Hello,
I want to simulate some cross-section measurements.
Can OpenMC simulate neutron beam experiments?
I want to define a neutron beam of a given energy, and measure the relative number of counts of a detector after being attenuated by a certain material.
Hi Terry,
It’s definitely possible to define a “beam” of a given energy. As far as measuring “counts”, you would have to rely on some kind of proxy measure – for example, if you were simulating a 3He detector, you could tally the neutron absorption rate in He3 since that would be related to the actual count you would receive in a detector. Hope that helps.
Best regards,
Paul