Present status of JEFF-3.1 validation for fast reactors using the ERANOS-2.1 code system
Creators
- 1. CEA-Cadarache, DEN/DER/SPRC, 13108 Saint Paul Lez Durance (France)
Description
The latest release (2.1) of the ERANOS code system, using JEF-2.2, JEFF-3.1 and ENDF/B-VI r8 multigroup cross-section libraries is currently being validated on fast reactor critical experiments at CEA-Cadarache (France). This paper briefly presents the library effect studies and the detailed best-estimate validation studies performed up to now as part of the validation process. The library effect studies are performed over a wide range of experimental configurations, using simple model and method options. They yield global trends about the shift from JEF-2.2 to JEFF-3.1 cross-section libraries, that can be related to individual sensitivities and cross-section changes. The more detailed, best-estimate, calculations have been performed up to now over three experimental configurations carried out in the MASURCA critical facility at CEA-Cadarache: two cores with a softened spectrum due to large amounts of graphite (MAS1A' and MAS1B), and a core representative of sodium-cooled fast reactors (CIRANO ZONA2A). Calculated values have been compared to measurements, and discrepancies analyzed in detail using perturbation theory. Values calculated with JEFF-3.1 were found to be within 3 standard deviations of the measured values, and at least of the same quality as the JEF-2.2 based results. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 8 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
- 43130109
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CEA CADARACHE; COMPARATIVE EVALUATIONS; CROSS SECTIONS; E CODES; EXPERIMENTAL DATA; GRAPHITE; MASURCA REACTOR; NEUTRON SPECTRA; NUCLEAR DATA COLLECTIONS; PERTURBATION THEORY; REACTOR CORES; SENSITIVITY ANALYSIS; SODIUM COOLED REACTORS; THEORETICAL DATA; VALIDATION
- Descriptors DEC
- AIR COOLED REACTORS; CARBON; CEA; COMPUTER CODES; DATA; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FAST REACTORS; FRENCH ORGANIZATIONS; GAS COOLED REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; MINERALS; NATIONAL ORGANIZATIONS; NONMETALS; NUMERICAL DATA; PLUTONIUM REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SPECTRA; TESTING; ZERO POWER REACTORS
Optional Information
- Notes
- 7 refs.