I’m a beginner to OpenMC, and now I’ve built a model of my own.But an error occurred while I was running it.
I want to evaluate the absorbing properties of a new material with boron for different (discrete) neutron energies. When compiling the source with, open the openmc.Source() and openmp.statistics.Discrete () error: “There are no division points tilted by MPI of rank 0”.
When using fixed source, another error is “Could not find the cell containing particle 5001”.
How to correctly set the source for such a task? I think that using a openmc.Source() is wrong. In my opinion, it is correct to use custom source . But how can I fix a compilation error?
Sincerely hope to get your help.