École Nationale Supérieure de
Techniques Avancées

Abstract

For nuclear safety studies, accurate knowledge of the nuclear data used as input to neutron simulation codes is of the highest importance. This knowledge is necessary to determine the uncertainties on the neutron parameters and to evaluate the bias coming from the nuclear data. The work detailed in this study was proposed by the ‘Institut de Radioprotection et de Sûreté Nucléaire’ (IRSN). It consists of identifying sensitive isotopes, impacting simulation results for Pressurized Water Reactors (PWRs) using Monte Carlo calculations in evolution and sensitivity calculations. The computation of sensitivities and contribution of uncertainty of nuclear data to the final simulation result is performed as a function of irradiation time. This is in contrast to studies where calculations are carried out for the beginning of life of a reactor fuel lifecycle. The aim of this work is to assess the uncertainties related to the nuclear data impacting the safety studies at IRSN.