Hi,
How would one go about fuel shuffling in OpenMC? Any nice way of doing this with lattices? Or must I update all materials and cells individually with results from a previous depletion result file? Any ideas?
best regards,
Sindre
Hi,
How would one go about fuel shuffling in OpenMC? Any nice way of doing this with lattices? Or must I update all materials and cells individually with results from a previous depletion result file? Any ideas?
best regards,
Sindre
Hi Sindre,
There is not yet a simplified approach to doing fuel shuffling in OpenMC, but the general approaches are in the following categories:
Universes/Lattices: This is the simplest to implement, but requires the model include a universe and lattice structure and that the desired fuel management strategy is amenable to lattices. Do this by simply re-order a lattice universe structure in the Lattice.universes attribute as desired.
Cells: This is the most complicated, but theoretically you could be moving actual cells around (from one universe to another).
Materials: This is simple conceptually, and more generally applicable, but requires more steps to perform than the lattice case. Here, you are actually going through and swapping one material out for another manually.
Note that all of the above assume you have imported depleted materials from the previous depletion results file as you mentioned.
Thanks!
Adam Nelson