New ENDF/B-V nuclear data library for WIMS-D4M
- Argonne National Lab., IL (United States)
- Univ. of Illinois, Urbana, IL (United States)
The WIMS-D4M code has been chosen by the Reduced Enrichment for Research and Test Reactor (RERTR) Program for all future research reactor cross-section generation replacing EPRI-CELL. A new 69-group 96-material library has been created for use in WIMS-D4M. The latest SUN version of NJOY (91.27) was used to generate the ENDF/B-V-based cross-section library. The library also includes ENDF/B-V based fission yields, energy fission and energy per capture data. The upper energy boundary has been extended from 10 to 20 MeV in order to model high energy neutron reactions. Additional fuel and moderator temperatures have been included to better predict temperature coefficients. More excess potential scattering points have been added to increase the accuracy of self-shielded resonance cross-sections. Several benchmark comparisons have been made to validate the new library.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10110224
- Report Number(s):
- ANL/EP/CP-81441; CONF-9310185-7; ON: DE94004585; TRN: 94:001510
- Resource Relation:
- Conference: 16. international meeting on reduced enrichment for research and test reactors (RERTR),Ibaraki (Japan),3-7 Oct 1993; Other Information: PBD: [1993]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
RESEARCH AND TEST REACTORS
REACTOR KINETICS
NUCLEAR DATA COLLECTIONS
W CODES
CROSS SECTIONS
BENCHMARKS
LIBRARIES
NEUTRON TRANSPORT
FISSION YIELD
FISSION
CAPTURE
NEUTRON REACTIONS
NUCLEAR FUELS
MODERATORS
VALIDATION
220600
990200
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
MATHEMATICS AND COMPUTERS