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Benchmarking of MCNP Against B&W LRC Core XI Critical Experiments

Conference ·
OSTI ID:100102
 [1]
  1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
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The MCNP Monte Carlo code and its ENDF/B-V continuous-energy cross- section library previously has been benchmarked against a variety of critical experiments, and that benchmarking recently has been extended to include its ENDF/B-VI continuous-energy cross-section library and additional critical experiments. This study further extends the benchmarking of MCNP and its two continuous-energy libraries to 17 large-scale mockup experiments that closely resemble the core of a pressurized water reactor (PWR). The experiments were performed at Babcock & Wilcox`s Lynchburg Research Center in 1970 and 1971. The series was designated as Core XI, and the individual experiments were characterized as different "loadings." The experiments were performed inside a large aluminum tank that contained borated water. The water height for each loading was exactly 145 cm, and the soluble boron concentration in the water was adjusted until the configuration was slightly supercritical, with a value of 1.0007 for keff. Pin-by-pin power distributions were measured for several of the loadings.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
100102
Report Number(s):
LA-UR--95-1899; CONF-951006--15; ON: DE95015251
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
99 GENERAL AND MISCELLANEOUS
BENCHMARKS
CRITICALITY
CROSS SECTIONS
ENDF/B-V Continuous-Energy Cross-Section Library
M CODES
MCNP Monte Carlo Code
MOCKUP
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
REACTOR CORES
REACTOR PHYSICS
REACTOR SAFETY
TESTING
VERIFICATION