Hi, I am a first-time user of openmc. I encountered a problem when run depletion.ipynb. The initialization of number of nuclide Xe135 is not zero, it’s about 5.541e+02. Why is this?
I’m not sure from the description if this is the answer you are looking for. But perhaps this applies to your simulation.
When running deletion simulation for non fission situations I tend to use the dilute_initial keyword and set it to zero to avoid the production of fissile nuclides in small quantities.
https://docs.openmc.org/en/v0.12.2/pythonapi/generated/openmc.deplete.Operator.html
Thank you very much for your response. It works well!