Monte Carlo simulation of fission yields, kinetic energy, fission neutron spectrum and decay gamma-ray spectrum for Th-232(n,f) reaction induced by H-3(d,n) He-4 neutron source

摘要

Monte Carlo transport code Geant4 has been successfully utilised to study of neutron-induced fission reaction for Th-232 in the transport neutrons generated from H-3(d,n)He-4 neutron source. The purpose of this work is to examine the applicability of Monte Carlo simulations for the computation of fission reaction process. For this, Monte Carlo simulates and calculates the characteristics of fission reaction process of Th-232(n,f), such as the fission yields distribution, kinetic energy distribution, fission neutron spectrum and decay gamma-ray spectrum. This is the first time to simulate the process of neutron-induced fission reaction using Geant4 code. Typical computational results of neutron-induced fission reaction of Th-232(n,f) reaction are presented. The computational results are compared with the previous experimental data and evaluated nuclear data to confirm the certain physical process model in Geant4 of scientific rationality.