The MNP analysis of BWR-simulated critical experiments with ENDF/B-VI.2 and JEF-2.2

Journal Article · Sun Dec 31 04:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:411804

Kim, Jung-Do; Gil, Choong-Sup ^[1]

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1. Korea Atomic Energy Research Institute, Daejon (Korea, Democratic People`s Republic of)

In the past few years, a number of new revisions of major evaluated nuclear data files such as ENDF/B-VI.2, JEF-2.2, JENDL-3.2, and BROND-2.2 have been released and validated through analyses of the Cross-Section Evaluation Working Group benchmarks at room temperature. Sitaraman and Rahnemal reported the detailed specifications for two sets of criticals, which were made up of actual power reactor fuel bundles in critical configurations at both room and operating temperatures. This paper describes two sets of boiling water reactor simulated experiments at temperatures representative of cold as well as operating conditions analyzed by the MCNP-4a codes with continuous energy pointwise cross-section data.

• OSTI ID: 411804
• Report Number(s): CONF-951006--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
66 PHYSICS
BENCHMARKS
BWR TYPE REACTORS
CROSS SECTIONS
FUEL ASSEMBLIES
M CODES
MULTIPLICATION FACTORS
NUCLEAR DATA COLLECTIONS
REACTOR CORES