# Bison Only Code Reference Manual

Given below are the reference pages for all of the Bison specific code. To see a complete list of all of the possible input parameter options and the associated reference pages for Bison and the MOOSE Modules code, view the Complete Code Manual.

Click the blue links in the class names shown below to view the detailed description the class purpose, theoretical models, input file examples, and references.

## AuxKernels*input*

- Al2O3AuxCalculates the Aluminum oxide thickness with either the Griess model or a user-defined function
- BurnupAuxCompute burnup given fission_rate, density, and molecular_weight.
- BurnupGridRetrieve burnup, fission_rate, concentrations, etc. from the grid used in BurnupFunction. Built by an Action.
- BurnupMetalAux
- CoolantAux
- CumulativeDamageIndexCalculates the cumulative damage to cladding for low temperature steady-state conditions
- EffectiveBurnupAuxCompute effective burnup given temperature and local burnup
- EutecticThicknessFCCICalculates eutectic penetration thickness based on boundary temperature.
- FastNeutronFluenceAuxCompute fast neutron fluence from fast_neutron_flux.
- FastNeutronFluxAuxCompute fast neutron flux.
- FeCrAlOxideAuxCalculates the oxidation and corrosion of FeCrAl cladding
- FissionRateAuxGive a scaled value of a function that can be used to set fission rate. Similar to FuntionAux.
- FissionRateAuxLWRCompute fission rate based on common LWR parameters.
- FissionRateAxialAuxCalculates the amount of fission rate based on relative axial position from the ends of the fuel stack
- FissionRateFromPowerDensityCompute fission rate based on power density.
- FissionRateMOXCompute fission rate for right circular cylinder fast MOX fuel taking porosity into account.
- GapValueDefaultSameValue
- GrainRadiusAuxEmpirical model for calculating grain evolution
- GrainRadiusPorosity
- HydridePrecipitationAuxCalculates the hydrides precipitation and dissolution
- MassFluxAuxCalculates the flux of a species concentration along a specified axis
- MaxFissionRateAuxReturns the maximum fission rate value
- OxideAuxThis class incorporates correlations for Zircaloy cladding oxidation through metal-water reactions.
- PelletIdAuxComputes a pellet number
- PercolationAuxMark elements as part of a percolated path to the surface
- PlenumTemperatureDistance
- PorosityAuxUO2
- PowerFunctionAux
- Radius
- ScalarStrainAuxClass for assembling scalar strains into one aux variable
- ThicknessLayerFCCICalculates the FCCI layer thickness using the boundary mass flux.
- UO2IsotropicDislocationDensityCalculates an effective isotropic dislocation density for UO2 fuel by smearing the sum of the dislocations across all of the slip planes; uses a Kocks-type dislocation density model.

## AuxVariables*input*

## BCs*input*

- ConvectiveFluxLWRBC
- DryCaskHeatFluxApplies a boundary condition that models fuel rod in a dry cask storage system. The rod is assumed to be the center rod in an assembly of identical rods so that the peak cladding temperature is reached. This uses the Manteufel and Trodreas correlations inside the assembly and models the assembly-to-ambient flux using a single parameter.
- GapHeatTransferLWRBC that aids with thermal contact similar to GapHeatTransfer
- GapPerfectConductance
- HydrogenFluxBC
- HydrogenFluxBC_simplified
- HydrogenPickupHydrogen flux BC that simply multiplies the time derivative of the oxide thickness by a pickup factor to get flux. Units are for H concentration in wt.ppm.
- PostprocessorBulkCoolantBC
- REBEKADirichletBC
- StanNeumannBC
- SubmodelEndBCspecial type of Preset BC that is applied only above and below the ends of a submodel, as determined by postprocessors
- PlenumPressure

### BCs/PlenumPressure*input*

- PlenumPressureUOActionSets up the calculation of the plenum pressure as a function of temperature, plenum volume, and moles of fission and plenum gases.

## Burnup*input*

- BurnupAuxKernelsActionCreates the set of auxkernels required to collect the radial average burnup and heavy metal isotope concentrations as calculated by the BurnupFunction
- BurnupAuxVarsActionCreates the set of auxvariables required to store the radial average burnup and heavy metal isotope concentrations as calculated by the BurnupFunction
- BurnupFunctionActionComputes the radial distributions of power density, burnup, and concentrations of various heavy metal isotopes in UO2 and U3Si2 fuels for LWRs

## CladdingHydrides*input*

- HydrideActionAction to add kernels and materials to model hydride formation in the cladding (does not include hydrogen pickup).

## CoolantChannel*input*

## DefaultElementQuality*input*

- CheckElementQualityActionAction to create a default set of ElementQualityChecker UserObjects

## Functions*input*

- BurnupFunctionCompute burnup and radial power factor. Built by an Action.
- CladdingAxialPressureFunctionComputes the axial pressure applied to the cladding from the coolant and plenum pressure
- PowerPeakingFunction

## ICs*input*

## Kernels*input*

- ArrheniusDiffusionDiffusion with Arrhenius coefficient
- CompositeHeatConductionCompute thermal conductivity
- ConstituentDiffusion
- ConstitutiveHeatConductionThe Laplacian operator (), with the weak form of .
- ConstitutiveHeatConductionTimeDerivativeTime derivative term of the heat equation for quasi-constant specific heat and the density .
- Decay
- DiffusionLimitedReactionCalculates losses due to diffusion limited reaction
- FissionRateHeatSource
- HZrHSource
- HydrideSourceAdd source (sink) term for precipitation (dissolution) of hydrogen as hydride
- HydrogenDiffusionCalculates the diffusion of hydrogen in solid solution due to Fick's law and the Soret effect
- HydrogenPrecipitationCalculates the precipitation of hydrogen in solid solution from McMinn's TSSp equilibrium and the dissolution hydrides to solid solution hydrogen from Marino's kinetics
- HydrogenSourceAdd source (sink) term for dissolved hydrogen from hydride dissolution (precipitation)
- HydrogenTimeDerivativeTime derivative for species where the volume fraction of the phase is time-dependent.
- IsotropicDiffusionIsotropic diffusion that uses arbitrary diffusivity
- MOXActinideRedistributionMOX kernel used to simulate actinide redistribution.
- MOXActinideRedistributionEnhancementMOX kernel used to simulate actinide redistribution enhanced by porosity.
- MOXOxygenDiffusionMOX oxygen diffusion kernel.
- MOXPoreContinuityMOX kernel used to simulate pore migration.
- MOXPoreDiffusionMOX porosity diffusion kernel used with kernel MOXPoreContinuity.
- NeutronHeatSourceCompute heat generation due to fission.
- OxideEnergyDepositionComputes the amount of energy released from the zirconium oxide reaction and applies it to the cladding.
- OxygenDiffusion
- ZirconiumDiffusionCalculates the amount of zirconium that is transported across the mesh

## Materials*input*

- ArrheniusDiffusionCoefComputes a two-term Arrhenius diffusion coefficient
- ArrheniusMaterialPropertyArbitrary material property of the form A * exp(-Q / RT), where A is the frequency factor, Q is the activation energy, and R is the gas constant.
- ChromiumCreepUpdateCalculates the thermal creep behavior pure chromium. This material must be run in conjunction with ComputeMultipleInelasticStress.
- ChromiumElasticityTensorCalculates the Young's modulus and Poisson's ratio for pure chromium using relations as a function of temperature.
- ChromiumOxidationThis class computes the oxide mass gain and oxide scale thickness for pure chromium.
- ChromiumPlasticityUpdateCalculates the plastic strain as a function of strain rate for pure chromium. Note: This material must be run in conjunction with ComputeMultipleInelasticStress.
- ChromiumThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion for pure chromium using a function that describes the mean thermal expansion as a function of temperature.
- CompositeSiCElasticityTensorComputes the orthotropic axisymmetric RZ elasticity tensor for composite (CVI) SiC/SiC with the fibers oriented in the axial direction.
- CompositeSiCThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion using a function that describes the instantaneous thermal expansion as a function of temperature for composite (CVI) SiC/SiC.
- CoolantChannelMaterial
- CoupledThermalUO2Gas/Fuel thermal conductivity from concurrently coupled mesoscale data and specific heat from Fink model
- CreepFastMOXModelModels the creep behavior of fast MOX
- CreepMOXCalculates the thermal and irradiation creep of MOX fuel
- CreepPyCModels the creep behavior of pyrolytic carbon
- CreepSiCModels the creep behavior of silicon carbide
- CreepU10MoModels the thermal and irradiation creep behavior of U-10Mo fast fuel
- CreepUO2Models the creep behavior of UO2
- CreepUPuZrModels the thermal and irradiation creep behavior of U-Pu-Zr fast reactor fuel
- CreepUPuZrModel
- CreepZryModelThe default constitutive model used in MechZry
- FailureCladHT9Failure model for HT-9 cladding. Contains multiple models for steady state (burnup calculations) and transient operations.
- FailureCladdingModels and sets the failure of Zircaloy-4 cladding due to burst in a LOCA event
- FailureFeCrAlFailure model for FeCrAl cladding, with an option for the failure criterion based on the ultimate tensile stress or the failure criterion based on the temperature
- FastMOXCreepUpdateModels the creep behavior of fast MOX
- FeCrAlCladdingFailureA failure model for FeCrAl cladding. Three failure criteria exist including ultimate tensile strength, tresca criterion, and an Idaho National Laboratory developed criterion.
- FeCrAlCreepUpdateCalculates the thermal and irradiation creep behavior of FeCrAl cladding alloys. This material must be run in conjunction with ComputeMultipleInelasticStress.
- FeCrAlElasticityTensorCalculates Young's modulus and Poisson's ratio as a function of temperature for FeCrAl alloys.
- FeCrAlOxidationThis class computes the oxide mass gain and oxide scale thickness for the C35M FeCrAl alloy.
- FeCrAlPlasticityUpdateCalculates the plastic strain as a function of strain rate for FeCrAl cladding. Note: This material must be run in conjunction with ComputeMultipleInelasticStress.
- FeCrAlThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion using a function that describes the mean thermal expansion as a function of temperature. The function is calculated internally based upon the FeCrAl alloy of interest.
- FeCrAlVolumetricSwellingEigenstrainCalculates the change in cladding volume due to irradiation by fast neutrons. This class applies a volumetric strain correction before adding the strain from this class to the diagonal entries of the eigenstrain tensor.
- FgrFraction
- FgrUPuZrFission gas release model for UPuZr metal fuel
- ForMasOutdated model. It's recommended to use Sifgrs instead
- GapConductanceLWR
- GenericMaterialFailureGeneric class for use in setting the failed material property.
- HT9CreepUpdateThermal and irradiation creep for HT9 based on M. B. Toloczko et al (1999) 18th Symposium ASTM-1325 for tensor mechanics. Must be used in conjunction with ComputeMultipleInelasticStress.
- HotPressingUO2Models the stress induced densification of UO2
- HydridePrecipitationRateCalculates the preciptation or dissolution rate of hydrogen to ZrHx in Zr cladding.
- HydrogenDiffusivityExtends ArrheniusMaterialProperty by also accounting for reduction in diffusivity due to volume fraction less than unity.
- IrradiationGrowthZr4Model that incorporates anisotropic volumetric swelling to track axial elongation in Zr4 cladding
- IsoPlasticityFeCrAlCalculates the isotropic plasticity of FeCrAl
- MAMOXElasticityTensorSets the Young's modulus and Poisson's ration for MAMOX fuel using values from JAEA
- MAMOXThermalExpansionEigenstrainCalculates eigenstrain due to isotropic thermal expansion in MA-MOX fuel using JNM 469 (2016) 223-227 correlations
- MOXCreepMATPROUpdateCalculates the steady state thermal and irradiation creep for MOX fuel according to MATPRO and Guerrin (1985), respectively. This material must be run in conjunction with ComputeMultipleInelasticStress.
- MOXOxygenPartialPressureCalculates oxygen partial pressure and corresponding integral. Used with material MOXVaporPressure and MOXPoreVelocityVaporPressure.
- MOXPoreVelocityCalculates pore speed. Used with kernel MOXPoreContinuity.
- MOXPoreVelocityVaporPressureCalculates pore speed from author Kato. Used with vapor pressure calculations from MOXVaporPressure.
- MOXVaporPressureParsed Function Material with automatic derivatives.
- MechAlloy33Calculates the linear thermal expansion strain and the isotropic elasticity constants for Alloy33
- MechFeCrAlComputes the elastic moduli, coefficient of thermal expansion, and thermal creep of FeCrAl alloys
- MechFeCrAlModelThe default constitutive model used in MechFeCrAl
- MechHT9Computes mechanical properties of HT9 martensitic steel
- MechMAMOXComputes the thermal expansion of minor actinide doped mixed oxide fast fuel
- MechMoComputes mechanical properties of molybdenum
- MechSS316Computes mechanical properties of stainless steel 316
- MechSS316TabularComputes mechanical properties of Stainless Steel 316
- MechU3Si5UNCalculates mechanical properties of U3Si5UN
- MechUO2Models the stress induced densification of UO2
- MechUPuZrCalculates mechanical properties and thermal expansion of U-Pu-Zr fast reactor fuel
- MechZryModel that includes the options to model primary, thermal, and irradiation-induced creep
- MoElasticityTensorCalculates the Young's modulus for Molybdenum cladding as a function of temperature; Poisson's ratio is held constant
- MoThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion using a function that describes the mean thermal expansion as a function of temperature.
- MonolithicSiCElasticityTensorCalculates the Young's modulus and Poisson's ratio for monolithic silicon carbide (CVD) cladding using relations as a function of temperature.
- MonolithicSiCThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion using a function that describes the mean thermal expansion as a function of temperature for monolithic (CVD) silicon carbide.
- Nicrofer3033ElasticityTensorCalculates the Young's modulus for Nicrofer3033 cladding using IFR equation for Young's modulus as a function of temperature; Poisson's ratio is held constant
- Nicrofer3033ThermalExpansionEigenstrainCalculates eigenstrain due to linear thermal expansion in Nicrofer3033, or Alloy 33, cladding using a constant thermal expansion coefficient
- NuclearSystemsMaterialsHandbookSS316CreepUpdateThermal and irradiation creep for protypic heats of 20 percent cold worked SS AISI 316 Nuclear Systems Materials Handbook Revision 5
- OxidationCladdingModel that incorporates correlations for Zircaloy cladding oxidation through metal-water reactions
- PhaseUPuZrProperty that determines the phase for a given temperature and Zr atom concentration from the pseudo-binary phase diagram for U-Pu-Zr fuel.
- PorosityMOX
- PyCCreepComputes the irradiation creep for PyC in an implicit manner
- PyCIrradiationStrainModel that tracks the irradiation-induced strain in pyrolytic carbon
- RadioActiveDecayConstant
- RelocationRecoveryUO2Recovers 50 percent of the fuel relocation eigenstrain from fuel pellet cracking once mechanical contact between the fuel and cladding occurs
- RelocationUO2This model accounts for cracking and relocation of fuel pelletfragments in the radial direction
- SS316CreepUpdateThermal and irradiation creep for SS AISI 316 based on: 'High Temperature Inelastic Behavior of the Austenitic Steel AISI Type 316' by H. Altenbach and Y. Gorash, 2013 'Irradiation Creep and Swelling of AISI 316 to Exposures of 130 dpa at 385-400 degrees C' by F. Garner and D. Porter
- SS316ElasticityTensorCalculates the Young's modulus and Poisson's ratio for Stainless Steel 316 cladding using relations as a function of temperature.
- SS316ThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion for Stainless Steel 316 using a function that describes the mean thermal expansion as a function of temperature.
- SiCCreepUpdateIrradiation creep for SiC based on Lewinsohn, et al. JNM (2004); this class must be used in conjunction with ComputeMultipleInelasticStress.
- SifgrsRecommended fission gas model to account for generation of fission gasses in nuclear fuel
- ThermIrradCreepZr4Zr2Recommended creep calculation model for cases where cladding experiences multiple load reversals and load drops
- Thermal316Computes thermal properties of stainless steel 316
- ThermalAlloy33Computes thermal properties of nickal-base alloy PK33
- ThermalChromiumComputes thermal conductivity and specific heat of pure chromium.
- ThermalCompositeSiCComputes thermal conductivity and specific heat of composite (CVI) SiC/SiC cladding.
- ThermalD9
- ThermalExpansionUPuZr
- ThermalFastMOXComputes the thermal conductivity for fast MOX fuel
- ThermalFeCrAlModel that computes the specific heat and thermal conductivity for FeCrAl cladding alloys.
- ThermalFuelModel that computes specific heat and thermal conductivity for oxide fuel.
- ThermalHT9Computes thermal properties of HT9 martensitic steel
- ThermalIrradiationCreepHT9Models thermal and irradiation creep in HT9 martensitic steel
- ThermalIrradiationCreepPlasZr4Calculates combined instantaneous plasticity and time-dependent creep
- ThermalIrradiationCreepZr4Object used for Zr4 cladding in LWR simulations
- ThermalMAMOXComputes the thermal conductivity for minor actinide fast MOX fuel
- ThermalMoComputes thermal properties of molybdenum
- ThermalMonolithicSiCComputes thermal conductivity and specific heat of monolithic (CVD) silicon carbide cladding.
- ThermalNa
- ThermalSilicideFuelComputes the specific heat and thermal conductivity for different phases of uranium silicide fuel
- ThermalUComputes thermal properties of uranium metal
- ThermalU10MoCalculates thermal properties of low enriched uranium-molybdenum alloy
- ThermalU3Si5UNCalculates thermal properties of U3Si5UN
- ThermalUO2FissionGasModel that computes specific heat and thermal conductivity for oxide fuel.
- ThermalUO2MesoModel that computes specific heat and thermal conductivity for oxide fuel.
- ThermalUO2PX
- ThermalUPuZrMaterial that calculates the thermal conductivity and specific heat for U-Pu-Zr fuels based on mole fractions, porosity, and temperature.
- ThermalZircaloy
- ThermalZrO2Calculates the thermal conductivity and the specific heat, under constant pressure, for zirconium oxide found on fuel rods.
- ThermalZryCalculates the thermal conductivity and the specific heat, under constant pressure, for zirconium alloy cladding based on either the MATPRO or IAEA models.
- U3Si2CreepUpdateCalculates the thermal creep behavior of U3Si2 fuel. This material must be run in conjunction with ComputeMultipleInelasticStress.
- U3Si2FissionGasCalculates fission gas release and swelling in U3Si2 through a physically-based model.
- U3Si2ThermalExpansionEigenstrainComputes eigenstrain due to thermal expansion using a function that describes the instantaneous thermal expansion as a function of temperature for U3Si2 fuel.
- U3Si2VolumetricSwellingEigenstrainCalculates and sums the change in fuel pellet volume due to densification and fission product release. This class applies a volumetric strain correction before adding the strain from this class to the diagonal entries of the eigenstrain tensor.
- U3Si5UNElasticityTensorSets the Young's modulus and Poisson's ratio for U3Si5UN fuel using values from the IFR Handbook
- U3Si5UNThermalExpansionEigenstrainCalculates eigenstrain due to isotropic thermal expansion in U3Si5UN fuel using a correlation from the IFR Handbook
- UNVolumetricSwellingEigenstrainCalculates the change in volume due to swelling in UN fuel. This class applies a volumetric strain correction before adding the strain from this class to the diagonal entries of the eigenstrain tensor.
- UO2AxialRelocationEigenstrainThis model accounts for the in the effective diameter of a crumbled layer of fuel during axial relocation under Loss of Coolant Conditions.
- UO2CreepUpdateCalculates the secondary thermal and irradiation creep for UO2 LWR fuel. This material must be run in conjunction with ComputeMultipleInelasticStress.
- UO2ElasticityTensorEither provides constant elasticty constants for UO2 fuel or calculates the Young's modulus and/or the Poisson's ratio for UO2 fuel using Matpro relations as a function of temperature, burnup, and fuel composition.
- UO2HotPressingCreepUpdateCalculates the secondary thermal and irradiation creep for UO2 LWR fuel. This material must be run in conjunction with ComputeMultipleInelasticStress.
- UO2HotPressingPlasticityUpdateCalculates the effective inelastic strain increment required to return the isotropic stress state to a J2 yield surface. This class is intended to be a parent class for classes with specific constitutive models.
- UO2IsotropicDamageElasticityTensorCalculates the isotropic elastic constants for UO2 fuel as a scaled function of the number of cracks in the fuel
- UO2PulverizationDetermines whether or not the fuel has pulverized into small fragments during a Loss of Coolant Accident.
- UO2RelocationEigenstrainThis model accounts for cracking and relocation of fuel pellet fragments in the radial direction and is necessary for accurate modeling of LWR fuel. Only one of q and q variable may be given.
- UO2ThermalExpansionMatproEigenstrainCalculates eigenstrain due to thermal expansion in UO2 fuel using MATPRO correlations
- UO2VolumetricSwellingEigenstrainCalculates and sums the change in fuel pellet volume due to densification and fission product release. This class applies a volumetric strain correction before adding the strain from this class to the diagonal entries of the eigenstrain tensor.
- UPuZrAnisotropicSwellingEigenstrainThis model accounts for the anisotropic swelling effect in UPuZr metal fuel.
- UPuZrBurnup
- UPuZrCreepUpdateCalculates the secondary thermal and irradiation creep for UPuZr fast metal fuel. This material must be run in conjunction with ComputeMultipleInelasticStress.
- UPuZrDiffusivityReturns Fickian and Soret diffusion parameters for U-Pu-Zr using phase fractions from UPuZrPhaseLookup
- UPuZrElasticityTensorCalculates the Young's modulus and Poisson's ratio for UPuZr fuel based on supplied fractions of Pu and Zr
- UPuZrFissionRateCompute fission rate based on common LWR parameters.
- UPuZrPhaseLookupReturns U-Pu-Zr phase fractions, equilibrium concentrations, and multi-phase contributions given temperature and composition using a lookup table
- UPuZrVolumetricSwellingEigenstrainCalculates and sums the change in fuel pellet volume due to solid and gaseous fission product buildup in UPuZr.
- VSwellingFeCrAlComputes a volumetric strain to account for irradiation induced swelling of FeCrAl alloys used for cladding
- VSwellingU3Si2Computes a volumetric strain to account for solid and gaseous swelling and densification in U3Si2 fuel
- VSwellingUNCalculates volumetric swelling of uranium nitride
- VSwellingUO2Computes a volumetric strain to account for solid and gaseous swelling and for densification
- VSwellingUPuZrComputes a volumetric strain to account for solid and gaseous swelling and for open pore compression in U-Pu-Zr metal fuel system
- ZrDiffusivityUPuZrProperty that determines Fickian and Soret Diffusivity.
- ZrO2ElasticityTensorComputes the Young's Modulus and Poisson's ratio for zirconium oxide.
- ZrO2ThermalExpansionEigenstrainCalculates eigenstrain due to thermal expansion in zirconium oxide using MATPRO correlations.
- ZrPhaseComputes the volume fraction of beta phase for Zr-based cladding materials as a function of temperature and time
- ZryCladdingFailureModels the failure of Zircaloy-4 cladding due to burst under LOCA conditions
- ZryCreepHayesHoppeUpdateCalculates the secondary thermal Hayes and Kassner secondary creep and the Hoope irradiation creep for Zircaloy cladding. This material must be run in conjunction with ComputeMultipleInelasticStress.
- ZryCreepLOCAErbacherLimbackHoppeUpdateCalculates the Erbacher secondary thermal creep under loss-of-coolant accident conditions, the Limback-Andersson primary thermal creep, and the Hoope irradiation creep for Zircaloy cladding. This material must be run in conjunction with ComputeMultipleInelasticStress.
- ZryCreepLimbackHoppeUpdateCalculates the Limback-Andersson thermal primary and secondary creep and the Hoppe irradiation creep for Zircaloy cladding. This material must be run in conjunction with ComputeMultipleInelasticStress.
- ZryCreepTulkkiHayesHoppeUpdateCalculates the viscoelastic primary creep and secondary thermal Hayes and Kassner creep and the Hoope irradiation creep for Zircaloy cladding. This material must be run in conjunction with ComputeMultipleInelasticStress.
- ZryElasticityTensorEither provides constant elasticty constants for Zircaloy cladding or calculates the Young's modulus and Poisson's ratio for Zircaloy cladding using MATPRO relations as a function of temperature and fast neutron fluence.
- ZryIrradiationGrowthEigenstrainCalculates eigenstrain from irradiation growth in Zircaloy cladding using either the Franklin or ESCORE models
- ZryOxidationThis class incorporates correlations for Zircaloy cladding oxidation through metal-water reactions. Calculated processes include outer oxide scale thickness growth and oxygen mass gain; the model is to be applied to the cladding waterside boundary. Current version covers LWR Zircaloy cladding only.
- ZryPlasticityModels the instantaneous plasticity of the Zry cladding
- ZryPlasticityUpdateCalculates the plastic strain as a function of strain rate for Zircaloy cladding. Note: This material must be run in conjunction with both ComputeMultipleInelasticStress and ZryElasticityTensor.
- ZryThermalExpansionMatproEigenstrainCalculates eigenstrain due to anisotropic thermal expansion in Zircaloy cladding using Matpro correlations

## Mesh*input*

- Layered1DMeshCreates an axisymmetric mesh composed of layers of 1-dimensional elements.
- SmearedPelletMesh
- TRISO1DMesh

## Modules*input*

### Modules/TensorMechanics*input*

#### Modules/TensorMechanics/Layered1DMaster*input*

- Layered1DActionSet up (Aux)variables, materials and (Aux)kernels for layered one dimensional simulations

## NuclearMaterials*input*

### NuclearMaterials/UO2*input*

### NuclearMaterials/ZirconiumAlloy*input*

## PlenumTemperature*input*

## Postprocessors*input*

- AverageAxialPosition
- AverageBurnup
- AverageFissionRate
- CarbonMonoxideProduction
- CrumbledInternalVolumeLayered1DCalculates the total volume of the pellets taking into account layers that may have crumbled during axial relocation.
- DecayHeatFunctionCalculate the decay heat as a fraction of recoverable fission energy using the ANSI/ANS-5.1-2005 Standard.
- ElementIntegralFisGasBoundarySifgrsReports the fission gas that is on the grain boundary
- ElementIntegralFisGasGeneratedSifgrsReports the fission gas that is produced in moles
- ElementIntegralFisGasGrainSifgrsReports the fission gas within the grains
- ElementIntegralFisGasProduce
- ElementIntegralFisGasRelease
- ElementIntegralFisGasReleasedSifgrsReports the fission gas that is released to the plenum in moles
- ElementIntegralPowerComputes the power given the fission rate and energy per fission
- FGRPercentCalculates the ratio of the first user defined value (generally fission gas released) to the second user provided value (generally fission gas generated)
- HeatFluxIntegral
- IFBAHeProductionComputes the Helium gas production as a result of an IFBA layer applied to the surface of a fuel rod
- InternalVolumeLayered1DComputes the volume of an enclosed area by performing an integral over a user-supplied boundary.
- PercolationUserObjectEnhanced FeatureFloodCount that provides a list of clusters that touch a specified boundary
- PlenumTemperatureGives an estimate of the temperature of the gas in the plenum
- RadialAverageEnthalpyUses radial temperature output from a LineValueSampler postprocessor to calculate radial average fuel enthalpy at given axial position for UO2 above 300 K
- RodAverageBurnup
- SideAverageIncrementTensorComponentThis postprocessor computes an volume integral increment of a specified tensor component
- SideAverageValueLayered1DComputes the average value of a variable on a sideset. Note that this cannot be used on the centerline of an axisymmetric model.
- SideFluxIntegralLayered1DComputes the integral of the flux over the specified boundary
- SideIntegralMassFlux
- SideIntegralVariableIncrementPostprocessorThis postprocessor computes an volume integral increment of a variable

## ThermalContact*input*

## UserObjects*input*

- AxialRelocationUserObjectTracks mass movement due to axial relocation of fuel during a Loss of Coolant Accident
- CoolantChannelUserObjectCoolantChannelUserObject is used to compute coolant enthalpy to define the bulk coolant conditions
- FuelPinGeometryCalculates LWR fuel pin geometry by reading the input mesh. This object can be coupled to Burnup and other functions as an alternative to having the user supply parameters such as pellet radius and pellet-cladding gap.
- Layered1DFuelPinGeometryCalculates LWR fuel pin geometry for 1D meshes by reading the input mesh. This object can be coupled to Burnup and other functions as an alternative to having the user supply parameters such as pellet radius and pellet-cladding gap.
- LayeredIntegralLayered1DComputes the volume integral of the layers in a layered 1D mesh.
- PartialSumHeatFluxIntegral
- PartialSumHeatFluxIntegral2D
- PelletBrittleZoneComputes the brittle zone width on a per-pellet basis
- PlenumPressureUserObjectUses the ideal gas law to compute internal pressure and an initial moles of gas quantity.
- U3Si2TricubicInterpolationUserObjectPerforms tricubic interpolation in temperature, temperature gradient, and burnup (fission density) to determine the degradation to the thermal conductivity and gaseous swelling of U3Si2 fuel.