Nuclear Material Particle Layers

Description

This NuclearMaterialParticleLayers action reduces BISON input file length by internally generating the Materials required for simulating TRISO nuclear outer layers for multiple different levels.

warning:For TRISO Use Only

This action is designed for use with only TRISO simulations.

User-based Interface

To reduce the length and complexity of necessary blocks for simulations, an extensive standardization of operating conditions has been utilized within the NuclearMaterials.

All of the blocks, generated with the default parameter settings, are shown in Table 1, Table 2, and Table 3. These blocks are created internally, based on the Layers Models and/or physics conditions shown. Additional parameters for each created class can be found below.

note

Certain parameters are determined internally to further reduce input length and complexity.

The classes in Table 1 are automatically created when using NuclearMaterialParticleLayers depending on the Layers Models and Fission operation used as well as what occurs under Physics conditions.

Table 1: Material classes created by the NuclearMaterialParticleLayers action

Created Classes	Pre-Set Parameters	Block Name	Layers Models	Fission Operation
StrainAdjustedDensity		'layers_block_name' + "_density"		Normal
ArrheniusDiffusionCoef	arrhenius_prpty_name = "arrhenius_diffusion_coef_" + 'elem_name'	'layers_block_name' + "_conc_" + 'elem_name'	Diffusion	Normal
BufferThermal		Buffer_thermal	Thermal	Normal
MonolithicSiCThermal		SiC_thermal	Thermal	Normal

HeatConductionMaterial		IPyC_thermal/OPyC_thermal	Thermal	Normal

The classes in Table 2 are only created when Thermal or if any Fission occurs under the Fission Operation conditions.

Table 2: Auxiliary classes created by the NuclearMaterialParticleLayers action

Created Auxiliary Classes	Type	Pre-Set Parameters	Block Name	Physics/Layers Models
StrainAdjustedDensity	AuxKernel	variable = density	'layers_block_name' + "_density"
		property = density
StrainAdjustedDensity	AuxVariable		density
Diffusion Coefficient	AuxKernel	variable = 'elem_name' + "_diff_coef"	'layers_block_name' + "_" + 'elem_name' + diff_coef\| Diffusion
		property = "arrhenius_diffusion_coef_" + 'elem_name'
Diffusion Coefficient	AuxVariable		'elem_name' + diff_coef	Diffusion
Thermal Conductivity	AuxKernel	variable = thermal_conductivity	'layers_block_name' + "_thermal_conductivity"	Thermal
		property = thermal_conductivity
Thermal Conductivity	AuxVariable		thermal_conductivity	Thermal
Specific Heat	AuxKernel	variable = specific_heat	'layers_block_name' + "_specific_heat"	Thermal
		property = specific_heat
Specific Heat	AuxVariable		specific_heat	Thermal
Fast Neutron Fluence	AuxKernel	\|fast_neutron_fluence	Normal (Fission)
Fast Neutron Fluence	AuxVariable	\|fast_neutron_fluence	Normal (Fission)
Concentration	Variable		conc + 'elem_name'	Diffusion
Temperature	Variable		temperature	Thermal
HeatConduction	Kernel	variable = temperature	fuel_heat	Thermal
		extra_vector_tags = ref
HeatConductionTimeDerivative	Kernel	variable = temperature	fuel_heat_dt	Thermal
		extra_vector_tags = ref
ArrheniusDiffusion	Kernel	arrhenius_prpty_name = arrhenius_diffusion_coef_" + 'elem_name'	'layers_block_name' + "_mass_" + 'elem_name'	Diffusion
		variable = "conc_" + 'elem_name'
		extra_vector_tags = ref
TimeDerivative / MassLumpedTimeDerivative	Kernel	variable = "conc_" + 'elem_name'	'layers_block_name' + "_mass_" + 'elem_name' + _dt	Diffusion

Table 3: Actions created by the NuclearMaterialParticleLayers action

Created Actions	Pre-Set Parameters	Block Name	Physics/Layers Model Conditions
TensorMechanicsAction	volumetric_locking_correction = false	Physics/SolidMechanics/QuasiStatic	Mechanics
	automatic_eigenstrain_names = true
	decomposition_method = EigenSolution
	strain = FINITE

## Example Simple Input Syntax

NuclearMaterials simplifies Material block inputs by applying standard parameter and classes depending on the simulation. It is possible to only replace the Materials blocks in an input file with the equivalent NuclearMaterialParticleLayers. This procedure greatly reduces the length and complexity of the the necessary inputs while fully retaining the same functionality and end results. An example of this can be seen below.

Fission Operation

note

This required parameter describes the characteristic type of fission study that will occur, i.e. Normal. This must be placed under the NuclearMaterials block heading and cannot be placed under sub-blocks such as SiC.

Layers Model Parameters

Diffusion : Models diffusion of specified elements through the layers.

Expanded Layers Material Block


[Materials]
  [fission_rate]
    type = GenericFunctionMaterial
    prop_names = fission_rate
    prop_values = fission_rate
  []
  [fast_neutron_fluence]
    type = GenericFunctionMaterial
    prop_names = fast_neutron_fluence
    prop_values = fast_neutron_fluence
  []
  [buffer_thermal]
    type = BufferThermal
    block = buffer
    initial_density = 1050.0
  []
  [Buffer_density]
    type = StrainAdjustedDensity
    block = buffer
    density = 1050.0
  []
  [IPyC_thermal]
    type = HeatConductionMaterial
    block = IPyC
    thermal_conductivity = 4.0
    specific_heat = 720.0
  []
  [IPyC_density]
    type = StrainAdjustedDensity
    block = IPyC
    density = 1900.0
  []
  [SiC_thermal]
    type = MonolithicSiCThermal
    block = SiC
    temperature = temperature
    thermal_conductivity_model = miller
  []
  [SiC_density]
    type = StrainAdjustedDensity
    block = SiC
    density = 3200.0
  []
  [OPyC_thermal_conductivity]
    type = HeatConductionMaterial
    block = OPyC
    thermal_conductivity = 4.0
    specific_heat = 720.0
  []
  [OPyC_density]
    type = StrainAdjustedDensity
    block = OPyC
    density = 1900.0
  []
  [buffer_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = buffer
    d1 = 1e-8             # m^2/s
    q1 = 0.0
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [IPyC_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = IPyC
    d1 = 5.3e-9                   # m^2/s
    q1 = 154e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [SiC_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = SiC
    d1 = 3.6e-9                  # m^2/s
    q1 = 215e3                   # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [OPyC_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = OPyC
    d1 = 5.3e-9                   # m^2/s
    q1 = 154e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [mass_source_Ag_property_OPyC]
    type = SpeciesSourceMaterial
    property_name = Ag_generation
    kind = Ag
    block = OPyC
    #value = 1.57e-6 * vol_kernel / vol_opyc
    #value = 1.57e-6 * 6.85e-11 / 1.18e-10
    value = 9.11e-7
  []
  [buffer_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = buffer
    d1 = 1e-8             # m^2/s
    q1 = 0.0
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [IPyC_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = IPyC
    d1 = 6.3e-8                   # m^2/s
    q1 = 222e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [SiC_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = SiC
    d1 = 5.5e-14                  # m^2/s
    q1 = 125e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [OPyC_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = OPyC
    d1 = 6.3e-8                   # m^2/s
    q1 = 222e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [buffer_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = buffer
    d1 = 1e-8             # m^2/s
    q1 = 0.0
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
  [IPyC_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = IPyC
    d1 = 2.3e-6                   # m^2/s
    q1 = 197e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
  [SiC_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = SiC
    d1 = 1.2e-9                  # m^2/s
    q1 = 205e3                   # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
  [OPyC_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = OPyC
    d1 = 2.3e-6                   # m^2/s
    q1 = 197e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
[]

Equivalent Simplified NuclearMaterial Layers Block

[NuclearMaterials<<<{"href": "../index.html"}>>>]
  fission_operation<<<{"description": "Type of fission occuring in this simulation."}>>> = 'Normal'
  physics<<<{"description": "Type(s) of physics used on this block."}>>> = 'Thermal'
  initial_temperature<<<{"description": "Initial temperature in Kelvins."}>>> = 923.15
  elements_tracked<<<{"description": "The elements tracked within TRISO simulations."}>>> = 'Ag'
  elements_initial_concentration<<<{"description": "Relative ratio of element concentration"}>>> = '0.0'
  element_scaling<<<{"description": "Relative scaling of element percentages"}>>> = '1e14'
  use_automatic_differentiation<<<{"description": "Flag to use automatic differentiation (AD) objects when possible"}>>> = false
  [ParticleLayers<<<{"href": "index.html"}>>>]
    layers_models<<<{"description": "Type(s) of physics models used on this block."}>>> = 'Diffusion'
    fuel_type<<<{"description": "Type of fuel used in TRISO simulation.  The choices are: UO2 UCO"}>>> = UCO
    [SiC<<<{"href": "SiC/index.html"}>>>]
      [SiC_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = SiC
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '3.6e-9'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '215e3'
        diffusion_2nd_coefficients<<<{"description": "2nd diffusion coefficient"}>>> = '0'
        diffusion_2nd_activation_energies<<<{"description": "Second diffusion activation energy"}>>> = '0'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 3200.0
        thermal_conductivity_model<<<{"description": "Options for the correlation used to calculate thermal conductivity"}>>> = miller
      []
    []
    [IPyC<<<{"href": "IPyC/index.html"}>>>]
      [IPyC_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = IPyC
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '5.3e-9'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '154e3'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 1900.0
        thermal_conductivity<<<{"description": "The thermal conductivity value"}>>> = 4.0
        specific_heat<<<{"description": "The specific heat value"}>>> = 720.0
      []
    []
    [OPyC<<<{"href": "OPyC/index.html"}>>>]
      [OPyC_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = OPyC
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '5.3e-9'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '154e3'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 1900.0
        thermal_conductivity<<<{"description": "The thermal conductivity value"}>>> = 4.0
        specific_heat<<<{"description": "The specific heat value"}>>> = 720.0
      []
    []
    [Buffer<<<{"href": "Buffer/index.html"}>>>]
      [Buffer_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = buffer
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '1e-8'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '0'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 1050.0
      []
    []
  []
[]

Example Fully Reduced Input Syntax

Input file length and complexity can be reduced even further by use of additional Physics and/or LayersModels block parameters, in addition to applying common parameters to sub-blocks under the NuclearMaterials header.

Physics parameters

Mechanics : This will create the TensorMechanicsAction block(s) under which it is listed. If listed under the NuclearMaterial block header, then this will be applied to all blocks under the header.
Thermal : This will create the temperature variable, the Kernel blocks HeatConduction and HeatConductionTimeDerivative needed to model thermal effects for ZirconiumAlloys.

Expanded Layers Block


[Variables]
  [temperature]
    initial_condition = 923.15
  []
[]
[AuxVariables]
  [fission_rate]
    block = fuel
    order = CONSTANT
    family = MONOMIAL
  []
  [burnup]
    block = fuel
    order = CONSTANT
    family = MONOMIAL
  []
  [fast_neutron_fluence]
    order = CONSTANT
    family = MONOMIAL
  []
  [density]
    order = CONSTANT
    family = MONOMIAL
  []
  [thermal_conductivity]
    order = CONSTANT
    family = MONOMIAL
  []
  [specific_heat]
    order = CONSTANT
    family = MONOMIAL
  []
  [fis_gas_produced]
    order = CONSTANT
    family = MONOMIAL
  []
  [fis_gas_released]
    order = CONSTANT
    family = MONOMIAL
  []
[]
[Kernels]
  [heat_dt]
    type = HeatConductionTimeDerivative
    variable = temperature
  []
  [heat]
    type = HeatConduction
    variable = temperature
    extra_vector_tags = 'ref'
  []
  [heat_source]
    type = NeutronHeatSource
    variable = temperature
    block = fuel
    fission_rate = fission_rate
    extra_vector_tags = 'ref'
  []
[]
[AuxKernels]
  [fissionrate]
    type = MaterialRealAux
    variable = fission_rate
    property = fission_rate
    block = fuel
    execute_on = timestep_begin
  []
  [burnup]
    type = MaterialRealAux
    variable = burnup
    property = burnup
    block = fuel
    execute_on = timestep_begin
  []
  [fast_neutron_fluence]
    type = MaterialRealAux
    variable = fast_neutron_fluence
    property = fast_neutron_fluence
    block = 'fuel buffer IPyC SiC OPyC'
    execute_on = timestep_begin
  []
  [density]
    type = MaterialRealAux
    variable = density
    property = density
    block = 'fuel buffer IPyC SiC OPyC'
    execute_on = 'initial linear'
  []
  [thermal_conductivity]
    type = MaterialRealAux
    variable = thermal_conductivity
    property = thermal_conductivity
    block = 'fuel buffer IPyC SiC OPyC'
    execute_on = timestep_end
  []
  [specific_heat]
    type = MaterialRealAux
    variable = specific_heat
    property = specific_heat
    block = 'fuel buffer IPyC SiC OPyC'
    execute_on = timestep_end
  []
  [fis_gas_produced]
    type = MaterialRealAux
    variable = fis_gas_produced
    property = fis_gas_produced
    block = fuel
    execute_on = linear
  []
  [fis_gas_released]
    type = MaterialRealAux
    variable = fis_gas_released
    property = fis_gas_released
    block = fuel
    execute_on = linear
  []
[]
[Materials]
  [fission_rate]
    type = GenericFunctionMaterial
    prop_names = fission_rate
    prop_values = fission_rate
  []
  [fast_neutron_fluence]
    type = GenericFunctionMaterial
    prop_names = fast_neutron_fluence
    prop_values = fast_neutron_fluence
  []
  [buffer_thermal]
    type = BufferThermal
    block = buffer
    initial_density = 1050.0
  []
  [Buffer_density]
    type = StrainAdjustedDensity
    block = buffer
    density = 1050.0
  []
  [IPyC_thermal]
    type = HeatConductionMaterial
    block = IPyC
    thermal_conductivity = 4.0
    specific_heat = 720.0
  []
  [IPyC_density]
    type = StrainAdjustedDensity
    block = IPyC
    density = 1900.0
  []
  [SiC_thermal]
    type = MonolithicSiCThermal
    block = SiC
    temperature = temperature
    thermal_conductivity_model = miller
  []
  [SiC_density]
    type = StrainAdjustedDensity
    block = SiC
    density = 3200.0
  []
  [OPyC_thermal_conductivity]
    type = HeatConductionMaterial
    block = OPyC
    thermal_conductivity = 4.0
    specific_heat = 720.0
  []
  [OPyC_density]
    type = StrainAdjustedDensity
    block = OPyC
    density = 1900.0
  []
  [buffer_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = buffer
    d1 = 1e-8             # m^2/s
    q1 = 0.0
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [IPyC_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = IPyC
    d1 = 5.3e-9                   # m^2/s
    q1 = 154e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [SiC_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = SiC
    d1 = 3.6e-9                  # m^2/s
    q1 = 215e3                   # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [OPyC_conc_Ag]
    type = ArrheniusDiffusionCoef
    block = OPyC
    d1 = 5.3e-9                   # m^2/s
    q1 = 154e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Ag
  []
  [mass_source_Ag_property_OPyC]
    type = SpeciesSourceMaterial
    property_name = Ag_generation
    kind = Ag
    block = OPyC
    #value = 1.57e-6 * vol_kernel / vol_opyc
    #value = 1.57e-6 * 6.85e-11 / 1.18e-10
    value = 9.11e-7
  []
  [buffer_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = buffer
    d1 = 1e-8             # m^2/s
    q1 = 0.0
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [IPyC_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = IPyC
    d1 = 6.3e-8                   # m^2/s
    q1 = 222e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [SiC_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = SiC
    d1 = 5.5e-14                  # m^2/s
    q1 = 125e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [OPyC_conc_Cs]
    type = ArrheniusDiffusionCoef
    block = OPyC
    d1 = 6.3e-8                   # m^2/s
    q1 = 222e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Cs
  []
  [buffer_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = buffer
    d1 = 1e-8             # m^2/s
    q1 = 0.0
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
  [IPyC_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = IPyC
    d1 = 2.3e-6                   # m^2/s
    q1 = 197e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
  [SiC_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = SiC
    d1 = 1.2e-9                  # m^2/s
    q1 = 205e3                   # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
  [OPyC_conc_Sr]
    type = ArrheniusDiffusionCoef
    block = OPyC
    d1 = 2.3e-6                   # m^2/s
    q1 = 197e3                    # J/mol
    temperature = temperature
    arrhenius_prpty_name = arrhenius_diffusion_coef_Sr
  []
[]

Fully Simplified Fuel Block

[NuclearMaterials<<<{"href": "../index.html"}>>>]
  fission_operation<<<{"description": "Type of fission occuring in this simulation."}>>> = 'Normal'
  physics<<<{"description": "Type(s) of physics used on this block."}>>> = 'Thermal'
  initial_temperature<<<{"description": "Initial temperature in Kelvins."}>>> = 923.15
  elements_tracked<<<{"description": "The elements tracked within TRISO simulations."}>>> = 'Ag'
  elements_initial_concentration<<<{"description": "Relative ratio of element concentration"}>>> = '0.0'
  element_scaling<<<{"description": "Relative scaling of element percentages"}>>> = '1e14'
  use_automatic_differentiation<<<{"description": "Flag to use automatic differentiation (AD) objects when possible"}>>> = false
  [ParticleLayers<<<{"href": "index.html"}>>>]
    layers_models<<<{"description": "Type(s) of physics models used on this block."}>>> = 'Diffusion'
    fuel_type<<<{"description": "Type of fuel used in TRISO simulation.  The choices are: UO2 UCO"}>>> = UCO
    [SiC<<<{"href": "SiC/index.html"}>>>]
      [SiC_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = SiC
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '3.6e-9'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '215e3'
        diffusion_2nd_coefficients<<<{"description": "2nd diffusion coefficient"}>>> = '0'
        diffusion_2nd_activation_energies<<<{"description": "Second diffusion activation energy"}>>> = '0'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 3200.0
        thermal_conductivity_model<<<{"description": "Options for the correlation used to calculate thermal conductivity"}>>> = miller
      []
    []
    [IPyC<<<{"href": "IPyC/index.html"}>>>]
      [IPyC_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = IPyC
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '5.3e-9'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '154e3'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 1900.0
        thermal_conductivity<<<{"description": "The thermal conductivity value"}>>> = 4.0
        specific_heat<<<{"description": "The specific heat value"}>>> = 720.0
      []
    []
    [OPyC<<<{"href": "OPyC/index.html"}>>>]
      [OPyC_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = OPyC
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '5.3e-9'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '154e3'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 1900.0
        thermal_conductivity<<<{"description": "The thermal conductivity value"}>>> = 4.0
        specific_heat<<<{"description": "The specific heat value"}>>> = 720.0
      []
    []
    [Buffer<<<{"href": "Buffer/index.html"}>>>]
      [Buffer_layer]
        block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = buffer
        diffusion_1st_coefficients<<<{"description": "1st diffusion coefficient."}>>> = '1e-8'
        diffusion_1st_activation_energies<<<{"description": "Diffusion activation energies."}>>> = '0'
        initial_density<<<{"description": "Initial density in kg-UO2/m^3"}>>> = 1050.0
      []
    []
  []
[]

The eigenstrain names must be included in the SolidMechanics QuasiStatic Action following the naming convention created by this class. The easiest method to ensure this continutity is to include Mechanics in the physics input parameter. By default, this will select automatic_eigenstrain_names = true.

warning

automatic_eigenstrain_names = true, the eigenstrain_names will be populated under restrictive conditions for classes such as CompositeEigenstrain, ComputeReducedOrderEigenstrain, and RankTwoTensorMaterialADConverter. The input components for these classes are not included in the eigenstrain_names passed to the TensorMechanicsAction. Set the automatic_eigenstrain_names = false and populate this list manually if these components need to be included.

Example Input File Syntax

-!listing test/tests/triso/base_irradiation/triso_accident_action.i block=NuclearMaterials/ParticleLayers-

(assessment/TRISO/validation/AGR-1/AGR-1_action.i)

#COMPACT = <compact_id>
#DATA_FILE = <data_file_name>

[GlobalParams]
  order = SECOND
  family = LAGRANGE
  initial_enrichment = 0.19736 # [wt-]
  energy_per_fission = 3.204e-11 # [J/fission]
  O_U = 1.3613 # Initial Oxygen to Uranium atom ratio
  C_U = 0.3253 # Initial Carbon to Uranium atom ratio
  mass_source_property_OPyC = 7.06e-7 # Default = UCO fuel kernel
  extra_vector_tags = 'ref'
  use_displaced_mesh = false
[]

[Mesh]
  coord_type = RSPHERICAL
  [gen]
    type = TRISO1DFiveLayerMeshGenerator
    elem_type = EDGE3
    kernel_radius = 175e-6
    buffer_thickness = 100e-6
    IPyC_thickness = 40e-6
    SiC_thickness = 35e-6
    OPyC_thickness = 40e-6
    kernel_mesh_density = 18
    buffer_mesh_density = 14
    IPyC_mesh_density = 6
    SiC_mesh_density = 8
    OPyC_mesh_density = 6
    block_names = 'fuel buffer IPyC SiC OPyC'
    include_gap = false
    kernel_bias = 0.8
    buffer_bias = 1.25
  []
[]

[Problem]
  type = ReferenceResidualProblem
  reference_vector = 'ref'
  extra_tag_vectors = 'ref'
[]

[UserObjects]
  [particle_geometry]
    type = TRISOGeometry
    outer_OPyC = OPyC_outer_boundary
    outer_SiC = SiC_outer_boundary
    outer_IPyC = IPyC_outer_boundary
    inner_IPyC = IPyC_inner_boundary
    outer_buffer = buffer_outer_boundary
    outer_kernel = fuel_outer_boundary
    include_particle = true
    include_pebble = false
  []
[]

[Functions]
  [temp_bc_file]
    type = PiecewiseLinear
    #data_file = DATA_FILE
    x_index_in_file = 0
    y_index_in_file = 1
    xy_in_file_only = false
    format = columns
  []
  [temp_bc_safety]
    type = ParsedFunction
    symbol_names = 'test_temperature'
    symbol_values = '1873.15'
    expression = 'start := 55209600+1800;
             ramp1 := 120.0/3600.0;
             ramp2 := 120.0/3600.0;
             ramp3 := 50.0/3600.0;
             ramp4 := -600.0/3600.0;
             room := 303.15;
             plateau1 := 673.15;
             plateau2 := 1523.15;
             hold1 := 7200;
             hold2 := 43200;
             hold3 := 1080000;
             ramp_time1 := (plateau1-room)/ramp1;
             ramp_time2 := (plateau2-plateau1)/ramp2;
             ramp_time3 := (test_temperature-plateau2)/ramp3;
             ramp_time4 := (room-test_temperature)/ramp4;
             t1 := start+ramp_time1;
             t2 := t1+hold1;
             t3 := t2+ramp_time2;
             t4 := t3+hold2;
             t5 := t4+ramp_time3;
             t6 := t5+hold3;
             t7 := t6+ramp_time4;
             if(t<start,room,
             if(t<t1,room+(t-start)*ramp1,
             if(t<t2,plateau1,
             if(t<t3,plateau1+(t-t2)*ramp2,
             if(t<t4,plateau2,
             if(t<t5,plateau2+(t-t4)*ramp3,
             if(t<t6,test_temperature,
             if(t<t7,test_temperature+(t-t6)*ramp4,
             room))))))))'
  []
  [temp_bc]
    type = ParsedFunction
    symbol_names = 'tbcf tbcs'
    symbol_values = 'temp_bc_file temp_bc_safety'
    expression = 'if(t<=55209600,tbcf,tbcs)'
  []
  [power_history] # W/m^3
    type = PiecewiseLinear
    #data_file = DATA_FILE
    x_index_in_file = 0
    y_index_in_file = 2
    xy_in_file_only = false
    format = columns
  []
  [fast_neutron_fluence]
    type = PiecewiseLinear
    #data_file = DATA_FILE
    x_index_in_file = 0
    y_index_in_file = 3
    xy_in_file_only = false
    format = columns
  []
  [fission_rate_from_power]
    type = LinearCombinationFunction
    functions = power_history
    # W/m^3 / (1.602e-13 J/MeV) / (200 MeV/fission)
    w = 3.1211e10
  []
  [fission_rate]
    type = ParsedFunction
    symbol_names = 'fr'
    symbol_values = 'fission_rate_from_power'
    expression = 'if(t<=55209600,fr,0)'
  []
  [d1_function]
    type = ParsedFunction
    expression = 'exp(t/4.5e25)'
  []
[]

[BCs]
  # fix temperature on free surface
  [freesurf_temp]
    type = FunctionDirichletBC
    variable = temperature
    function = temp_bc
    boundary = exterior
  []
[]

[NuclearMaterials]
  fission_operation = 'Normal'
  physics = 'Thermal'
  initial_temperature = 923.15
  elements_tracked = 'Ag'
  elements_initial_concentration = '0.0'
  element_scaling = '1e14'
  use_automatic_differentiation = false
  [ParticleFuel]
    [UCO]
      fuel_type = UCO
      particle_fuel_models = 'Burnup Diffusion'
      diffusion_1st_coefficients = '6.7e-9'
      diffusion_1st_activation_energies = '165e3'
      diffusion_2nd_coefficients = '0'
      diffusion_2nd_activation_energies = '0'
      block = fuel
      fission_rate_function = fission_rate
      fast_neutron_fluence_function = fast_neutron_fluence
      initial_density = 10400.0
      average_grain_radius = 10e-6
      triso_geometry = particle_geometry
    []
  []
  [ParticleLayers]
    layers_models = 'Diffusion'
    fuel_type = UCO
    [SiC]
      [SiC_layer]
        block = SiC
        diffusion_1st_coefficients = '3.6e-9'
        diffusion_1st_activation_energies = '215e3'
        diffusion_2nd_coefficients = '0'
        diffusion_2nd_activation_energies = '0'
        initial_density = 3200.0
        thermal_conductivity_model = miller
      []
    []
    [IPyC]
      [IPyC_layer]
        block = IPyC
        diffusion_1st_coefficients = '5.3e-9'
        diffusion_1st_activation_energies = '154e3'
        initial_density = 1900.0
        thermal_conductivity = 4.0
        specific_heat = 720.0
      []
    []
    [OPyC]
      [OPyC_layer]
        block = OPyC
        diffusion_1st_coefficients = '5.3e-9'
        diffusion_1st_activation_energies = '154e3'
        initial_density = 1900.0
        thermal_conductivity = 4.0
        specific_heat = 720.0
      []
    []
    [Buffer]
      [Buffer_layer]
        block = buffer
        diffusion_1st_coefficients = '1e-8'
        diffusion_1st_activation_energies = '0'
        initial_density = 1050.0
      []
    []
  []
[]

[Dampers]
  [temp]
    type = MaxIncrement
    variable = temperature
    max_increment = 50
  []
[]

[Debug]
  show_var_residual_norms = true
  show_var_residual = 'temperature'
[]

[Preconditioning]
  [smp]
    type = SMP
    full = true
  []
[]

[Executioner]
  type = Transient
  solve_type = 'PJFNK' # Shall we switch to 'Newton'?
  # solve_type = 'Newton'

  petsc_options_iname = '-pc_type -pc_factor_mat_solver_package'
  petsc_options_value = 'lu superlu_dist'

  line_search = 'none'

  nl_rel_tol = 1e-6
  nl_abs_tol = 1e-12
  nl_max_its = 50

  l_tol = 1e-4
  l_max_its = 50

  start_time = 0.0
  end_time = 55209600
  num_steps = 1500

  dt = 86400
  dtmax = 86400
  dtmin = 100

  [TimeStepper]
    type = FunctionDT
    function = 'if(t<55209600,86400,1800)'
  []
  automatic_scaling = true
  compute_scaling_once = false
[]

[Postprocessors]
  [_dt]
    type = TimestepSize
    execute_on = timestep_end
  []

  ### Temperature
  [temp_min]
    type = NodalExtremeValue
    variable = temperature
    value_type = 'min'
    execute_on = 'initial timestep_end'
  []
  [temp_max]
    type = NodalExtremeValue
    variable = temperature
    value_type = 'max'
    execute_on = 'initial timestep_end'
  []

  ### Postprocessors for CO production
  [total_fission_rate]
    type = ElementIntegralPower
    variable = temperature
    fission_rate = fission_rate
    block = fuel
    energy_per_fission = 1.0
    outputs = exodus
    execute_on = 'initial timestep_end'
  []
  [total_fissions]
    type = TimeIntegratedPostprocessor
    value = total_fission_rate
    outputs = exodus
    execute_on = 'initial timestep_end'
  []

  ##### irradiation conditions
  [particle_power]
    type = ElementIntegralPower
    variable = temperature
    use_material_fission_rate = true
    fission_rate_material = fission_rate
    block = fuel
    execute_on = 'initial timestep_end'
  []

  [max_fluence]
    type = ElementExtremeValue
    variable = fast_neutron_fluence
    value_type = 'max'
    execute_on = 'initial timestep_end'
  []

  [max_burnup]
    type = ElementExtremeValue
    variable = burnup
    block = fuel
    value_type = 'max'
    execute_on = 'initial timestep_end'
  []
[]

[Outputs]
  perf_graph = true
  print_linear_residuals = false
  [console]
    type = Console
    time_step_interval = 1
  []
  [exodus]
    type = Exodus
    file_base = COMPACT
  []
  [release]
    type = CSV
    file_base = release_COMPACT
    sort_columns = true
  []
  [final_release]
    type = CSV
    file_base = final_release_COMPACT
    sort_columns = true
    execute_on = 'final'
  []

[]

(assessment/TRISO/validation/AGR-1/AGR-1_action.i)

#COMPACT = <compact_id>
#DATA_FILE = <data_file_name>

[GlobalParams]
  order = SECOND
  family = LAGRANGE
  initial_enrichment = 0.19736 # [wt-]
  energy_per_fission = 3.204e-11 # [J/fission]
  O_U = 1.3613 # Initial Oxygen to Uranium atom ratio
  C_U = 0.3253 # Initial Carbon to Uranium atom ratio
  mass_source_property_OPyC = 7.06e-7 # Default = UCO fuel kernel
  extra_vector_tags = 'ref'
  use_displaced_mesh = false
[]

[Mesh]
  coord_type = RSPHERICAL
  [gen]
    type = TRISO1DFiveLayerMeshGenerator
    elem_type = EDGE3
    kernel_radius = 175e-6
    buffer_thickness = 100e-6
    IPyC_thickness = 40e-6
    SiC_thickness = 35e-6
    OPyC_thickness = 40e-6
    kernel_mesh_density = 18
    buffer_mesh_density = 14
    IPyC_mesh_density = 6
    SiC_mesh_density = 8
    OPyC_mesh_density = 6
    block_names = 'fuel buffer IPyC SiC OPyC'
    include_gap = false
    kernel_bias = 0.8
    buffer_bias = 1.25
  []
[]

[Problem]
  type = ReferenceResidualProblem
  reference_vector = 'ref'
  extra_tag_vectors = 'ref'
[]

[UserObjects]
  [particle_geometry]
    type = TRISOGeometry
    outer_OPyC = OPyC_outer_boundary
    outer_SiC = SiC_outer_boundary
    outer_IPyC = IPyC_outer_boundary
    inner_IPyC = IPyC_inner_boundary
    outer_buffer = buffer_outer_boundary
    outer_kernel = fuel_outer_boundary
    include_particle = true
    include_pebble = false
  []
[]

[Functions]
  [temp_bc_file]
    type = PiecewiseLinear
    #data_file = DATA_FILE
    x_index_in_file = 0
    y_index_in_file = 1
    xy_in_file_only = false
    format = columns
  []
  [temp_bc_safety]
    type = ParsedFunction
    symbol_names = 'test_temperature'
    symbol_values = '1873.15'
    expression = 'start := 55209600+1800;
             ramp1 := 120.0/3600.0;
             ramp2 := 120.0/3600.0;
             ramp3 := 50.0/3600.0;
             ramp4 := -600.0/3600.0;
             room := 303.15;
             plateau1 := 673.15;
             plateau2 := 1523.15;
             hold1 := 7200;
             hold2 := 43200;
             hold3 := 1080000;
             ramp_time1 := (plateau1-room)/ramp1;
             ramp_time2 := (plateau2-plateau1)/ramp2;
             ramp_time3 := (test_temperature-plateau2)/ramp3;
             ramp_time4 := (room-test_temperature)/ramp4;
             t1 := start+ramp_time1;
             t2 := t1+hold1;
             t3 := t2+ramp_time2;
             t4 := t3+hold2;
             t5 := t4+ramp_time3;
             t6 := t5+hold3;
             t7 := t6+ramp_time4;
             if(t<start,room,
             if(t<t1,room+(t-start)*ramp1,
             if(t<t2,plateau1,
             if(t<t3,plateau1+(t-t2)*ramp2,
             if(t<t4,plateau2,
             if(t<t5,plateau2+(t-t4)*ramp3,
             if(t<t6,test_temperature,
             if(t<t7,test_temperature+(t-t6)*ramp4,
             room))))))))'
  []
  [temp_bc]
    type = ParsedFunction
    symbol_names = 'tbcf tbcs'
    symbol_values = 'temp_bc_file temp_bc_safety'
    expression = 'if(t<=55209600,tbcf,tbcs)'
  []
  [power_history] # W/m^3
    type = PiecewiseLinear
    #data_file = DATA_FILE
    x_index_in_file = 0
    y_index_in_file = 2
    xy_in_file_only = false
    format = columns
  []
  [fast_neutron_fluence]
    type = PiecewiseLinear
    #data_file = DATA_FILE
    x_index_in_file = 0
    y_index_in_file = 3
    xy_in_file_only = false
    format = columns
  []
  [fission_rate_from_power]
    type = LinearCombinationFunction
    functions = power_history
    # W/m^3 / (1.602e-13 J/MeV) / (200 MeV/fission)
    w = 3.1211e10
  []
  [fission_rate]
    type = ParsedFunction
    symbol_names = 'fr'
    symbol_values = 'fission_rate_from_power'
    expression = 'if(t<=55209600,fr,0)'
  []
  [d1_function]
    type = ParsedFunction
    expression = 'exp(t/4.5e25)'
  []
[]

[BCs]
  # fix temperature on free surface
  [freesurf_temp]
    type = FunctionDirichletBC
    variable = temperature
    function = temp_bc
    boundary = exterior
  []
[]

[NuclearMaterials]
  fission_operation = 'Normal'
  physics = 'Thermal'
  initial_temperature = 923.15
  elements_tracked = 'Ag'
  elements_initial_concentration = '0.0'
  element_scaling = '1e14'
  use_automatic_differentiation = false
  [ParticleFuel]
    [UCO]
      fuel_type = UCO
      particle_fuel_models = 'Burnup Diffusion'
      diffusion_1st_coefficients = '6.7e-9'
      diffusion_1st_activation_energies = '165e3'
      diffusion_2nd_coefficients = '0'
      diffusion_2nd_activation_energies = '0'
      block = fuel
      fission_rate_function = fission_rate
      fast_neutron_fluence_function = fast_neutron_fluence
      initial_density = 10400.0
      average_grain_radius = 10e-6
      triso_geometry = particle_geometry
    []
  []
  [ParticleLayers]
    layers_models = 'Diffusion'
    fuel_type = UCO
    [SiC]
      [SiC_layer]
        block = SiC
        diffusion_1st_coefficients = '3.6e-9'
        diffusion_1st_activation_energies = '215e3'
        diffusion_2nd_coefficients = '0'
        diffusion_2nd_activation_energies = '0'
        initial_density = 3200.0
        thermal_conductivity_model = miller
      []
    []
    [IPyC]
      [IPyC_layer]
        block = IPyC
        diffusion_1st_coefficients = '5.3e-9'
        diffusion_1st_activation_energies = '154e3'
        initial_density = 1900.0
        thermal_conductivity = 4.0
        specific_heat = 720.0
      []
    []
    [OPyC]
      [OPyC_layer]
        block = OPyC
        diffusion_1st_coefficients = '5.3e-9'
        diffusion_1st_activation_energies = '154e3'
        initial_density = 1900.0
        thermal_conductivity = 4.0
        specific_heat = 720.0
      []
    []
    [Buffer]
      [Buffer_layer]
        block = buffer
        diffusion_1st_coefficients = '1e-8'
        diffusion_1st_activation_energies = '0'
        initial_density = 1050.0
      []
    []
  []
[]

[Dampers]
  [temp]
    type = MaxIncrement
    variable = temperature
    max_increment = 50
  []
[]

[Debug]
  show_var_residual_norms = true
  show_var_residual = 'temperature'
[]

[Preconditioning]
  [smp]
    type = SMP
    full = true
  []
[]

[Executioner]
  type = Transient
  solve_type = 'PJFNK' # Shall we switch to 'Newton'?
  # solve_type = 'Newton'

  petsc_options_iname = '-pc_type -pc_factor_mat_solver_package'
  petsc_options_value = 'lu superlu_dist'

  line_search = 'none'

  nl_rel_tol = 1e-6
  nl_abs_tol = 1e-12
  nl_max_its = 50

  l_tol = 1e-4
  l_max_its = 50

  start_time = 0.0
  end_time = 55209600
  num_steps = 1500

  dt = 86400
  dtmax = 86400
  dtmin = 100

  [TimeStepper]
    type = FunctionDT
    function = 'if(t<55209600,86400,1800)'
  []
  automatic_scaling = true
  compute_scaling_once = false
[]

[Postprocessors]
  [_dt]
    type = TimestepSize
    execute_on = timestep_end
  []

  ### Temperature
  [temp_min]
    type = NodalExtremeValue
    variable = temperature
    value_type = 'min'
    execute_on = 'initial timestep_end'
  []
  [temp_max]
    type = NodalExtremeValue
    variable = temperature
    value_type = 'max'
    execute_on = 'initial timestep_end'
  []

  ### Postprocessors for CO production
  [total_fission_rate]
    type = ElementIntegralPower
    variable = temperature
    fission_rate = fission_rate
    block = fuel
    energy_per_fission = 1.0
    outputs = exodus
    execute_on = 'initial timestep_end'
  []
  [total_fissions]
    type = TimeIntegratedPostprocessor
    value = total_fission_rate
    outputs = exodus
    execute_on = 'initial timestep_end'
  []

  ##### irradiation conditions
  [particle_power]
    type = ElementIntegralPower
    variable = temperature
    use_material_fission_rate = true
    fission_rate_material = fission_rate
    block = fuel
    execute_on = 'initial timestep_end'
  []

  [max_fluence]
    type = ElementExtremeValue
    variable = fast_neutron_fluence
    value_type = 'max'
    execute_on = 'initial timestep_end'
  []

  [max_burnup]
    type = ElementExtremeValue
    variable = burnup
    block = fuel
    value_type = 'max'
    execute_on = 'initial timestep_end'
  []
[]

[Outputs]
  perf_graph = true
  print_linear_residuals = false
  [console]
    type = Console
    time_step_interval = 1
  []
  [exodus]
    type = Exodus
    file_base = COMPACT
  []
  [release]
    type = CSV
    file_base = release_COMPACT
    sort_columns = true
  []
  [final_release]
    type = CSV
    file_base = final_release_COMPACT
    sort_columns = true
    execute_on = 'final'
  []

[]

Description
User - based Interface
Example Fully Reduced Input Syntax
Example Input File Syntax