CECMIntegrator source normalization

User Support
1

Hi all,

I want to use IndependentOperator with CECMIntegrator to deplete material; I have a fixed neutron flux source in n/cm2s (total magnitude); I have used this flux to get one group cross sections.

My question pertains to the normalization CECMIntegrator using source_rates:

Should I just use my total flux magnitude or should I multiply it with the volume of the irradiated material? Naturally, I have already provided the volume of the irradiated material.

2

I tried various normalizations and compared the results against analytical calculations for very simple cases. The answer is to multiply by the volume of the irradiated material.