adding nuc_with_data to allow all nuclides #40
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Many thanks to a user for reporting and to @eepeterson for identifying the cause of this bug.
details here https://openmc.discourse.group/t/openmc-13-3-depletion-results-is-not-as-expected/2941
This PR is a quick and not very eligant fix that changes the code to call
export_to_materialswith thenuc_with_dataargument. This allows nuclides not in the cross_sections.xml to be added to the material when it is exported.