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Questions related from Otto Haubrich
I simulate a reactor in MCNP. However I want to know the spectrum (energy) and flux in a specific surface (or cell) away from the nucleus (source). I thought using F2 tally, but I do not want the...
05 January 2024 3,864 6 View
Hello. I defined my material in MCNP, but I want to add an element in it. My material is a human tissue and I want to add the element boron-10, more precisaly 30ppm of boron-10 in the material....
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Hello. I have a souce of neutrons and my F4 tally value (non-normalized) in a cell is 10^3/(cm^2). I want to increase the value, for exemple 10^9 /(cm^2), without modifying the area. I used FM...
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