Dear guys,
I’m trying to partition the fuel to realize an accurate burnup calculation , get power distribution evolution over time and obtain local burnup level . For this purpose, I use the diff_burnable_mats=True property in CoupledOperator instance to distinguish the same fuel material in different lattice. However, In the materials.xml file getting from the results class, these materials become indistinguishable except the id.
I want to know how to relate the id of these materials to the cell index where the fuel is located so that I can get the burnup depth at different locations.
Thank you.
Hi fyh_sinap
Perhaps you can use the cell bounding box to get the location of the material, here are some links to the docs for the latest version of openmc. Bounding_box has a . center attribute
https://docs.openmc.org/en/latest/pythonapi/generated/openmc.Cell.html
bounding_box
https://docs.openmc.org/en/latest/pythonapi/generated/openmc.BoundingBox.html#openmc.BoundingBox