I want to try to do Monte Carlo transient simulations using OpenMC. Theoretically, I can do transient simulations by simply time-tagging each neutron, and I would like to know if OpenMC currently supports it?
OpenMC will keep track of the time of particles and allows you to filter scores by time using the TimeFilter class. However, do note that if you have fissionable materials, delayed neutrons are not emitted at the correct time, so it is not possible to do transient simulations for fission reactors.