HighBurnup LWRNuclearMaterials
This tutorial is currently under development.
schooltip:Try the Action Wizard
There is a recently developed Action Wizard that will create the NuclearMaterials block based on user input. Read through this tutorial, then use it to experiment with the action.
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'
fission_operation<<<{"description": "Type of fission occuring in this simulation."}>>> = HighBurnup
physics<<<{"description": "Type(s) of physics used on this block."}>>> = 'Mechanics Thermal'
initial_temperature<<<{"description": "Initial temperature in Kelvins."}>>> = 300
stress_free_temperature<<<{"description": "Reference temperature for thermal eigenstrain calculation"}>>> = 300
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_1
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."}>>> = '0.9293 0.0707'
burnup_relocation_stop<<<{"description": "Burnup at which relocation strain stops (in FIMA)"}>>> = 0.035
fuel_pin_geometry<<<{"description": "Name of the UserObject that reads the pin geometry from the mesh."}>>> = pin_geometry
rod_ave_lin_pow<<<{"description": "The rod power history function."}>>> = power_history
axial_power_profile<<<{"description": "The axial power peaking function."}>>> = axial_peaking_factors
additional_generate_output<<<{"description": "Add scalar quantity output for stress and/or strain (will be appended to the list in `generate_output`)"}>>> = hydrostatic_stress
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."}>>> = 1.0
# The mesh is not a right cyclinder due to
# chamfering and dishing, following the
# established HBEP_BK363.i results, this
# is kept as fuel_volume_ratio=1 to match
# test results
extra_vector_tags<<<{"description": "The tag names for extra vectors that residual data should be saved into"}>>> = 'ref'
[]
[]
[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'
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 hoop_creep_strain'
flux_function<<<{"description": "Function which contains the neutron flux data."}>>> = flux
extra_vector_tags<<<{"description": "The tag names for extra vectors that residual data should be saved into"}>>> = 'ref'
[]
[]
[]