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Merge remote-tracking branch 'yardasol/prepare-0.13.1' into prepare-0.13.1
2 parents 282c811 + bee89f2 commit 409263b

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openmc/deplete/independent_operator.py

Lines changed: 7 additions & 8 deletions
Original file line numberDiff line numberDiff line change
@@ -272,15 +272,15 @@ class _IndependentRateHelper(ReactionRateHelper):
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This class does not generate tallies, and instead stores cross sections
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for each nuclide and transmutation reaction relevant for a depletion
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calculation. The reaction rate is calculated by multiplying the flux by the
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cross sections.
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calculation. The reaction rate is calculated by multiplying the flux by
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the cross sections.
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Parameters
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----------
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op : openmc.deplete.IndependentOperator
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Reference to the object encapsulate _IndependentRateHelper.
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We pass this so we don't have to duplicate the :attr:`IndependentOperator.number` object.
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We pass this so we don't have to duplicate the
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:attr:`IndependentOperator.number` object.
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Attributes
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----------
@@ -317,15 +317,14 @@ def get_material_rates(self, mat_id, nuc_index, react_index):
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"""
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self._results_cache.fill(0.0)
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volume = self._op.number.get_mat_volume(mat_id)
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for i_nuc, i_react in product(nuc_index, react_index):
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nuc = self.nuc_ind_map[i_nuc]
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rxn = self.rxn_ind_map[i_react]
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density = self._op.number.get_atom_density(mat_id, nuc)
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# Sigma^j_i * V = sigma^j_i * rho * V
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# Sigma^j_i * V = sigma^j_i * n_i * V = sigma^j_i * N_i
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self._results_cache[i_nuc,i_react] = \
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self._op.cross_sections[rxn][nuc] * density * volume
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self._op.cross_sections[rxn][nuc] * \
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self._op.number[mat_id, nuc]
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return self._results_cache
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