Benchmarking of the characteristics method combined with advanced self-shielding models on BWR-MOX assemblies
Conference
·
OSTI ID:22039720
- Ecole Polytechnique de Montreal, C.P. 6079 succ. Centre-Ville, Montreal, H3C 3A7 (Canada)
- CEA Cadarache DEN/DER/SPRC, Bldg. 230, 13108 Saint Paul-lez-Durance (France)
Calculations based on the characteristics method and different self-shielding models are presented for 9 x 9 BWR assemblies fully loaded with MOX fuel. The geometry of these assemblies was recovered from the BASALA experimental program implemented in the EOLE facility at CEA Cadarache. We have focused our study on two configurations, a 'hot case' simulating hot operation conditions and a 'cold case' with a cruciform control blade filled with B{sub 4}C poisoned rods. A parametric study was carried out with respect to the spatial discretization, the tracking parameters and the anisotropy order. Comparisons with Monte-Carlo calculations in terms of k{sub eff}, radiative capture and fission rates were performed in order to validate the computational tools. The results are in good agreement between the stochastic and deterministic approaches. The mutual self-shielding model recently introduced within the framework of the Ribon extending self-shielding method appears as useful for this type of assemblies. Indeed, in the calculation of these MOX benchmarks, the overlapping of resonances especially between {sup 238}U and {sup 240}Pu plays an important role due to the spectral strengthening of the flux as the voiding percentage is increased. The method of characteristics and the developed acceleration strategies are shown to be adequate to perform accurate calculations for these configurations handling a fine spatial discretization. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22039720
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
BORON CARBIDES
BWR TYPE REACTORS
CEA CADARACHE
COMPARATIVE EVALUATIONS
CONTROL ELEMENTS
DETERMINISTIC ESTIMATION
EOLE REACTOR
FISSION
FUEL ASSEMBLIES
MIXED OXIDE FUELS
MONTE CARLO METHOD
MULTIPLICATION FACTORS
PARAMETRIC ANALYSIS
PLUTONIUM 240
SELF-SHIELDING
STOCHASTIC PROCESSES
URANIUM 238
BENCHMARKS
BORON CARBIDES
BWR TYPE REACTORS
CEA CADARACHE
COMPARATIVE EVALUATIONS
CONTROL ELEMENTS
DETERMINISTIC ESTIMATION
EOLE REACTOR
FISSION
FUEL ASSEMBLIES
MIXED OXIDE FUELS
MONTE CARLO METHOD
MULTIPLICATION FACTORS
PARAMETRIC ANALYSIS
PLUTONIUM 240
SELF-SHIELDING
STOCHASTIC PROCESSES
URANIUM 238