Hi, i’m working on a hexagonal core.i’m facing a problem which i don’t know what to do about-
How can i calculate assembly average fission rate for every individual assembly?is there a way?
-Thanks in advance
Hello, I recently completed my hexagonal RBWR. There are a few ways to accomplish your objective using tallies with Filter like MeshFilter and CellFilter : Tally Arithmetic — OpenMC Documentation
Alternatively specify a material and geometry zone separately and utilize results.get_reaction_rate : Pincell Depletion — OpenMC Documentation
Additionally, you may view my post here; my code there may correspond to what you’re attempting to accomplish : Difference in Fission rate Tally value from MeshFilter and CellFilter
@Sivakorn.SSW thank you for your kind response. i’ll try these first ,if there is anything else i’d let you know.