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getting initial nuclide densities from depletion results, other choice would be to update python densities, but depletion results are needed anyway

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guillaume 2018-05-29 19:09:38 -04:00
parent cf85c2bb05
commit 563e3436e4
3 changed files with 43 additions and 11 deletions
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2
examples/python/pincell_depletion/restart_depletion.py
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@ -40,7 +40,7 @@ previous_results = openmc.deplete.ResultsList("depletion_results.h5")
# Transport calculation settings
###############################################################################
# Instantiate a Settings object, set all runtime parameters, and export to XML
# Instantiate a Settings object, set all runtime parameters
settings_file = openmc.Settings()
settings_file.batches = batches
settings_file.inactive = inactive