A comparison of WIMS-D4 and WIMS-D4m generated cross-section data with Monte Carlo

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:6909143

Woodruff, W L; Deen, J R ^[1]; Costescu, C I ^[2]

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1. Argonne National Lab., IL (United States)
2. Illinois Univ., Urbana, IL (United States)

Cross-section and related data generated by a modified version of the WIMS-D4 code for both plate and rod type research reactor fuel are compared with Monte Carlo data from the VIM code. The modifications include the introduction of a capability for generating broad group microscopic data and to write selected microscopic cross-sections to an ISOTXS file format. The original WIMS-D4 library with H in ZrH, and [sup 166]Er and [sup 167]Er added gives processed microscopic cross-section data that agree well with VIM ENDF/B-V based data for both plate and TRIGA cells. Additional improvements are in progress including the capability to generate an ENDF/B-V based library.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6909143
• Report Number(s): ANL/EP/CP-77800; CONF-9209266-4; ON: DE93002933
• Resource Relation: Conference: 1992 international meeting on reduced enrichment for research and test reactors, Roskilde (Denmark), 27 Sep - 1 Oct 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CROSS SECTIONS
W CODES
NEUTRON REACTIONS
COMPARATIVE EVALUATIONS
ERBIUM ISOTOPES
MONTE CARLO METHOD
NUCLEAR FUELS
SHIELDING
TRIGA TYPE REACTORS
BARYON REACTIONS
CALCULATION METHODS
COMPUTER CODES
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EVALUATION
FUELS
HADRON REACTIONS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
ISOTOPES
MATERIALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
RARE EARTH ISOTOPES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* - Nuclear Reactor Technology- Theory & Calculation
990200 - Mathematics & Computers