Contribution to the validation of JEF2 actinide nuclear data. Analysis of fuel and sample irradiation experiments in PHENIX
Creators
- 1. CEA Centre d'Etudes de Cadarache, 13 -Saint-Paul-lez-Durance (France). Service de Physique des Reacteurs et du Cycle
Description
In connection with Plutonium recycling and radioactive waste transmutation studies envisaged in fast power reactors, there is a need for further improvements in the nuclear data for major and minor actinides. Multigroup and multitemperature libraries have been produced from the JEF2 evaluations for all isotopes including the most important actinides (U, Pu) and also the minor actinides (Np, Am, Cm) for which transmutation is being envisaged. The validation of these libraries is currently underway. It is based both on: 1) analyses of a wide range of integral experiments performed in fast and thermal configurations, 2) sensitivity studies of these integral parameters to the nuclear data, allowing the adjustment of the cross-sections, by a statistical approach. In this paper, we present a contribution to the validation of the JEF2 data, based on the reanalysis of sample and fuel pin irradiation experiments carried out in the PHENIX reactor: the PROFIL and TRAPU experiments. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- International conference on future nuclear systems. Challenge towards second nuclear era with advanced fuel cycles. Proceedings
- Imprint Pagination
- 1588 p.
- Journal Page Range
- p. 1332-1337.
Conference
- Title
- International conference on future nuclear systems.
- Acronym
- Global '97
- Dates
- 5-10 Oct 1997.
- Place
- Yokohama (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29033434
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BENCHMARKS; CAPTURE-TO-FISSION RATIO; CROSS SECTIONS; EXPERIMENTAL DATA; FAST FISSION; FUEL ASSEMBLIES; NUCLEAR DATA COLLECTIONS; PHENIX REACTOR; PLUTONIUM 240 TARGET; PLUTONIUM 241 TARGET; RECYCLING; TRANSMUTATION; URANIUM 235 TARGET; URANIUM 238 TARGET
- Descriptors DEC
- BARYON REACTIONS; BREEDER REACTORS; DATA; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FISSION; HADRON REACTIONS; INFORMATION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NEUTRON REACTIONS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; TARGETS
Optional Information
- Notes
- Imprint:Published in 2 volumes.