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MCNP5 help

 
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Dec5-10, 03:01 PM   #1
 

MCNP5 help


Hello fellow nuclear engineers and physicists,

Does anyone know how to just get the scattered dose from a surface like concrete using MCNP5? I'm doing a project for a shielding class and I need to compare scattered dose and direct (uncollided) dose for a point detector. The photons are coming from a point source.

I've experimented with tallies associated with energy bins, but it's getting real complicated and I can't find a clever way to filter just the photons scattered from concrete.

My only theory is finding the dose with just air, then finding the dose with the concrete and air and subtracting the two to find the scattered dose from the concrete.
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Dec5-10, 03:08 PM   #2
 
Here is my input file, it has the geometry in it.
Attached Files
File Type: txt project.txt (3.7 KB, 16 views)
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