On the analysis method of effective delayed neutron fraction at thermal neutron systems
Creators
- 1. Research Reactor Inst., Kyoto Univ., Asashiro-Nishi 2, Kumatori-cho, Sennan-gun, Osaka 590-0494 (Japan)
Description
The effective delayed neutron fraction (beta-effective) was numerically analyzed with different analysis methods, and their effects on the results were investigated. The cores investigated in this study were light-water moderated low enriched UO2 lattices, of which the beta-effective had been reported. The effects of transport/diffusion calculation, energy group collapsing, and change of nuclear data library were studied. The study showed that the diffusion calculation with coarse group cross section gave smaller beta-effective than the transport one with fine group cross section, although the difference was not so large, about 2%. On the other hand, the change of nuclear data library from JENDL-3.3 to ENDF/B-VI.8 gave a significant difference, over than 4%. In comparisons with the experiments, it was indicated that the delayed neutron data in JENDL-3.3 are more reliable than those in ENDF/B-VI.8. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 6 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
- 43130029
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CROSS SECTIONS; DELAYED NEUTRON FRACTION; DELAYED NEUTRONS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; SLIGHTLY ENRICHED URANIUM; THERMAL NEUTRONS; URANIUM DIOXIDE; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; BARYONS; CHALCOGENIDES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM; EQUATIONS; EVALUATION; FERMIONS; FISSION NEUTRONS; HADRONS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON TRANSPORT THEORY; NEUTRONS; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT; REACTORS; TRANSPORT THEORY; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 7 refs.