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| | CoupledFissionKernel (const InputParameters ¶meters) |
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| | ScalarTransportBase (const InputParameters ¶meters) |
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| virtual Real | computeConcentration (const VariableValue &u, unsigned int qp) |
| | Computes \(c\).
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| virtual RealVectorValue | computeConcentrationGradient (const VariableValue &u, const VariableGradient &grad_u, unsigned int qp) |
| | Computes \(\nabla c\).
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| virtual Real | computeConcentrationDerivative (const VariableValue &u, const VariablePhiValue &phi, unsigned int j, unsigned int qp) |
| | Computes \(\frac{\partial c}{\partial u_j}\).
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| virtual RealVectorValue | computeConcentrationGradientDerivative (const VariableValue &u, const VariableGradient &grad_u, const VariablePhiValue &phi, const VariablePhiGradient &grad_phi, unsigned int j, unsigned int qp) |
| | Computes \(\nabla \frac{\partial c}{\partial u_j}\).
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| virtual Real | computeConcentrationDot (const VariableValue &u, const VariableValue &u_dot, unsigned int qp) |
| | Computes \(\frac{\partial c}{\partial t}\).
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| virtual Real | computeConcentrationDotDerivative (const VariableValue &u, const VariableValue &u_dot, const VariableValue &du_dot_du, const VariablePhiValue &phi, unsigned int j, unsigned int qp) |
| | Computes \(\frac{\partial}{\partial t} \frac{\partial c}{\partial u_j}\).
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| const MaterialProperty< std::vector< Real > > & | _nsf |
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| const MaterialProperty< std::vector< Real > > & | _d_nsf_d_temp |
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| const MaterialProperty< std::vector< Real > > & | _chi_t |
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| const MaterialProperty< std::vector< Real > > & | _chi_p |
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| const MaterialProperty< std::vector< Real > > & | _d_chi_t_d_temp |
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| const MaterialProperty< std::vector< Real > > & | _d_chi_p_d_temp |
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| const MaterialProperty< Real > & | _beta |
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| const MaterialProperty< Real > & | _d_beta_d_temp |
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| const unsigned int | _group |
| | Neutron group number.
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| const unsigned int | _num_groups |
| | Number of neutron groups.
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| const unsigned int | _temp_id |
| | Temperature variable ID.
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| const VariableValue & | _temp |
| | Temperature variable.
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| std::vector< const VariableValue * > | _group_fluxes |
| | Group flux variables.
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| std::vector< unsigned int > | _flux_ids |
| | Group flux variable IDs.
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| const bool | _account_delayed |
| | Whether to account for delayed neutron precursors.
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| const PostprocessorValue & | _eigenvalue_scaling |
| | Eigenvalue scaling factor.
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Computes fission source of neutrons without normalizing by \( 1/k \). Note that this kernel is meant for transients.