Criticality safety benchmark calculations using the new evaluated data librariesI.I. Degtyarev1 and V.M. Maslov2
1 Institute of High Energy Physics, 142281 Protvino, Russia
2 Joint Institute of Nuclear and Energy Research-SOSNY, 220109 Minsk-Sosny, Belarus
Published online: 21 May 2008
The criticality safety benchmark calculations with the RTS&T general purpose Monte Carlo code were extensively used to validate the 233,235U and 239Pu evaluated data files. The benchmarks employed are from the International Criticality Safety Benchmark Evaluation Project (ICSBEP). We have performed calculations using the newly evaluated data files from ENDF/B-VII.0 and special purpose Minsk Actinides Library. The influence of the prompt fission neutron spectra of major actinides on the keff for the selected fast spectrum benchmarks is investigated.
© CEA 2008