Dear community,
I am running a fixed source simulation to tally the flux, which I want to use later for creating weight windows in a cylindrical mesh, but I did not manage to do it because:
I attach the pictures of the model I am using for this purpose.
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I ran the eigenvalue simulation and obtained the fission source (this worked well),
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I created a cylindrical mesh to tally the neutron flux and the simulation get stuck in a given particle number. Then, I cannot generate my weight window using this tally.
I saw that something similar was happening and was fixed in the mesh.cpp for a regular mesh, but maybe something similar is happening for the cylindrical mesh.
Your assistance would be supportful,
Best
Juan

