Dear,
Paul Romano
I want to ask, can you tell me about Burn-up code of openmc with uranium oxide fuel pebble shaped?
And In pincell depletion, there are only k effective and reaction fission. But i want to get information about atomic density, neutron flux and burn-up level through burn-up time. Can you tell me how i can resolve my problem?
Thx,
Auliyah