Hi all,
I am currently running some simulations of a tokamak style fusion reactor using paramak & DAGMC. I am also comparing my results from using a standard ring of sources and the openmc-plasma-source developed by Shimwell. I am currently trying to normalise my flux tally from the default output of neutron-cm/source to neutron/cm^2*s.
I am aware of the method involving using the power estimation and the energy of each neutron but I was wondering if there was a way to precisely find out the total neutrons/second outputted in the simulation and then use that information to process the flux tally data. (I am running fixed source simulations)
Thanks
Jake