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ElmIntegTotFissNtsPostprocessor Class Reference

#include <ElmIntegTotFissNtsPostprocessor.h>

Inheritance diagram for ElmIntegTotFissNtsPostprocessor:
[legend]

Public Member Functions

 ElmIntegTotFissNtsPostprocessor (const InputParameters &parameters)
 

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.
 

Detailed Description

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. \( \sum_g \nu \Sigma_{g,f} \phi_g + \sum_i \lambda_i C_i \)

Constructor & Destructor Documentation

◆ ElmIntegTotFissNtsPostprocessor()

ElmIntegTotFissNtsPostprocessor::ElmIntegTotFissNtsPostprocessor ( const InputParameters & parameters)

Member Function Documentation

◆ computeQpIntegral()

Real ElmIntegTotFissNtsPostprocessor::computeQpIntegral ( )
overrideprotectedvirtual

◆ validParams()

InputParameters ElmIntegTotFissNtsPostprocessor::validParams ( )
static

Member Data Documentation

◆ _account_delayed

bool ElmIntegTotFissNtsPostprocessor::_account_delayed
protected

Whether to account for delayed neutrons.

◆ _beta

const MaterialProperty<Real>& ElmIntegTotFissNtsPostprocessor::_beta
protected

delayed neutron fraction material property

◆ _decay_constant

const MaterialProperty<std::vector<Real> >& ElmIntegTotFissNtsPostprocessor::_decay_constant
protected

Decay constant material property.

◆ _delayed_source

const VariableValue& ElmIntegTotFissNtsPostprocessor::_delayed_source
protected

delayed source variable

◆ _group_fluxes

std::vector<const VariableValue *> ElmIntegTotFissNtsPostprocessor::_group_fluxes
protected

Group flux variables.

◆ _has_delayed_source

const bool ElmIntegTotFissNtsPostprocessor::_has_delayed_source
protected

Whether we have delayed source variable.

◆ _nsf

const MaterialProperty<std::vector<Real> >& ElmIntegTotFissNtsPostprocessor::_nsf
protected

nu Sigma_f material property

◆ _num_groups

unsigned int ElmIntegTotFissNtsPostprocessor::_num_groups
protected

The number of neutron energy groups.

◆ _num_precursor_groups

unsigned int ElmIntegTotFissNtsPostprocessor::_num_precursor_groups
protected

The number of precursor groups.

◆ _pre_concs

std::vector<const VariableValue *> ElmIntegTotFissNtsPostprocessor::_pre_concs
protected

Precursor concentration variables.

◆ _vars

std::vector<MooseVariableFEBase *> ElmIntegTotFissNtsPostprocessor::_vars
protected

The documentation for this class was generated from the following files: