Current Status of Nuclear Data Processing Activities Current Status of Nuclear Data Processing Activities at KAERIat KAERI

Do Heon KIMDo Heon KIM

Korea Atomic Energy Research InstituteKorea Atomic Energy Research Institute

Consultants’ Meeting on

“The New Evaluated Nuclear Data File Processing Capabilities”

October 5-9, 2015

IAEA Headquarters, Vienna, Austria

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IntroductionIntroduction ACE-Format LibraryACE-Format Library MATXS-Format LibraryMATXS-Format Library Covariance Data LibraryCovariance Data Library PWR Core Analysis Code LibraryPWR Core Analysis Code Library Nuclear Decay and FP Yield LibraryNuclear Decay and FP Yield Library SummarySummary

CONTENTSCONTENTS

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IntroductionIntroduction

Roles of NDC, KAERI Generate several kinds of XS libraries for radiation

transport/depletion codes such as MCNP/MCNPX, DANTSYS, DOORS, WIMS-D, and ORIGEN

Disseminate them to many researchers in domestic and foreign institutions

Fulfil nuclear data needs for R&D activities on advanced reactors

Verify and validate our new evaluated data Nuclear Data Processing

No complete ND processing code package NJOY99, NJOY2012, ERRORJ, AMPX, PREPRO Auxiliary tools to ease NJOY processing and generate

unique XS libraries for our own transport/depletion codes

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KAERI/NDC (KN)-Series of ACE Libraries MCNP/MCNPX, McCARD NJOY99/NJOY2012 As release of new source evaluated files Application to various reactor developments (KALIMER,

SMART, VHTR, Research Reactors, etc.) http://atom.kaeri.re.kr

ACE-Format LibraryACE-Format Library

KN Library Source Data Temperature Note

MCLIB-E6 ENDF/B-VI.5 300K, 600K, 900K NEA-1651

KNE62, KNE68, KNE70, KNE71

ENDF/B-VI.2, VI.8, VII.0, VII.1 293.6K

KNF30, KNF31, KNF311, KNF312, KNF32

JEFF-3.0, 3.1, 3.1.1, 3.1.2, 3.2 293.6K

KNJ33, KNJ40, KNJAC08 JENDL-3.3, 4.0, JENDL/AC-2008 293.6K

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Multi-Temperature ACE Libraries Reaction XS and thermal scattering libraries at certain

temperatures, upon request Analysis of reactivity coefficients for VHTR, Research

Reactors, etc. Cold neutron analysis for Hanaro research reactor

On-The-Fly Doppler Broadening (DB) Traditional XS treatments for precise temperature analyses

require a lot of ACE libraries at different temperatures. Huge memory size requirement Leal-Hwang DB and SIGMA1 Kernel Broadening methods

have been implemented in McCARD and tested with initial XS libraries at 0K and 300K.

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Auxiliary Tools To ease NJOY input generation and running Simple Linux script file, ANJOYMC, NIM

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Shielding Libraries DANTSYS, DOORS NJOY97/NJOY99 Temperatures of 300, 600, 1000, and 2100K Application to various reactor shielding calculations

MATXS-Format LibraryMATXS-Format Library

Library Source Data Energy Group Note

KASHIL-E6 ENDF/B-VI.5 Neutron 175G, Photon 42G NEA-1649

KASHIL-E68 ENDF/B-VI.8 Neutron 199G, Photon 42G

KASHIL-E70 ENDF/B-VII.0

Neutron 199G, Photon 42GNeutron 175G, Photon 42GNeutron 80G, Photon 24GNeutron 47G, Photon 20GNeutron 44G, Photon 18GNeutron 30G, Photon 12G

NEA-1818

KASHIL-F31 JEFF-3.1.1 Neutron 199G, Photon 42G

KASHIL-J33 JENDL-3.3 Neutron 199G, Photon 42G

ENDF/B-VII.0(Neutron)

RECONR

BROADR

HEATR

UNRESR

PENDF(Neutron)

GROUPR

GENDF(Neutron)

MATXSR

MATXS-Format 30-G Library

ENDF/B-VII.0(Photon)

RECONR

PENDF(Photon)

GAMINR

GENDF(Photon)

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Fast Reactor Libraries DANTSYS NJOY94/NJOY99 Weighting function of KALIMER-150 core flux Temperatures of 300, 600, 900, and 1200K Application to various fast reactor analyses (KALIMER)

Library Source Data Energy Group Note

KAFAX-F22 JEF-2.2 Neutron 80G, Photon 24G NEA-1650

KAFAX-E66 ENDF/B-VI.6 Neutron 150G, Photon 12G

KAFAX-E70 ENDF/B-VII.0 Neutron 150G, Photon 12G NEA-1815

KAFAX-E71 ENDF/B-VII.1 Neutron 150G, Photon 12G

KAFAX-F31 JEFF-3.1 Neutron 150G, Photon 12G NEA-1816

KAFAX-J33 JENDL-3.3 Neutron 150G, Photon 12G NEA-1817

KAFAX-JAC08 JENDL/AC-2008 Neutron 150G, Photon 12G

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ISOTXS-Format microscopic XS Libraries MUST (Multi-group Unstructured geometry SN Transport)

Code TRANSX post-processing of KASHIL libraries Temperatures of 300, 600, 1000, and 2100K

Supplementation of KAFAX Ultrafine energy group XS treatment to correct resonance

overlap effect Self-shielded XS treatment in URR

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COVFIL-Format Covariance Libraries DANTSYS/SUSD3D, McCARD, TSUNAMI NJOY99, ERRORJ, PUFF-IV Estimation of ND uncertainties to k-eff

Covariance Data LibraryCovariance Data Library

DANTSYSNJOY

(ERRORR)

(44g)

*, GENDF(44g)

COVFIL(44g)

SUSD3D

ENDF

NJOYTRANSX

ISOTXS(44g)

Library Source Data Energy Group Note

GCovar-J33r Revision of JENDL-3.3 Neutron 44G, Neutron 30G

GCovar-J40GCovar-J40u

JENDL-4.0JENDL-4.0 Update

Neutron 44G, Neutron 33GNeutron 44G

GCovar-E71 ENDF/B-VII.1 Neutron 44G

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Multi-Group Libraries for PWR Core Analysis (KAERI) Whole core analysis transport code, DeCART Transport lattice transport codes, LIBERTE & KARMA Application to PWR and SMART reactor developments

PWR Core Analysis Code LibraryPWR Core Analysis Code Library

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Multi-Group Libraries for PWR Core Analysis (SNU) Whole core analysis transport code, nTRACER Application to PWR and SMART reactor developments

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Nuclear Decay & Fission-Product Yield Libraries for SCALE-6.1.3 Burnup/Depletion Module ORIGEN-S In-house processing tool Application to decay heat estimation after a fission event

Nuclear Decay and FP Yield LibraryNuclear Decay and FP Yield Library

FP Yield Library Source Data No. of Fissionable Note

YLD-E70 ENDF/B-VII.0 30

YLD-E71 ENDF/B-VII.1 30

YLD-J40 JENDL-4.0 30

YLD-JFPY2011 JENDL/FPY-2011 30

YLD-F311 JEFF-3.1.1 19

YLD-K00 KAERI 3 U-235, U-238, Pu-239

Decay Library Source Data No. of FPs Note

Dec-E71 ENDF/B-VII.1 2238

Dec-K00 KAERI 24 Mass chains 72 & 144

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SummarySummary

Nuclear Data Processing Activities at KAERI ACE-format library MATXS-format library Covariance data library PWR core analysis code library Nuclear decay and FP yield library

Suggestion Inclusion of capability to deal with ultrafine energy groups in

resonance range• Enable to perform more accurate resonance treatment

• Useful for practical reactor core design/analysis applications