Depletion on Nonfissile material

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.

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

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