Testing WIMS-D4M cross sections and the ANL ENDF/B-V 69 group library. Results from global diffusion and Monte Carlo calculations compared with measurements in the Romanian 14-MW TRIGA reactor

Conference · Fri Dec 31 04:00:00 EST 1993

OSTI ID:10110320

Bretscher, M M

The WIMS-D4 code has been modified (WIMS-D4M) to produce microscopic isotopic cross sections in ISOTXS format for use in diffusion and transport calculations. Beginning with 69-group libraries based on ENDF/B-V data, numerous cell calculations have been made to prepare a set of broad group cross sections for use in diffusion calculations. Global calculations have been made for two control rod states of the Romanian steady state TRIGA reactor with 29 fresh HEU fuel clusters. Detailed Monte Carlo calculations also have been performed for the same reactor configurations using data based on ENDF/B-V. Results from these global calculations are compared with each other and with the measured excess reactivities. Although region-averaged macroscopic principal cross sections obtained from WIMS-D4M are in good agreement with the corresponding Monte Carlo values, problems exist with the high energy (E > 10 keV) microscopic hydrogen transport cross sections.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10110320
• Report Number(s): ANL/EP/CP--81422; CONF-9310185--6; ON: DE94004612
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
990200
COMPARATIVE EVALUATIONS
CONTROL ELEMENTS
CROSS SECTIONS
DIFFUSION
HIGHLY ENRICHED URANIUM
LIBRARIES
MATHEMATICS AND COMPUTERS
MODIFICATIONS
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
REACTIVITY
REACTOR KINETICS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
TESTING
TRIGA TYPE REACTORS
W CODES