2 n,

gam

ma

1.50

010E

+02

1.50

100E

+02

1.00

063

8.51

438E

+02

1.21

911E

-01

7.37

811E

-04

Mat

eria

l(M

AT

)=93

43:N

p-23

6

001

Tot

al

3.48

303E

+03

3.48

320E

+03

1.00

004

1.42

780E

+03

7.76

557E

+00

5.84

944E

+00

002

Ela

stic

1.

2296

3E+0

1 1.

3879

0E+0

1 1.

1287

2 1.

4560

9E+0

2 5.

0857

1E+0

0 3.

1480

0E+0

0 01

8 Fi

ssio

n 2.

7697

8E+0

3 2.

7686

0E+0

3 0.

9995

9 1.

0234

0E+0

3 1.

9223

1E+0

0 2.

4318

1E+0

0 10

2 n,

gam

ma

7.00

944E

+02

7.00

640E

+02

0.99

956

2.58

791E

+02

1.89

506E

-01

1.00

377E

-03

Mat

eria

l(M

AT

)=93

46:N

p-23

7

001

Tot

al

1.75

802E

+02

1.75

010E

+02

0.99

547

8.31

491E

+02

7.85

367E

+00

5.78

427E

+00

002

Ela

stic

1.

4085

1E+0

1 1.

5732

0E+0

1 1.

1169

1 1.

6967

2E+0

2 4.

6518

9E+0

0 2.

7849

8E+0

0 01

8 Fi

ssio

n 2.

0365

0E-0

2 1.

9875

0E-0

2 0.

9759

3 6.

3669

4E-0

1 1.

3343

1E+0

0 2.

1559

0E+0

0 10

2 n,

gam

ma

1.61

697E

+02

1.59

250E

+02

0.98

490

6.60

804E

+02

1.58

595E

-01

1.07

209E

-03

Mat

eria

l(M

AT

)=93

49:N

p-23

8

001

Tot

al

2.25

073E

+03

2.23

270E

+03

0.99

197

1.15

393E

+03

7.84

587E

+00

6.05

519E

+00

002

Ela

stic

2.

0854

8E+0

1 2.

3293

0E+0

1 1.

1169

1 1.

4294

7E+0

2 4.

8625

1E+0

0 2.

9145

7E+0

0 01

8 Fi

ssio

n 2.

0270

3E+0

3 2.

0083

0E+0

3 0.

9907

8 9.

1028

3E+0

2 1.

4882

3E+0

0 1.

8500

0E+0

0 10

2 n,

gam

ma

2.02

846E

+02

2.01

020E

+02

0.99

099

1.00

612E

+02

3.39

726E

-02

1.06

197E

-02

Mat

eria

l(M

AT

)=93

52:N

p-23

9

001

Tot

al

8.75

253E

+01

8.89

010E

+01

1.01

571

6.17

232E

+02

7.85

505E

+00

5.53

495E

+00

002

Ela

stic

1.

0522

1E+0

1 1.

1876

0E+0

1 1.

1287

1 1.

6041

5E+0

2 4.

7517

5E+0

0 2.

6519

7E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 4.

1233

1E-0

2 1.

4475

4E+0

0 2.

4200

0E+0

0 10

2 n,

gam

ma

7.70

032E

+01

7.70

240E

+01

1.00

027

4.56

264E

+02

2.02

180E

-01

1.00

005E

-05

Mat

eria

l(M

AT

)=94

28:P

u-23

6

001

Tot

al

2.05

227E

+02

2.05

470E

+02

1.00

118

1.37

044E

+03

7.88

166E

+00

5.95

089E

+00

002

Ela

stic

9.

1783

6E+0

0 1.

0336

0E+0

1 1.

1261

3 1.

5403

7E+0

2 4.

4791

1E+0

0 2.

7539

6E+0

0 01

8 Fi

ssio

n 1.

6482

1E+0

2 1.

6389

0E+0

2 0.

9943

8 9.

4957

4E+0

2 2.

0993

7E+0

0 2.

5477

3E+0

0 10

2 n,

gam

ma

3.12

278E

+01

3.12

390E

+01

1.00

037

2.66

711E

+02

6.22

997E

-02

8.02

168E

-04

129 124

Page 125: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=94

31:P

u-23

7

001

Tot

al

2.65

184E

+03

2.65

410E

+03

1.00

084

1.40

075E

+03

7.56

532E

+00

6.42

911E

+00

002

Ela

stic

1.

1758

9E+0

1 1.

3273

0E+0

1 1.

1287

2 1.

3982

2E+0

2 4.

2563

2E+0

0 3.

3207

0E+0

0 01

8 Fi

ssio

n 2.

1000

7E+0

3 2.

1006

0E+0

3 1.

0002

7 1.

0705

6E+0

3 3.

0080

4E+0

0 2.

6932

1E+0

0 10

2 n,

gam

ma

5.40

018E

+02

5.40

170E

+02

1.00

028

1.90

351E

+02

3.18

665E

-02

2.40

001E

-03

Mat

eria

l(M

AT

)=94

34:P

u-23

8

001

Tot

al

5.86

500E

+02

5.65

140E

+02

0.96

358

4.11

853E

+02

8.81

707E

+00

6.86

876E

+00

002

Ela

stic

2.

8577

7E+0

1 3.

1473

0E+0

1 1.

1013

2 2.

3484

2E+0

2 6.

0183

3E+0

0 3.

5838

7E+0

0 01

8 Fi

ssio

n 1.

7881

1E+0

1 1.

7119

0E+0

1 0.

9573

6 2.

7492

1E+0

1 1.

9860

4E+0

0 2.

7145

9E+0

0 10

2 n,

gam

ma

5.40

041E

+02

5.16

550E

+02

0.95

650

1.49

374E

+02

9.82

352E

-02

5.86

100E

-09

Mat

eria

l(M

AT

)=94

37:P

u-23

9

001

Tot

al

1.02

646E

+03

1.10

730E

+03

1.07

879

6.28

125E

+02

7.80

185E

+00

5.79

457E

+00

002

Ela

stic

7.

9904

2E+0

0 8.

8068

0E+0

0 1.

1021

7 1.

5324

5E+0

2 4.

6180

5E+0

0 2.

7504

3E+0

0 01

8 Fi

ssio

n 7.

4778

5E+0

2 7.

8857

0E+0

2 1.

0545

4 2.

9296

1E+0

2 1.

7909

9E+0

0 2.

4180

0E+0

0 10

2 n,

gam

ma

2.70

686E

+02

3.09

960E

+02

1.14

509

1.81

119E

+02

5.50

898E

-02

2.00

097E

-03

Mat

eria

l(M

AT

)=94

40:P

u-24

0

001

Tot

al

2.88

552E

+02

2.96

290E

+02

1.02

681

9.45

309E

+03

7.83

441E

+00

5.79

421E

+00

002

Ela

stic

2.

6669

2E+0

0 2.

8278

0E+0

0 1.

0603

4 9.

6576

6E+0

2 4.

7857

8E+0

0 2.

6837

1E+0

0 01

8 Fi

ssio

n 5.

9159

6E-0

2 6.

1093

0E-0

2 1.

0326

9 3.

3568

6E+0

0 1.

3486

6E+0

0 2.

1448

0E+0

0 10

2 n,

gam

ma

2.85

826E

+02

2.93

400E

+02

1.02

650

8.48

383E

+03

8.33

478E

-02

2.06

826E

-03

Mat

eria

l(M

AT

)=94

43:P

u-24

1

001

Tot

al

1.38

638E

+03

1.44

550E

+03

1.04

265

8.93

360E

+02

7.86

018E

+00

5.81

392E

+00

002

Ela

stic

1.

1259

1E+0

1 1.

2477

0E+0

1 1.

1081

5 1.

5237

3E+0

2 5.

1954

2E+0

0 3.

3046

2E+0

0 01

8 Fi

ssio

n 1.

0121

4E+0

3 1.

0595

0E+0

3 1.

0467

7 5.

6085

7E+0

2 1.

6505

2E+0

0 2.

2980

0E+0

0 10

2 n,

gam

ma

3.62

975E

+02

3.73

540E

+02

1.02

912

1.80

110E

+02

1.20

515E

-01

1.04

967E

-07

Mat

eria

l(M

AT

)=94

46:P

u-24

2

001

Tot

al

2.71

347E

+01

2.83

680E

+01

1.04

544

1.45

376E

+03

7.95

644E

+00

5.95

370E

+00

002

Ela

stic

8.

3369

4E+0

0 9.

3848

0E+0

0 1.

1256

8 3.

2297

6E+0

2 4.

8184

6E+0

0 2.

7906

0E+0

0 01

8 Fi

ssio

n 2.

5574

2E-0

3 2.

5722

0E-0

3 1.

0057

9 2.

5351

1E-0

1 1.

1546

8E+0

0 2.

0886

0E+0

0 10

2 n,

gam

ma

1.87

952E

+01

1.89

800E

+01

1.00

985

1.13

023E

+03

8.92

200E

-02

7.99

999E

-04

Mat

eria

l(M

AT

)=94

49:P

u-24

3

001

Tot

al

2.89

010E

+02

2.89

070E

+02

1.00

021

9.88

402E

+02

7.86

099E

+00

5.69

267E

+00

002

Ela

stic

1.

9491

3E+0

1 2.

1779

0E+0

1 1.

1174

0 1.

6074

1E+0

2 4.

6494

7E+0

0 2.

5910

7E+0

0 01

8 Fi

ssio

n 1.

8140

6E+0

2 1.

7991

0E+0

2 0.

9917

3 5.

5320

2E+0

2 1.

0651

3E+0

0 1.

9000

0E+0

0 10

2 n,

gam

ma

8.81

122E

+01

8.73

850E

+01

0.99

175

2.74

439E

+02

4.39

346E

-02

1.60

000E

-03

125

Page 126: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=94

52:P

u-24

4

001

Tot

al

1.14

745E

+01

1.27

080E

+01

1.10

747

2.95

806E

+02

7.83

117E

+00

5.43

671E

+00

002

Ela

stic

9.

6444

4E+0

0 1.

0882

0E+0

1 1.

1283

3 1.

9011

7E+0

2 4.

8926

9E+0

0 3.

0758

2E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 6.

5911

3E-0

2 9.

9218

8E-0

1 1.

6890

5E+0

0 10

2 n,

gam

ma

1.83

003E

+00

1.82

550E

+00

0.99

752

1.05

320E

+02

1.76

183E

-02

2.80

001E

-03

Mat

eria

l(M

AT

)=94

58:P

u-24

6

001

Tot

al

8.10

580E

+02

8.09

600E

+02

0.99

880

8.40

216E

+02

7.91

779E

+00

5.99

026E

+00

002

Ela

stic

1.

0822

1E+0

1 1.

2215

0E+0

1 1.

1287

0 1.

4798

6E+0

2 4.

0022

4E+0

0 2.

9776

3E+0

0 01

8 Fi

ssio

n 0.

0000

0E+0

0 0.

0000

0E+0

0 0.

0000

0 6.

4802

6E-0

4 7.

3405

2E-0

1 1.

6437

0E+0

0 10

2 n,

gam

ma

7.99

758E

+02

7.97

390E

+02

0.99

704

6.92

103E

+02

1.14

833E

+00

9.34

958E

-04

Mat

eria

l(M

AT

)=95

43:A

m-2

41

00

1 T

otal

6.

6252

6E+0

2 6.

7361

0E+0

2 1.

0167

3 1.

6887

5E+0

3 7.

8143

0E+0

0 5.

7414

9E+0

0 00

2 E

last

ic

1.22

568E

+01

1.32

800E

+01

1.08

350

1.53

352E

+02

4.59

900E

+00

2.51

013E

+00

018

Fiss

ion

3.15

054E

+00

3.33

380E

+00

1.05

816

1.07

808E

+01

1.36

486E

+00

2.67

000E

+00

102

n,ga

mm

a 6.

4711

9E+0

2 6.

5700

0E+0

2 1.

0152

7 1.

5244

9E+0

3 2.

5727

5E-0

1 7.

0192

0E-0

4

Mat

eria

l(M

AT

)=95

46:A

m-2

42

00

1 T

otal

2.

3214

3E+0

3 2.

4374

0E+0

3 1.

0499

7 1.

3091

5E+0

3 7.

7543

7E+0

0 5.

7121

9E+0

0 00

2 E

last

ic

7.67

958E

+00

8.66

930E

+00

1.12

887

1.36

205E

+02

4.45

838E

+00

2.84

035E

+00

018

Fiss

ion

2.09

476E

+03

2.19

950E

+03

1.05

001

9.86

371E

+02

1.75

829E

+00

2.17

538E

+00

102

n,ga

mm

a 2.

1898

5E+0

2 2.

2925

0E+0

2 1.

0468

8 1.

8652

8E+0

2 4.

7475

3E-0

2 7.

3355

2E-0

4

Mat

eria

l(M

AT

)=95

47:A

m-2

42M

001

Tot

al

7.63

436E

+03

8.36

870E

+03

1.09

619

1.89

817E

+03

7.75

507E

+00

5.72

723E

+00

002

Ela

stic

5.

2667

0E+0

0 6.

5779

0E+0

0 1.

2489

5 1.

2668

1E+0

2 4.

3594

8E+0

0 2.

5195

6E+0

0 01

8 Fi

ssio

n 6.

3982

5E+0

3 7.

0079

0E+0

3 1.

0952

9 1.

5326

6E+0

3 1.

8447

1E+0

0 2.

5498

4E+0

0 10

2 n,

gam

ma

1.23

084E

+03

1.35

420E

+03

1.10

024

2.38

793E

+02

7.53

542E

-02

7.33

552E

-04

Mat

eria

l(M

AT

)=95

49:A

m-2

43

00

1 T

otal

8.

4290

4E+0

1 8.

6235

0E+0

1 1.

0230

7 1.

9502

1E+0

3 7.

7290

9E+0

0 5.

7006

6E+0

0 00

2 E

last

ic

7.47

918E

+00

8.38

580E

+00

1.12

122

1.61

350E

+02

4.47

966E

+00

2.81

774E

+00

018

Fiss

ion

8.13

240E

-02

8.23

540E

-02

1.01

267

2.19

959E

+00

1.06

590E

+00

2.14

333E

+00

102

n,ga

mm

a 7.

6729

9E+0

1 7.

7767

0E+0

1 1.

0135

2 1.

7865

0E+0

3 2.

2621

0E-0

1 8.

8419

1E-0

4

Mat

eria

l(M

AT

)=95

52:A

m-2

44

00

1 T

otal

2.

9115

6E+0

3 2.

9927

0E+0

3 1.

0278

5 1.

7015

1E+0

3 7.

8258

9E+0

0 5.

9359

6E+0

0 00

2 E

last

ic

1.16

463E

+01

1.31

450E

+01

1.12

870

1.37

607E

+02

4.56

686E

+00

2.81

081E

+00

018

Fiss

ion

2.29

994E

+03

2.36

580E

+03

1.02

864

1.24

956E

+03

1.76

323E

+00

2.43

779E

+00

102

n,ga

mm

a 5.

9997

8E+0

2 6.

1371

0E+0

2 1.

0228

9 3.

1434

2E+0

2 3.

3914

7E-0

1 1.

7755

1E-0

7

126

Page 127: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=95

53:A

m-2

44M

001

Tot

al

2.01

169E

+03

2.21

740E

+03

1.10

226

1.70

155E

+03

7.82

538E

+00

5.93

596E

+00

002

Ela

stic

1.

1645

7E+0

1 1.

3145

0E+0

1 1.

1287

0 1.

3756

5E+0

2 4.

5298

4E+0

0 2.

8108

1E+0

0 01

8 Fi

ssio

n 1.

6000

6E+0

3 1.

7629

0E+0

3 1.

1018

0 1.

2496

1E+0

3 1.

7632

3E+0

0 2.

4377

9E+0

0 10

2 n,

gam

ma

3.99

984E

+02

4.41

320E

+02

1.10

334

3.14

319E

+02

3.70

872E

-01

1.12

652E

-06

Mat

eria

l(M

AT

)=96

25:C

m-2

40

00

1 T

otal

1.

9840

3E+0

2 1.

9523

0E+0

2 0.

9840

0 8.

9314

7E+0

2 7.

6245

4E+0

0 5.

9748

7E+0

0 00

2 E

last

ic

1.31

128E

+01

1.46

210E

+01

1.11

501

1.91

895E

+02

4.94

067E

+00

3.05

862E

+00

018

Fiss

ion

9.75

210E

+00

9.50

570E

+00

0.97

473

3.68

128E

+01

1.70

213E

+00

2.56

284E

+00

102

n,ga

mm

a 1.

7553

8E+0

2 1.

7110

0E+0

2 0.

9747

3 6.

6422

3E+0

2 2.

8398

9E-0

1 7.

7412

3E-0

4

Mat

eria

l(M

AT

)=96

28:C

m-2

41

00

1 T

otal

2.

8619

3E+0

3 2.

8642

0E+0

3 1.

0008

0 1.

4209

4E+0

3 7.

4912

3E+0

0 6.

0073

2E+0

0 00

2 E

last

ic

1.21

052E

+01

1.36

630E

+01

1.12

870

1.41

496E

+02

4.41

660E

+00

3.15

932E

+00

018

Fiss

ion

2.59

952E

+03

2.60

020E

+03

1.00

025

1.16

694E

+03

2.68

056E

+00

2.83

800E

+00

102

n,ga

mm

a 2.

5031

1E+0

2 2.

5039

0E+0

2 1.

0003

0 1.

1227

7E+0

2 2.

3578

0E-0

2 0.

0000

0E+0

0

Mat

eria

l(M

AT

)=96

31:C

m-2

42

00

1 T

otal

3.

2596

2E+0

1 3.

3958

0E+0

1 1.

0417

9 3.

0203

1E+0

2 8.

0950

5E+0

0 6.

1481

4E+0

0 00

2 E

last

ic

1.16

331E

+01

1.31

160E

+01

1.12

744

1.82

767E

+02

4.62

613E

+00

2.75

081E

+00

018

Fiss

ion

5.06

396E

+00

5.04

420E

+00

0.99

611

1.11

382E

+01

1.64

784E

+00

2.67

226E

+00

102

n,ga

mm

a 1.

5899

1E+0

1 1.

5799

0E+0

1 0.

9936

8 1.

0789

6E+0

2 3.

2330

0E-0

2 3.

8477

4E-0

5

Mat

eria

l(M

AT

)=96

34:C

m-2

43

00

1 T

otal

7.

5766

0E+0

2 7.

5905

0E+0

2 1.

0018

3 1.

8992

7E+0

3 7.

9933

3E+0

0 6.

2796

3E+0

0 00

2 E

last

ic

9.94

587E

+00

1.11

020E

+01

1.11

622

1.47

045E

+02

4.44

528E

+00

2.89

415E

+00

018

Fiss

ion

6.17

563E

+02

6.20

180E

+02

1.00

424

1.55

416E

+03

2.17

436E

+00

2.75

658E

+00

102

n,ga

mm

a 1.

3015

1E+0

2 1.

2777

0E+0

2 0.

9816

8 1.

9802

6E+0

2 1.

9372

3E-0

2 6.

9555

7E-0

5

Mat

eria

l(M

AT

)=96

37:C

m-2

44

00

1 T

otal

1.

7967

3E+0

1 1.

8844

0E+0

1 1.

0488

0 9.

2215

6E+0

2 7.

5618

5E+0

0 6.

6938

3E+0

0 00

2 E

last

ic

6.99

615E

+00

7.88

500E

+00

1.12

705

3.18

499E

+02

4.84

835E

+00

3.07

582E

+00

018

Fiss

ion

6.03

671E

-01

5.96

880E

-01

0.98

875

1.08

169E

+01

1.59

232E

+00

3.08

001E

+00

102

n,ga

mm

a 1.

0367

5E+0

1 1.

0362

0E+0

1 0.

9995

0 5.

9259

3E+0

2 1.

2689

1E-0

1 3.

0000

1E-0

3

Mat

eria

l(M

AT

)=96

40:C

m-2

45

00

1 T

otal

2.

5108

8E+0

3 2.

3776

0E+0

3 0.

9469

3 1.

0382

2E+0

3 7.

8803

0E+0

0 5.

7718

0E+0

0 00

2 E

last

ic

1.08

990E

+01

1.22

000E

+01

1.11

934

1.38

582E

+02

4.63

005E

+00

2.72

536E

+00

018

Fiss

ion

2.14

110E

+03

2.02

860E

+03

0.94

748

7.94

141E

+02

1.73

924E

+00

2.31

345E

+00

102

n,ga

mm

a 3.

5888

5E+0

2 3.

3678

0E+0

2 0.

9384

1 1.

0545

1E+0

2 8.

5564

2E-0

2 9.

5949

2E-0

4

127

Page 128: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=96

43:C

m-2

46

00

1 T

otal

1.

0682

9E+0

1 1.

1876

0E+0

1 1.

1117

2 2.

9104

2E+0

2 7.

9228

8E+0

0 5.

7142

4E+0

0 00

2 E

last

ic

9.22

731E

+00

1.04

130E

+01

1.12

854

1.71

938E

+02

4.84

050E

+00

2.72

817E

+00

018

Fiss

ion

1.44

196E

-01

1.44

550E

-01

1.00

246

4.72

170E

+00

1.21

329E

+00

1.89

824E

+00

102

n,ga

mm

a 1.

3113

5E+0

0 1.

3183

0E+0

0 1.

0053

3 1.

1398

9E+0

2 1.

0767

5E-0

1 1.

0000

1E-0

3

Mat

eria

l(M

AT

)=96

46:C

m-2

47

00

1 T

otal

1.

4777

3E+0

2 1.

4641

0E+0

2 0.

9907

5 1.

2758

6E+0

3 8.

0408

2E+0

0 5.

8073

9E+0

0 00

2 E

last

ic

8.79

213E

+00

9.87

380E

+00

1.12

303

1.40

990E

+02

4.87

505E

+00

2.75

132E

+00

018

Fiss

ion

8.17

765E

+01

7.98

630E

+01

0.97

661

6.00

584E

+02

1.90

942E

+00

2.53

913E

+00

102

n,ga

mm

a 5.

7204

3E+0

1 5.

6668

0E+0

1 0.

9906

3 5.

3423

8E+0

2 7.

6988

7E-0

2 1.

4823

6E-0

8

Mat

eria

l(M

AT

)=96

49:C

m-2

48

00

1 T

otal

9.

4684

5E+0

0 1.

0312

0E+0

1 1.

0891

3 5.

8723

2E+0

2 8.

0756

4E+0

0 5.

8289

9E+0

0 00

2 E

last

ic

6.52

770E

+00

7.36

510E

+00

1.12

829

3.15

874E

+02

5.37

627E

+00

2.76

539E

+00

018

Fiss

ion

3.70

031E

-01

3.70

410E

-01

1.00

101

1.12

763E

+01

1.23

979E

+00

2.68

000E

+00

102

n,ga

mm

a 2.

5707

2E+0

0 2.

5769

0E+0

0 1.

0023

9 2.

5972

7E+0

2 5.

4438

4E-0

2 1.

0494

0E-0

9

Mat

eria

l(M

AT

)=96

52:C

m-2

49

00

1 T

otal

2.

1193

6E+0

1 2.

2332

0E+0

1 1.

0537

3 3.

8544

5E+0

2 8.

0997

7E+0

0 6.

0084

7E+0

0 00

2 E

last

ic

9.20

178E

+00

1.03

850E

+01

1.12

854

1.67

732E

+02

4.29

340E

+00

2.67

397E

+00

018

Fiss

ion

1.02

332E

+01

1.01

890E

+01

0.99

570

1.55

007E

+02

2.10

511E

+00

2.36

769E

+00

102

n,ga

mm

a 1.

7586

5E+0

0 1.

7585

0E+0

0 0.

9999

0 6.

2259

0E+0

1 1.

3732

8E-0

2 8.

7596

0E-0

4

Mat

eria

l(M

AT

)=96

55:C

m-2

50

00

1 T

otal

1.

2494

8E+0

2 1.

2973

0E+0

2 1.

0382

8 1.

1108

1E+0

3 8.

1493

3E+0

0 6.

0092

7E+0

0 00

2 E

last

ic

3.95

898E

+01

4.45

380E

+01

1.12

498

8.06

468E

+02

4.93

756E

+00

2.71

391E

+00

018

Fiss

ion

2.08

910E

-03

2.09

140E

-03

1.00

112

7.65

082E

-02

1.52

016E

+00

2.16

040E

+00

102

n,ga

mm

a 8.

5356

5E+0

1 8.

5191

0E+0

1 0.

9980

6 3.

0384

4E+0

2 2.

3655

0E-0

2 4.

7516

7E-0

4

Mat

eria

l(M

AT

)=97

46:B

k-24

7

001

Tot

al

2.88

158E

+02

2.81

690E

+02

0.97

755

1.50

215E

+03

7.98

469E

+00

6.01

006E

+00

002

Ela

stic

1.

2348

0E+0

1 1.

3637

0E+0

1 1.

1043

8 1.

5848

2E+0

2 4.

6449

9E+0

0 2.

8016

0E+0

0 01

8 Fi

ssio

n 9.

1936

7E+0

1 8.

9351

0E+0

1 0.

9718

7 4.

4778

7E+0

2 9.

9787

9E-0

1 2.

2535

4E+0

0 10

2 n,

gam

ma

1.83

873E

+02

1.78

700E

+02

0.97

187

8.95

275E

+02

1.11

018E

-01

8.49

091E

-04

Mat

eria

l(M

AT

)=97

52:B

k-24

9

001

Tot

al

7.18

874E

+02

1.07

870E

+03

1.50

049

1.29

914E

+03

8.10

993E

+00

5.81

701E

+00

002

Ela

stic

3.

9347

3E+0

0 4.

6636

0E+0

0 1.

1852

5 1.

6856

5E+0

2 5.

0722

0E+0

0 2.

7468

4E+0

0 01

8 Fi

ssio

n 3.

9702

7E+0

0 5.

9595

0E+0

0 1.

5010

2 6.

4943

3E+0

0 9.

5548

3E-0

1 2.

6700

0E+0

0 10

2 n,

gam

ma

7.10

969E

+02

1.06

800E

+03

1.50

224

1.12

336E

+03

1.58

534E

-01

2.29

838E

-09

128

Page 129: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=97

55:B

k-25

0

001

Tot

al

1.32

407E

+03

1.25

280E

+03

0.94

615

8.45

482E

+02

8.15

285E

+00

5.82

051E

+00

002

Ela

stic

1.

2245

1E+0

1 1.

3509

0E+0

1 1.

1032

4 1.

4057

6E+0

2 4.

8357

7E+0

0 2.

7506

6E+0

0 01

8 Fi

ssio

n 9.

5864

2E+0

2 9.

0561

0E+0

2 0.

9446

8 5.

0569

6E+0

2 2.

0409

4E+0

0 2.

0764

9E+0

0 10

2 n,

gam

ma

3.53

184E

+02

3.33

650E

+02

0.94

468

1.98

892E

+02

3.24

960E

-02

8.02

854E

-09

Mat

eria

l(M

AT

)=98

52:C

f-24

9

001

Tot

al

2.17

580E

+03

2.10

850E

+03

0.96

909

3.03

201E

+03

8.09

670E

+00

6.01

349E

+00

002

Ela

stic

6.

2306

4E+0

0 6.

7676

0E+0

0 1.

0861

8 1.

2995

2E+0

2 4.

7357

9E+0

0 2.

9203

2E+0

0 01

8 Fi

ssio

n 1.

6652

8E+0

3 1.

6128

0E+0

3 0.

9684

6 2.

2082

8E+0

3 1.

7386

7E+0

0 2.

2892

2E+0

0 10

2 n,

gam

ma

5.04

289E

+02

4.89

010E

+02

0.96

970

6.93

734E

+02

1.66

645E

-01

8.55

210E

-04

Mat

eria

l(M

AT

)=98

55:C

f-25

0

001

Tot

al

1.95

119E

+03

1.96

020E

+03

1.00

463

9.18

706E

+03

8.15

380E

+00

5.83

854E

+00

002

Ela

stic

1.

6768

9E+0

2 1.

8465

0E+0

2 1.

1011

5 7.

4931

8E+0

2 5.

2843

0E+0

0 2.

7510

6E+0

0 01

8 Fi

ssio

n 4.

0905

9E+0

0 4.

0724

0E+0

0 0.

9955

5 1.

9363

3E+0

1 1.

8739

9E+0

0 2.

7213

3E+0

0 10

2 n,

gam

ma

1.77

941E

+03

1.77

150E

+03

0.99

555

8.41

801E

+03

9.96

477E

-02

4.96

617E

-07

Mat

eria

l(M

AT

)=98

58:C

f-25

1

001

Tot

al

8.19

537E

+03

8.17

050E

+03

0.99

697

6.80

460E

+03

7.91

474E

+00

5.77

377E

+00

002

Ela

stic

1.

2111

6E+0

1 1.

3854

0E+0

1 1.

1438

5 3.

0397

7E+0

2 4.

5816

4E+0

0 2.

6014

2E+0

0 01

8 Fi

ssio

n 5.

3215

9E+0

3 5.

3119

0E+0

3 0.

9981

7 4.

8870

9E+0

3 1.

7165

3E+0

0 2.

4000

0E+0

0 10

2 n,

gam

ma

2.86

167E

+03

2.84

480E

+03

0.99

412

1.61

349E

+03

7.80

842E

-02

1.00

000E

-03

Mat

eria

l(M

AT

)=98

61:C

f-25

2

001

Tot

al

6.37

779E

+01

6.46

940E

+01

1.01

437

3.29

341E

+02

7.84

384E

+00

5.74

373E

+00

002

Ela

stic

1.

1108

4E+0

1 1.

2507

0E+0

1 1.

1259

1 1.

7124

1E+0

2 4.

7200

8E+0

0 2.

6000

0E+0

0 01

8 Fi

ssio

n 3.

2175

5E+0

1 3.

1884

0E+0

1 0.

9909

3 1.

1102

9E+0

2 1.

8963

5E+0

0 2.

5292

9E+0

0 10

2 n,

gam

ma

2.04

940E

+01

2.03

040E

+01

0.99

072

4.70

546E

+01

4.18

569E

-02

8.00

008E

-04

Mat

eria

l(M

AT

)=98

67:C

f-25

4

001

Tot

al

1.71

212E

+01

1.84

900E

+01

1.07

996

1.97

600E

+02

8.30

810E

+00

5.85

843E

+00

002

Ela

stic

1.

0621

0E+0

1 1.

1988

0E+0

1 1.

1287

3 1.

7692

6E+0

2 5.

2653

2E+0

0 2.

7664

5E+0

0 01

8 Fi

ssio

n 2.

0000

5E+0

0 2.

0005

0E+0

0 1.

0002

2 1.

3834

4E+0

1 2.

1456

6E+0

0 2.

6478

1E+0

0 10

2 n,

gam

ma

4.50

015E

+00

4.50

140E

+00

1.00

028

6.48

603E

+00

6.65

454E

-03

2.33

501E

-09

Mat

eria

l(M

AT

)=99

13:E

s-25

3

001

Tot

al

2.10

995E

+02

2.22

680E

+02

1.05

539

6.99

419E

+03

9.76

273E

+00

9.76

000E

+00

002

Ela

stic

9.

8145

1E+0

0 1.

1018

0E+0

1 1.

1226

1 6.

8141

9E+0

2 9.

7623

1E+0

0 9.

7600

0E+0

0 10

2 n,

gam

ma

2.01

180E

+02

2.11

660E

+02

1.05

211

6.31

277E

+03

4.23

303E

-04

0.00

000E

+00

129

Page 130: The JEFF-3.1 Nuclear Data Library · of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data

Tab

le 9

. Sim

ple

inte

gral

neu

tron

cro

ss-s

ecti

on d

ata

from

JE

FF

-3.1

cal

cula

ted

wit

h th

e IN

TE

R c

ompu

ter

code

(co

nt.)

MT

R

eact

ion

(220

0 m

/s)

Avg

[1E

-5 t

o 10

] eV

G

fac

t (A

vg �

)/�

(E0)

A

vg r

es in

teg

[5E

-1 t

o 1E

+5] e

V

Avg

� f

iss

[1E

+3 t

o 2E

+7]

eV

� (

E14

) 1.

4E+7

eV

Mat

eria

l(M

AT

)=99

14:E

s-25

4

001

Tot

al

2.00

485E

+03

2.00

550E

+03

1.00

033

1.37

294E

+03

8.31

076E

+00

5.86

267E

+00

002

Ela

stic

1.

0621

0E+0

1 1.

1988

0E+0

1 1.

1287

3 1.

4811

3E+0

2 5.

1708

9E+0

0 2.

7664

5E+0

0 01

8 Fi

ssio

n 1.

9660

6E+0

3 1.

9666

0E+0

3 1.

0002

8 1.

2074

6E+0

3 2.

1846

9E+0

0 2.

2218

4E+0

0 10

2 n,

gam

ma

2.81

654E

+01

2.69

110E

+01

0.95

546

1.73

685E

+01

6.92

355E

-02

1.86

848E

-09

Mat

eria

l(M

AT

)=99

16:E

s-25

5

001

Tot

al

7.90

532E

+01

8.04

400E

+01

1.01

754

5.56

108E

+02

8.34

678E

+00

5.86

913E

+00

002

Ela

stic

1.

0620

9E+0

1 1.

1988

0E+0

1 1.

1287

2 1.

9520

5E+0

2 5.

2761

8E+0

0 2.

7707

5E+0

0 01

8 Fi

ssio

n 1.

3430

5E+0

1 1.

3435

0E+0

1 1.

0003

2 8.

2540

0E+0

1 2.

2350

6E+0

0 2.

7581

3E+0

0 10

2 n,

gam

ma

5.50

018E

+01

5.50

170E

+01

1.00

028

2.78

050E

+02

4.02

055E

-02

1.77

280E

-09

Mat

eria

l(M

AT

)=99

36:F

m-2

55

00

1 T

otal

3.

3967

3E+0

3 3.

3991

0E+0

3 1.

0006

9 1.

4339

4E+0

3 8.

3540

7E+0

0 5.

8733

7E+0

0 00

2 E

last

ic

1.06

209E

+01

1.19

880E

+01

1.12

872

1.69

072E

+02

5.13

490E

+00

2.77

075E

+00

018

Fiss

ion

3.36

011E

+03

3.36

110E

+03

1.00

029

1.16

353E

+03

2.32

759E

+00

2.36

716E

+00

102

n,ga

mm

a 2.

6000

8E+0

1 2.

6008

0E+0

1 1.

0002

8 1.

0125

2E+0

2 2.

0336

0E-0

2 4.

0442

9E-0

9

136 130