Hello there,
I am new to OpenMC and I am trying to learn to do depletion using OpenMC. Now there is an example for depletion in GitHub, but I can not understand how the neutron energy range was defined, or is the example for continuous energy spectrum?
If it is for continuous spectrum, Is it possible to define specific energy range for depletion analysis to accelarate the calculations and if yes, can anyone tell me how?
thank you in advance
Mary