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moltres
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#include <ElmIntegTotFissNtsPostprocessor.h>
Public Member Functions | |
| ElmIntegTotFissNtsPostprocessor (const InputParameters ¶meters) | |
Static Public Member Functions | |
| static InputParameters | validParams () |
Protected Member Functions | |
| virtual Real | computeQpIntegral () override |
Protected Attributes | |
| unsigned int | _num_groups |
| The number of neutron energy groups. | |
| unsigned int | _num_precursor_groups |
| The number of precursor groups. | |
| bool | _account_delayed |
| Whether to account for delayed neutrons. | |
| const MaterialProperty< std::vector< Real > > & | _nsf |
| nu Sigma_f material property | |
| const MaterialProperty< Real > & | _beta |
| delayed neutron fraction material property | |
| const MaterialProperty< std::vector< Real > > & | _decay_constant |
| Decay constant material property. | |
| const bool | _has_delayed_source |
| Whether we have delayed source variable. | |
| const VariableValue & | _delayed_source |
| delayed source variable | |
| std::vector< MooseVariableFEBase * > | _vars |
| std::vector< const VariableValue * > | _group_fluxes |
| Group flux variables. | |
| std::vector< const VariableValue * > | _pre_concs |
| Precursor concentration variables. | |
This class computes the postprocessor value for the total number of neutrons produced in one neutron generation from fission and delayed neutron precursors if specified. \( \sum_g \nu \Sigma_{g,f} \phi_g + \sum_i \lambda_i C_i \)
| ElmIntegTotFissNtsPostprocessor::ElmIntegTotFissNtsPostprocessor | ( | const InputParameters & | parameters | ) |
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Whether to account for delayed neutrons.
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delayed neutron fraction material property
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Decay constant material property.
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delayed source variable
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Group flux variables.
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Whether we have delayed source variable.
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nu Sigma_f material property
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The number of neutron energy groups.
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The number of precursor groups.
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Precursor concentration variables.
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