Monte Carlo simulation of neutron transport applied to criticality Focus on sources and flux convergence issues

摘要

Safety studies to determine criticality risk (uncontrolled multiplication of neutrons) in systems containing fissile material require the use of computer codes (software programs) that can simulate neutrons in complex three-dimensional configurations. This article describes the specific features of the Monte Carlo simulation method, used to simulate neutron transport for criticality studies conducted using the MORET code developed at IRSN. It highlights also the flux convergence issues in Monte Carlo depletion simulations.