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Author Mosteller, R. D.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ PHYSICS ♦ PWR TYPE REACTORS ♦ REACTOR CORES ♦ M CODES ♦ BENCHMARKS ♦ NUCLEAR DATA COLLECTIONS ♦ CROSS SECTIONS ♦ MULTIPLICATION FACTORS ♦ FUEL ASSEMBLIES
Abstract The MCNP Monte Carlo code and its ENDF/B-V continuous-energy cross-section library previously has been benchmark against a variety of critical experiments, and that benchmarking recently has been extended to include its ENDF/B-VI continuous-energy cross-section library (which is based on ENDF/B-VI Release 2) 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 the pressurized water reactor (PWR).
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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