The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility
スポンサーリンク
概要
- 論文の詳細を見る
A detailed MCNPX (version 2.4.0) model of the CROCUS zero-power critical facility was used to investigate the effect of nuclear data on the analysis of reactivity perturbations caused by variations in the moderator level. The analysis was performed using the ENDF/B-VI (Release 0), ENDF/B-V, JEF-2.2 and JENDL-3.2 cross-section libraries, and compared with experimental values derived from period measurements. The results of this study demonstrate that predictions of the reactivity effects of moderator-level variations are largely independent of the nuclear data evaluation even when the associated keff values vary significantly.
- 2003-06-25
著者
-
CHAWLA Rakesh
Paul Scherrer Institute
-
Chawla Rakesh
Paul Scherrer Institut
-
LEBENHAFT Julian
Paul Scherrer Institute
-
FRUH Rene
Swiss Federal Institute of Technology (EPFL)
関連論文
- Experimental Validation of Reaction Rate Distributions for a SVEA-96+ BWR Assembly with Hafnium Control Blades
- Experimental Validation of Channel Bowing Effects on Pin Power Distributions in a Westinghouse SVEA-96+ Assembly
- Comparisons of Deterministic Neutronic Calculations with Monte Carlo Results for an Advanced BWR Fuel Assembly with Hafnium Control Blades
- The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility
- Investigation of ADS-Type Heterogeneities in the MUSE4 Critical Configuration
- Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients
- Interpretation of High-Burnup Fuel Annealing Tests
- Statistical Uncertainty Analysis Applied to Fuel Depletion Calculations
- The Effect of Nuclear Data on the MCNPX Modeling of Moderator Level Variations in the CROCUS Critical Facility