Nuclear Data Needs for the Neutronic Design of MYRRHA Fast Spectrum Research Reactor

摘要

A global sensitivity analysis of effective neutron multiplication factor to the change of nuclear data library has been performed. It revealed that the test version of JEFF-3.2 neutron-induced evaluated data library produces closer results to ENDF/B-Ⅶ.1 than JEFF-3.1.2 does. The analysis of contributions of individual evaluations into k_(eff) sensitivity resulted in the priority list of nuclides, uncertainties on cross sections and fission neutron multiplicities of which have to be improved by setting up dedicated differential and integral experiments.