Isotropic distribution for a surface source MCNP

  • Thread starter angfells
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    Mcnp Mcnp6
  • #1
angfells
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Hello everyone!
I have to use isotropic distribution for my mcnp program. But I didn't find how can I create that one.
 
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  • #2
Does it have to be a surface source? With a cell source, for example a point source, isotropic is the default.
 
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Likes berkeman
  • #3
Alex A said:
Does it have to be a surface source? With a cell source, for example a point source, isotropic is the default.
Yes, it has to be a surface..
 
  • #4
What is the shape of the surface and can the source be a degenerate volume source?

That would be a surface but it has the advantages of not using a geometric surface and so the result is isotropic.
 
  • #5
Alex A said:
What is the shape of the surface and can the source be a degenerate volume source?

That would be a surface but it has the advantages of not using a geometric surface and so the result is isotropic.
This is the surface of the cube, that is, one side of it.
I tried to make a cell source of it, but i don't understant how to do it correctly. For the cell source I need to write from which cell neutron flux starts and add some distributions of the cell, if I correctly understand. But I also have energy distribution "erg=d4". When I write distributions si1=-12 11, si2=-10 10, si3=-10 10 for x y z coordinates and sp1=-2 for energy I have some fatal errors.

I just now tried to use a degenerate cartesian volumetric source and immediately checked at the angles of the departure of the particles whether it is isotropic, and it seems that everything worked.
 

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