hello everyone , I’ve got a question to consult , depletion calculation devide the fuel to several regions ,so there are several material,
_, u235=results.get_atoms(“38”, “U235”)only support one material id, but i want to get the total atome number of all regions,how can i get it
Are you referring to “diff_burnable_mats=True” in your depletion operator?
No, i divide the geometry to different region and differt region give deiffert material.
results = openmc.deplete.Results(‘depletion_results.h5’)
materials_dep = results.export_to_materials(1) # 1 is for 1 step depletion, 0 would be fresh
materials_dep.export_to_xml()
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Put these three lines after the line that runs the depletion (the “.integrate” line). Once the depletion is done it will read the results and rewrite the materials.xml file with the new material compositions generated by the depletion in units of atoms/barn-cm.
