Published 2004
| Version v1
Book
MINERVE reactor characterization in support of the OSMOSE program: Safety parameters
Creators
- 1. CEA Cadarache, DEN/DER, 13108 Saint Paul lez Durance (France)
- 2. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
Description
The experimental results of safety parameters measurements in R1 - UO2 and R1 - MOX configurations of the MINERVE facility were described. The results were compared to calculations performed with the MCNP code with JEF2.2 and ENDF-BVI data libraries, and with the TRIPOLI4 code with JEF2.2. The consistency of calculation of the multiplication factor with the experiment for both R1 - UO2 and R1 - MOX was within about $1. The results show that the MCNP and TRIPOLI4 models developed for the R1 - UO2 and R1 - MOX configurations of the MINERVE facility provide consistent results with the experimental results for most of the safety parameters. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448683-7
- Imprint Pagination
- 21 p.
Conference
- Title
- The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
- Acronym
- PHYSOR 2004
- Dates
- 25-29 Apr 2004
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42097553
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; M CODES; MINERVE REACTOR; MIXED OXIDE FUELS; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; REACTOR CORES; SAFETY ANALYSIS; T CODES; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; COMPUTER CODES; DATA; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; INFORMATION; MATERIALS; NUCLEAR FUELS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; THERMAL REACTORS; TRANSPORT THEORY; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZERO POWER REACTORS
Optional Information
- Notes
- 5 refs.