I need to cmpare power deposition results obtained with a Serpent model and an OpenMC model. The Serpent model calculates MT -80 Total energy deposition: combines responses for fission heating, neutron heating based on KERMA coefficioents and analog photon heating.
I wanted to knwo which (if it exists) is the equivalent Tally for this? and if there’s not one how can I obtain that exact information using OpenMC?
thanks in advance.