perhaps from nuclide

fusion-energy · Dec 2, 2023 · 4a8e80d · 4a8e80d
1 parent de5f746
commit 4a8e80d
Showing 1 changed file with 2 additions and 2 deletions.
diff --git a/tasks/task_11_CSG_shut_down_dose_tallies/3_mesh_based_shut_down_dose_rate_example.py b/tasks/task_11_CSG_shut_down_dose_tallies/3_mesh_based_shut_down_dose_rate_example.py
@@ -139,8 +139,8 @@
 )
 
 # # constructing the operator, note we pass in the flux and micro xs
-operator = openmc.deplete.IndependentOperator(
-    materials=#TODO find the materials in each mesh voxel and their volume fractions,
+operator = openmc.deplete.IndependentOperator().from_nuclides(
+    materials=#TODO find the nuclides in each mesh voxel and their volume fractions,
     fluxes=flux_in_each_group,
     micros=micro_xs,
     reduce_chain=True,  # reduced to only the isotopes present in depletable materials and their possible progeny