So I have a geometry model of a core + shielding. A kcode runs fine on it. I want to quantify how much makes it through the shielding. Specifically, what the absorbed dose rate of neutrons and gammas would be in a specific material right out side the shielding. (So total energy deposited divided by…

How to simulate reactor shielding in OpenMC?

Shimwell April 18, 2023, 12:43pm 2

Hi Kaspar Welcome to the community.

I have a few examples for question 1 (How do I define an absorbed dose tally?) here

Photon flux with a layer of water and air

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