Remove nuclides in depletion runs

[andrewjohnson]

Hi llgunnel7 and welcome to the forum!

We don’t have this functionality at this time. There have been some good discussions in

Geometry can change during depletion calculation?

Hello Julien, Thank you for the kind words. Currently we do not support changing the geometry through depletion in a simple manner. There have been some discussions in https://github.com/openmc-dev/openmc/issues/1519 and in change the material in individual cells during a depletion calculation that may be of interest Regards, Andrew

and

Geometry can change during depletion calculation?

Julien, That seems to be a pretty sensible approach. I think we (the core developers) are trying to figure out the best way to support these types of changes through depletion. Both for geometry and possibly material edits. There isn’t a great timeline at this point, but please let us know how your experience goes! Any insight would be great as we sort through this. With respect to extracting the depleted material compositions, we don’t have a straight forward way for doing this. Yet! There ar…

relating to how you could use some existing and new features (exporting depletion data to xml) to help achieve this.

Cheers,

Andrew