Simulating cask problem

Hi there!

I would like to ask if OpenMC is capable of simulating shielding problems or it is made for reactor studies only?. E.g: I would like to simulate an Am-Be neutron source and then surround it with layers of different materials and then to tally flux attenuation after each layer to check if these layers shield from neutrons or not. Thanks in advance!

Hi @nuclearsneke. Yes, OpenMC is capable of handling such a problem. You will have to define the neutron spectrum yourself, but otherwise you can run a fixed source problem and study the attenuation in each layer. The most recent release of OpenMC includes the capability to use weight windows, which may be useful for such a study.

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