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  • CSEWG Document ENDF-102

    Report BNL-203218-2018-INRE SVN Commit: Revision 215

    ENDF-6 Formats Manual

    Data Formats and Procedures for the Evaluated Nuclear Data Files

    ENDF/B-VI, ENDF/B-VII and ENDF/B-VIII

    Written by the Members of the Cross Sections Evaluation Working Group

    Edited by A. Trkov, M. Herman and D. A. Brown

    With contributions from N. Holden and G. Hedstrom

    February 1, 2018

    National Nuclear Data Center Brookhaven National Laboratory

    Upton, NY 11973-5000 www.nndc.bnl.gov

    Notice: This manuscript has been authored by employees of Brookhaven Science Associates, LLC under Contract No. DE-

    SC0012704 with the U.S. Department of Energy. The publisher by accepting the manuscript for publication acknowledges that

    the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the

    published form of this manuscript, or allow others to do so, for United States Government purposes.

  • DISCLAIMER

    This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the ac- curacy, completeness, or any third party’s use or the results of such use of any information, apparatus, product, or process disclosed, or represents that its use would not infringe pri- vately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

  • PREFACE TO THE 2018 EDITION

    In December 2006 and again in December 2011, the Cross Section Evaluation Working Group (CSEWG) of the United States released new versions of the ENDF/B-VII library. Each major release with minor revision number “0” coincides with the release of a new Neutron Standards Library. In December 2017, CSEWG released a new major version of ENDF/B, ENDF/B-VIII.0, again coinciding with the release of the Neutron Stanards Library. This ENDF release also contains the results of the Collaborative International Evaluation Library Organization (CIELO) Pilot Project, namely standards level full evaluations of 1H, 16O, 56Fe, 235U, 238U and 239Pu. It is our expectation that this major revision will be embraced by the data evaluators as well as members of numerous nuclear data user communities worldwide.

    With each release, CSEWG has released a new revision of the ENDF-6 formats man- ual. Although ENDF/B-VIII.0 uses the same ENDF-6 format as the previous three major library releases (ENDF/B-VII.1, ENDF/B-VII.0 and ENDF/B-VI), there have been many corrections and clarifications to the manual as well as a few minor additions to the ENDF-6 format. These additions include:

    • Simplified equations for charged-particle interpolation rule INT=6 (Chapter 0.5.2)

    • Line numbering optional (Chapter 0.5)

    • Explain notation for ENDF formats and relation to punch-card history (Chapter 0.6)

    • Clarify allowed number formats (Chapter 0.6.2)

    • Define allowed ASCII characters in TEXT records (Chapter 0.6.4.1)

    • New tabular form for fission energy release (Chapter 1.4)

    • Q values now computed using atomic masses (Chapter 3.3.2)

    • P (ν|E) for fission photons and neutrons (Chapter 6)

    • Kalbach interpolation fix (Chapter 6)

    • Provision for sub-actinide fission (Chapters 8, 10 and 40)

    • Rewritten chapter on atomic form factors or scattering functions (Chapter 27)

    • Clarified MAT numbers for TSL data (Appendix C)

    • New kinematics discussion (Appendix E)

    • CODATA2010 constants (Appendix I)

    • Various clarifications and minor revisions

  • In the early stage of work on the VII-th generation of the library CSEWG made important decision to use the same formats. This decision was adopted even though it was argued that it would be timely to modernize the formats and several interesting ideas were proposed. After careful deliberation CSEWG concluded that actual implementation would require considerable resources needed to modify processing codes and to guarantee high quality of the files processed by these codes. The transition to a new format, the Generalized Nuclear Database Structure (GNDS), is now underway. CSEWG determined that this ENDF/B-VIII.0 release will be released in both the ENDF-6 format and in the GNDS format. Despite this development, we anticipate a lengthy transition period in which data is released simultaneously in the legacy ENDF-6 format and in the new GNDS format.

    Many thanks are due to numerous CSEWG members and international colleagues for their useful comments and observations on several draft versions. We especially want to thank all those who provided comments and corrections on this latest version of the format manual, in particular C. Lubitz, A. Kahler, N. Larson, J. C. Sublet, T. Kawano, D. Smith, G. Hedstrom, B. Beck, C. Mattoon, P. Romano and A. Koning. We also want to stress that even though the Manual is maintained by the CSEWG collaboration in the United States, active contribution from the international data community is essential for achieving its high quality.

    Upton, February 2018 Andrej Trkov Michal Herman David Brown

    II

  • Contents

    Preface to the 2018 Edition I

    0 INTRODUCTION 1 0.1 Introduction to the ENDF-6 Format . . . . . . . . . . . . . . . . . . . . . . 1 0.2 Philosophy of the ENDF System . . . . . . . . . . . . . . . . . . . . . . . . 1

    0.2.1 Evaluated Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0.2.2 ENDF/B Library . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0.2.3 Choices of Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0.2.4 Experimental Data Libraries . . . . . . . . . . . . . . . . . . . . . . 3 0.2.5 Processing Codes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 0.2.6 Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 0.2.7 Documentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

    0.3 General Description of the ENDF System . . . . . . . . . . . . . . . . . . . 4 0.3.1 Library (NLIB, NVER, LREL, NFOR) . . . . . . . . . . . . . . . . 4 0.3.2 Incident Particles and Data Types (NSUB) . . . . . . . . . . . . . . 4

    0.3.2.1 Incident-Neutron Data (NSUB=10) . . . . . . . . . . . . . 7 0.3.2.2 Thermal Neutron Scattering (NSUB=12) . . . . . . . . . . 8 0.3.2.3 Fission Product Yield Data . . . . . . . . . . . . . . . . . . 8 0.3.2.4 Radioactive Decay Data (NSUB=4) . . . . . . . . . . . . . 9 0.3.2.5 Charged-Particle (NSUB≥10010) and

    Photo-Nuclear (NSUB=0) Sub-libraries . . . . . . . . . . . 9 0.3.2.6 Photo-Atomic Interaction Data (NSUB=3) . . . . . . . . . 10 0.3.2.7 Electro-Atomic Interaction Data (NSUB=113) . . . . . . . 10 0.3.2.8 Atomic Relaxation Data (NSUB=6) . . . . . . . . . . . . . 10

    0.4 Contents of an ENDF Evaluation . . . . . . . . . . . . . . . . . . . . . . . . 10 0.4.1 Material (MAT, MOD) . . . . . . . . . . . . . . . . . . . . . . . . . 11 0.4.2 ENDF Data Blocks (Files - MF) . . . . . . . . . . . . . . . . . . . . . 12 0.4.3 Reaction Nomenclature (MT) . . . . . . . . . . . . . . . . . . . . . . 13

    0.4.3.1 Elastic Scattering . . . . . . . . . . . . . . . . . . . . . . . 13 0.4.3.2 Simple Single Particle Reactions . . . . . . . . . . . . . . . 13 0.4.3.3 Simple Multi-Particle Reactions . . . . . . . . . . . . . . . 14 0.4.3.4 Breakup Reactions . . . . . . . . . . . . . . . . . . . . . . . 15 0.4.3.5 Complex Reactions . . . . . . . . . . . . . . . . . . . . . . 19 0.4.3.6 Radiative Capture . . . . . . . . . . . . . . . . . . . . . . . 19

    i

  • CONTENTS

    0.4.3.7 Fission . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 0.4.3.8 Nonelastic Reaction for Photon Production . . . . . . . . . 20 0.4.3.9 Special Production Cross Sections . . . . . . . . . . . . . . 20 0.4.3.10 Auxiliary MT Numbers . . . . . . . . . . . . . . . . . . . . 20 0.4.3.11 Sum Rules for ENDF . . . . . . . . . . . . . . . . . . . . . 21

    0.5 Representation of Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 0.5.1 Definitions and Conventions . . . . . . . . . . . . . . . . . . . . . . . 21

    0.5.1.1 Atomic Masses Versus Nuclear Masses . . . . . . . . . . . . 23 0.5.2 Interpolation Laws . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

    0.5.2.1 One-dimensional Interpolation Schemes . . . . . . . . . . . 23 0.5.2.2 Two-Dimensional Interpolation Schemes . . . . . . . . . . . 25

    0.6 General Description of Data Formats . . . . . . . . . . . . . . . . . . . . . . 28 0.6.1 Symbol Nomenclature . . . . . . . . . . . . . . . . . . . . . . . . . . 29 0.6.2 Representing Numbers in ENDF . . . . . . . . . . . . . . . . . . . . 30 0.6.3 Structure of an ENDF Data Tape . . . . . . . . . . . . . . . . . . . 30 0.6.4 Types of Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31

    0.6.4.1 TEXT Records . . . . . . . . . . . . . . . . . . . . . . . . . 31 0.6.4.2 CONT Records . . . . . . . . . . . . . . . . . . . . . . . . . 32 0.6.4.3 HEAD Records . . . . . . . . . . . . . . . . . . . .