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moltres
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#include <FissionHeatSource.h>
Public Member Functions | |
| FissionHeatSource (const InputParameters ¶meters) | |
Static Public Member Functions | |
| static InputParameters | validParams () |
Protected Member Functions | |
| virtual Real | computeQpResidual () override |
| virtual Real | computeQpJacobian () override |
| virtual Real | computeQpOffDiagJacobian (unsigned int jvar) override |
Protected Attributes | |
| const MaterialProperty< std::vector< Real > > & | _fissxs |
| const MaterialProperty< std::vector< Real > > & | _d_fissxs_d_temp |
| const MaterialProperty< std::vector< Real > > & | _fisse |
| const MaterialProperty< std::vector< Real > > & | _d_fisse_d_temp |
| unsigned int | _num_groups |
| Number of neutron groups. | |
| const PostprocessorValue & | _tot_fission_heat |
| Total fission heat postprocessor. | |
| const Real | _power |
| User-defined power output. | |
| const bool | _has_heat_source |
| Whether a heat source auxvariable is provided. | |
| const VariableValue & | _heat_source |
| Heat source variable. | |
| const Real | _gamma_frac |
| Gamma heating fraction in non-fissile regions. | |
| std::vector< const VariableValue * > | _group_fluxes |
| Group flux variables. | |
| std::vector< unsigned int > | _flux_ids |
| Group flux variable IDs. | |
This kernel will likely only be used with k-eigenvalue calculation mode with neutrons only, since the power is normalized in this case.
| FissionHeatSource::FissionHeatSource | ( | const InputParameters & | parameters | ) |
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Group flux variable IDs.
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Gamma heating fraction in non-fissile regions.
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Group flux variables.
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Whether a heat source auxvariable is provided.
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Heat source variable.
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Number of neutron groups.
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User-defined power output.
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Total fission heat postprocessor.