Replies: 2 comments 1 reply
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Interesting source. From the docs I can see that the Z arg accepts univariates which might do what you are after It might also be worth plotting the OpenMC source with https://github.com/fusion-energy/openmc_source_plotter |
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The Setting Lists are also acceptable so you could do However you want a different Univariate to the Discrete Univariate. I think you want a Perhaps something like this is what you are after openmc.stats.CylindricalIndependent(
r=openmc.stats.Uniform(a=0, 100), # 0 cm to 100 cm radius of cylinder
phi=openmc.stats.Uniform(a=0, b=2*3.141592653589793238), # 0 radians to 2 pi radians
z=openmc.stats.Uniform(a=-10, b=10), # -10 cm to 10cm in height
origin=(0.0, 0.0, 0.0),
) For the openmc_source_plotter it just got updated a few days ago but it does need the latest development version of openmc to work. If it still crashes with the new versions of both packages would you mind sending me any error messages. Thanks |
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Hello.
Is there an easy way to make an infinite cylindrical source in openmc? I am assuming it would be similar to your ring source, but I am having a hard time trying to modify it.
I have a geometry like this:
c1=openmc.ZCylinder(x0=0.0, y0=0.0, r=300.0, boundary_type="reflective")
c2=openmc.ZCylinder(x0=0.0, y0=0.0, r=100.0)
breeding_zone = +c2 & - c1
cell_bz=openmc.Cell(region = breeding_zone)
cell_bz.fill = mixed_mat
I want to place an axial source inside.
Thanks,
Felipe.
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