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Set OpenMCOperator materials to the model materials when diff_burnable_mats = True (#2877)
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openmc/deplete/openmc_operator.py

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@@ -142,6 +142,7 @@ def __init__(
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if diff_burnable_mats:
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self._differentiate_burnable_mats()
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self.materials = self.model.materials
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# Determine which nuclides have cross section data
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# This nuclides variables contains every nuclides

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