Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters

摘要

Analyses are carried out to assess the impact of nuclear data uncertainties on k_(eff) for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of ~(239)Pu random ENDF-formatted libraries generated using the TALYS based system were processed into ACE format with NJOY-99.336 code and used as input into the Serpent Monte Carlo neutron transport code to obtain distribution in k_(eff). The mean of the k_(eff) distribution obtained was compared with the major nuclear data libraries, JEFF-3.1.1, ENDF/B-Ⅶ.1 and JENDL-4.0. A method is proposed for the selection of benchmarks for specific applications using the Total Monte Carlo approach. Finally, an accept/reject criterion was investigated based on x~2 values obtained using the ~(239)Pu Jezebel criticality benchmark. It was observed that nuclear data uncertainties in k_(eff) were reduced considerably from 748 to 443 pcm by applying a more rigid acceptance criteria for accepting random files.