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remove unneeded parameter from update
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3 changed files with 4 additions and 8 deletions
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@ -331,7 +331,7 @@ class NormalizationHelper(ABC):
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`fission_rates` for :meth:`update`.
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"""
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def update(self, fission_rates, mat_index=None):
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def update(self, fission_rates):
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"""Update the normalization based on fission rates (only used for
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energy-based normalization)
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@ -341,8 +341,6 @@ class NormalizationHelper(ABC):
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fission reaction rate for each isotope in the specified
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material. Should be ordered corresponding to initial
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``rate_index`` used in :meth:`prepare`
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mat_index : int
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Material index
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"""
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@property
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@ -426,7 +426,7 @@ class ChainFissionHelper(EnergyNormalizationHelper):
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self._fission_q_vector = fission_qs
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def update(self, fission_rates, mat_index=None):
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def update(self, fission_rates):
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"""Update energy produced with fission rates in a material
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Parameters
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@ -435,8 +435,6 @@ class ChainFissionHelper(EnergyNormalizationHelper):
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fission reaction rate for each isotope in the specified
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material. Should be ordered corresponding to initial
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``rate_index`` used in :meth:`prepare`
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mat_index : int
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Unused
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"""
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self._energy += dot(fission_rates, self._fission_q_vector)
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@ -528,13 +528,13 @@ class OpenMCOperator(TransportOperator):
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# Accumulate energy from fission
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if fission_ind is not None:
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self._normalization_helper.update(
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tally_rates[:, fission_ind],
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mat_index=mat_index)
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tally_rates[:, fission_ind])
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# Divide by total number and store
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rates[i] = self._rate_helper.divide_by_adens(number)
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# Scale reaction rates to obtain units of reactions/sec
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print(f"flux, power, or source rate: {self._normalization_helper.factor(source_rate)}")
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rates *= self._normalization_helper.factor(source_rate)
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# Store new fission yields on the chain
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