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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
- - 22 - -
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
- - 33 - -
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
- - 44 - -
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
- - 55 - -
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.
- - 66 - -
Auxiliary Tools To ease NJOY input generation and running Simple Linux script file, ANJOYMC, NIM
- - 77 - -
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)
- - 88 - -
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
- - 1111 - -
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
- - 1212 - -
Multi-Group Libraries for PWR Core Analysis (SNU) Whole core analysis transport code, nTRACER Application to PWR and SMART reactor developments
- - 1313 - -
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
- - 1414 - -
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