BumpTest LWRNuclearMaterials

This tutorial is currently under development.

An pre-existing assessment case already exists in:

[NuclearMaterials<<<{"href": "../../syntax/NuclearMaterials/index.html"}>>>]
  generate_output<<<{"description": "Add scalar quantity output for stress and/or strain"}>>> = 'vonmises_stress stress_xx stress_yy stress_zz'
  fission_operation<<<{"description": "Type of fission occuring in this simulation."}>>> = 'BumpTest'
  physics<<<{"description": "Type(s) of physics used on this block."}>>> = 'Mechanics Thermal'
  initial_temperature<<<{"description": "Initial temperature in Kelvins."}>>> = ${initial_temperature}
  stress_free_temperature<<<{"description": "Reference temperature for thermal eigenstrain calculation"}>>> = ${stress_free_temperature}
  strain<<<{"description": "Strain formulation"}>>> = FINITE
  [UO2<<<{"href": "../../syntax/NuclearMaterials/UO2/index.html"}>>>]
    [fuel]
      block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = 'pellet_type_2 pellet_type_3'
      uo2_models<<<{"description": "Type(s) of physics models used on this block.   The choices are: Burnup Elastic Creep Relocation Swelling ThermalExpansion HighBurnupStructureFormation"}>>> = 'Burnup Elastic Relocation Swelling ThermalExpansion'
      isotopes<<<{"description": "Fuel isotopes: Gd155 Gd157 U235 U238 Pu239 Pu240 Pu241 Pu242.  Number of entries must match number of entries in isotope_fractions."}>>> = 'U238 U235'
      isotope_fractions<<<{"description": "The isotope fractions associated with the 'isotopes' input line.  Must sum to 1.0."}>>> = '${isotope_fraction_U238} ${isotope_fraction_U235}'
      burnup_relocation_stop<<<{"description": "Burnup at which relocation strain stops (in FIMA)"}>>> = ${burnup_relocation_stop}
      rod_ave_lin_pow<<<{"description": "The rod power history function."}>>> = power_history
      axial_power_profile<<<{"description": "The axial power peaking function."}>>> = axial_peaking_factors
      num_radial<<<{"description": "Number of radial divisions in secondary grid used to compute radial power profile."}>>> = ${num_radial_burnup}
      num_axial<<<{"description": "Number of axial divisions in secondary grid used to compute radial power profile."}>>> = ${num_axial_burnup}
      a_upper<<<{"description": "The upper axial coordinate of the fuel stack. Required if fuel_pin_geometry is not specified."}>>> = ${a_upper}
      a_lower<<<{"description": "The lower axial coordinate of the fuel stack. Required if fuel_pin_geometry is not specified."}>>> = ${a_lower}
      fuel_inner_radius<<<{"description": "The inner radius of the fuel."}>>> = ${fuel_inner_radius}
      fuel_outer_radius<<<{"description": "The outer radius of the fuel."}>>> = ${fuel_outer_radius}
      fuel_volume_ratio<<<{"description": "Reduction factor for deviation from right circular cylinder representation of the fuel mesh.  The ratio of actual volume to right circular cylinder volume."}>>> = ${fuel_volume_ratio}
      fraction_of_neutron_heat_source<<<{"description": "Fraction of neutron heat source power applied"}>>> = ${heat_source_fraction}
      additional_generate_output<<<{"description": "Add scalar quantity output for stress and/or strain (will be appended to the list in `generate_output`)"}>>> = 'hydrostatic_stress'
    []
  []
  [Insulator<<<{"href": "../../syntax/NuclearMaterials/Insulator/index.html"}>>>]
    [insulator]
      block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = 'pellet_type_1 pellet_type_4'
      insulator_models<<<{"description": "Type(s) of physics models used on this block.   The choices are: Elastic ThermalExpansion"}>>> = 'Elastic ThermalExpansion'
      youngs_modulus<<<{"description": "Young's modulus of the material."}>>> = ${insulator_youngs_modulus}
      poissons_ratio<<<{"description": "Poisson's ratio for the material."}>>> = ${insulator_poissons_ratio}
      thermal_expansion_coeff<<<{"description": "Thermal expansion coefficient"}>>> = ${insulator_thermal_expansion_coeff}
      thermal_conductivity<<<{"description": "The thermal conductivity value"}>>> = ${insulator_thermal_conductivity}
      specific_heat<<<{"description": "The specific heat value"}>>> = ${insulator_specific_heat}
      density<<<{"description": "Initial insulator density"}>>> = ${insulator_density}
    []
  []
  [ZirconiumAlloy<<<{"href": "../../syntax/NuclearMaterials/ZirconiumAlloy/index.html"}>>>]
    [clad]
      block<<<{"description": "The list of ids of the blocks (subdomain) that the stress divergence kernels will be applied to"}>>> = clad
      cladding_models<<<{"description": "Type(s) of physics models used on this block.   The choices are: Creep Elastic Plasticity ZryOxidation IrradiationGrowth ThermalExpansion ZrPhase ZryCladdingFailure"}>>> = 'Elastic Creep IrradiationGrowth ThermalExpansion'
      flux_function<<<{"description": "Function which contains the neutron flux data."}>>> = flux
      additional_generate_output<<<{"description": "Add scalar quantity output for stress and/or strain (will be appended to the list in `generate_output`)"}>>> = 'creep_strain_xx creep_strain_yy
        creep_strain_xy creep_strain_zz'
    []
  []
[]