LOCA LWRNuclearMaterials

This tutorial is currently under development.

A 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"}>>> = 'stress_xx stress_yy stress_zz vonmises_stress hoop_stress'
  fission_operation<<<{"description": "Type of fission occuring in this simulation."}>>> = 'LOCA'
  physics<<<{"description": "Type(s) of physics used on this block."}>>> = 'Mechanics Thermal'
  initial_temperature<<<{"description": "Initial temperature in Kelvins."}>>> = 295
  stress_free_temperature<<<{"description": "Reference temperature for thermal eigenstrain calculation"}>>> = 295
  extra_vector_tags<<<{"description": "The tag names for extra vectors that residual data should be saved into"}>>> = 'ref'
  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"}>>> = fuel
      fuel_pin_geometry<<<{"description": "Name of the UserObject that reads the pin geometry from the mesh."}>>> = fuel_pin_geometry
      uo2_models<<<{"description": "Type(s) of physics models used on this block.   The choices are: Burnup Elastic Creep Relocation Swelling ThermalExpansion HighBurnupStructureFormation"}>>> = 'Burnup Elastic Creep Relocation Swelling ThermalExpansion HighBurnupStructureFormation'
      isotopes<<<{"description": "Fuel isotopes: Gd155 Gd157 U235 U238 Pu239 Pu240 Pu241 Pu242.  Number of entries must match number of entries in isotope_fractions."}>>> = 'U235 U238'
      isotope_fractions<<<{"description": "The isotope fractions associated with the 'isotopes' input line.  Must sum to 1.0."}>>> = '0.035 0.965'
      burnup_relocation_stop<<<{"description": "Burnup at which relocation strain stops (in FIMA)"}>>> = 0.024
      axial_power_profile<<<{"description": "The axial power peaking function."}>>> = axial_peaking_factors
      rod_ave_lin_pow<<<{"description": "The rod power history function."}>>> = power_history
      fragmentation_model<<<{"description": "The model used to calculate the number of cracks in the fuel."}>>> = 'BARANI'
    []
  []
  [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
      fuel_pin_geometry<<<{"description": "Name of the UserObject that reads the pin geometry from the mesh."}>>> = fuel_pin_geometry
      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 ZrPhase ZryOxidation ZryCladdingFailure'
      failure_criterion<<<{"description": "Options to determine when the cladding material is considered to have burst"}>>> = overstress
      additional_generate_output<<<{"description": "Add scalar quantity output for stress and/or strain (will be appended to the list in `generate_output`)"}>>> = 'strain_zz hoop_creep_strain'
      fast_neutron_flux_factor<<<{"description": "The fast neutron flux if the function, RALP, and q_variable are not given. A scaling factor if the function, RALP, or q_variable is given.  If RALP or q_variable is given, it is recommended to use a value of 3e13 (n/(m^2s)/(W/m))."}>>> = 3e13
    []
  []
[]
(assessment/LWR/validation/LOCA_IFA_650/analysis/IFA_650_4/IFA_650_4_part1_action.i)