Published 2006
| Version v1
Book
Validation tests of the multigroup cross section libraries for fast reactors
Creators
- 1. Korea Atomic Energy Research Inst., P.O. Box 105, Yuseong, Daejeon 305-600 (Korea, Republic of)
Description
The MATXS-format 150-group neutron libraries for fast reactors were generated based on the ENDF/B-VII beta 0, JEFF-3.1, and JENDL-3.3. The libraries have been validated through the 18 fast benchmark experiments from the CSEWG benchmark specifications and BFS critical assemblies. The keff's and several central spectral indices obtained by the DANTSYS code have been compared with the results of the experiments and MCNPX. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 7 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
- 43129962
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BFS REACTOR; CROSS SECTIONS; D CODES; MONTE CARLO METHOD; MULTIGROUP THEORY; MULTIPLICATION FACTORS; NEUTRONS; NUCLEAR DATA COLLECTIONS; VALIDATION
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FERMIONS; HADRONS; NEUTRON TRANSPORT THEORY; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; TRANSPORT THEORY; ZERO POWER REACTORS
Optional Information
- Notes
- 5 refs.