Depletion on Nonfissile material

User Support
1

Hi all，
Whether the depletion process for non-fissile materials can be calculated by OpenMC? such as the graphite matrix in TRISO particles, Ag-In-Cd control rod burnup, etc.? Thanks.

2

@zhaozelong this is indeed possible. You just need to denote the material as burnable with

mat = openmc.Material()
mat.depletable = True

https://docs.openmc.org/en/stable/pythonapi/generated/openmc.Material.html

Cheers,
Andrew