Hello, everyone!

I want to use point reactor kinetics equations for calculating transient problems. The delayed neutron lifetime, fraction can be obtained by mgxs class. However, I can’t find a way to process the neutron generation time or prompt neutron lifetime. Does anyone know it,very gratefully!

Hello, although I’m not super fresh on the topic, I did my dissertation on transient problems in OpenMC. If you see this paper, equation 10 shows one way to calculate prompt neutron lifetime. Please see the PDF version of the paper, as the online version distorts equation 10.

You might also find it useful to poke around this branch of OpenMC on my GitHub for more.