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Respond to @wbinventor comments on #593
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3 changed files with 33 additions and 33 deletions
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@ -418,15 +418,15 @@
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"\n",
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"# Instantiate flux Tally in moderator and fuel\n",
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"tally = openmc.Tally(name='flux')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id]),\n",
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" energy_filter]\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n",
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"tally.filters.append(energy_filter)\n",
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"tally.scores = ['flux']\n",
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"tallies_file.add_tally(tally)\n",
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"\n",
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"# Instantiate reaction rate Tally in fuel\n",
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"tally = openmc.Tally(name='fuel rxn rates')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id]),\n",
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" energy_filter]\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id])]\n",
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"tally.filters.append(energy_filter)\n",
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"tally.scores = ['nu-fission', 'scatter']\n",
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"tally.nuclides = [u238, u235]\n",
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"tallies_file.add_tally(tally)\n",
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@ -516,8 +516,8 @@
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"\n",
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"# Instantiate flux Tally in moderator and fuel\n",
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"tally = openmc.Tally(name='need-to-slice')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id]),\n",
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" energy_filter]\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n",
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"tally.filters.append(energy_filter)\n",
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"tally.scores = ['nu-fission', 'scatter']\n",
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"tally.nuclides = [h1, u238]\n",
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"tallies_file.add_tally(tally)"
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