Open Access
ND 2007
Article Number 223
Number of page(s) 4
Section Benchmarking for fission applications
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07466

Nuclear data impact on multiplication factor and reactor physics parameters calculation for experiments simulating damp MOX powders

T. Ivanova, I. Duhamel, S. Evo and E. Létang

Institut de Radioprotection et de Sûreté Nucléaire, BP. 17, 92262 Fontenay-aux-Roses, France

Published online: 21 May 2008

The paper presents calculation results for experiments performed to address needs of the MOX fuel manufacturing process and particularly with low-moderated MOX fissile media. Computation of criticality for eleven configurations and reaction rates ratios for major and minor actinides are performed with CRISTAL french criticality code package, and the reference MCNPX and TRIPOLI-4.3 codes. The multigroup JEF-2.2, JEFF-3.1 and continuous energy JEF-2.2, JEFF-3.1, ENDF/B-VI and ENDF/B-VII neutron cross sections are used for the computations. The results are compared to verify group-wise calculations. Then the obtained calculated values will be used to predict eigenvalue accuracy for applications with damp MOX powder, and to validate 238U, 239Pu, and 240Pu cross sections.

© CEA 2008