Abstract

OpenMC(Time-Dependent) or OpenMC(TD), is a modified version of OpenMC which includes the time dependence related to the emission of fl -delayed neutron emission from individual precursors. Although the code is still in ongoing development and has been tested in simple systems, its results so far have been promising. The aim of this work is to show that OpenMC(TD) can be a valuable Monte Carlo tool and opens up the possibility of new studies in problems related to the future of nuclear reactor physics and nuclear fission technology. In particular, OpenMC(TD) has the potential to serve as a tool to study the neutronics of transients systems such as the proposed advanced reactor concept that is the Molten Salt Fast Reactor, to prompt the measurement of new experimental data to study its impact on nuclear reactor calculations, to enhance the use of nuclear fuel with improved depletion calculations, and in the assessment of proliferation resistance of nuclear fuels.