Preliminary evaluation of the Compact Nuclear Power Source (CNPS) critical experiments as a VHTR physics benchmark
Creators
- 1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
- 2. Korea Atomic Energy Research Inst., P. O. Box 105, Yuseong-Gu, Daejon (Korea, Republic of)
Description
An evaluation of the Compact Nuclear Power Source (CNPS) experiments conducted at the Los Alamos National Laboratory (LANL) in the 1980's has been done using information available in the open literature. The Monte Carlo results for critical test configurations have been quite good with keff values within 0.5% of the critical value of unity. The calculated total and differential rod and material worths were found generally close to measurement values. The lack of information on design data uncertainties and the inconsistency in the design data from different sources make it difficult to quantify the uncertainty in the core integral parameters arising from data uncertainties. The evaluated configurations could however be useful as numerical benchmarks that are based on the currently available information. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 10 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43130098
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; DATA ACQUISITION; DESIGN; EVALUATION; LANL; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NUCLEAR PHYSICS; NUCLEAR POWER; REACTIVITY WORTHS; REACTOR CORES; VHTR REACTOR
- Descriptors DEC
- CALCULATION METHODS; DIMENSIONLESS NUMBERS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; NATIONAL ORGANIZATIONS; PHYSICS; POWER; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; US DOE; US ORGANIZATIONS
Optional Information
- Notes
- 5 refs.