- heat_fluxThe thermal Lagrange multiplier variable, which corresponds to the gap heat flux.
C++ Type:std::vector<VariableName>
Unit:(no unit assumed)
Controllable:No
Description:The thermal Lagrange multiplier variable, which corresponds to the gap heat flux.
- primary_boundaryThe name of the primary boundary sideset.
C++ Type:BoundaryName
Controllable:No
Description:The name of the primary boundary sideset.
- primary_subdomainThe name of the primary subdomain.
C++ Type:SubdomainName
Controllable:No
Description:The name of the primary subdomain.
- secondary_boundaryThe name of the secondary boundary sideset.
C++ Type:BoundaryName
Controllable:No
Description:The name of the secondary boundary sideset.
- secondary_subdomainThe name of the secondary subdomain.
C++ Type:SubdomainName
Controllable:No
Description:The name of the secondary subdomain.
- temperatureThe temperature variable
C++ Type:std::vector<VariableName>
Unit:(no unit assumed)
Controllable:No
Description:The temperature variable
- variableThe name of the variable that this object applies to
C++ Type:AuxVariableName
Unit:(no unit assumed)
Controllable:No
Description:The name of the variable that this object applies to
GapConductanceMortar
Returns the gap conductance for mortar-based thermal contact. It uses the heat flux and the temperature gradient to perform a weighted integration and return a nodal value
Description
The GapConductanceMortar AuxKernel is used to calculate the gap conductance from LWR problems solved with a mortar formulation. The value of gap conductance is computed from the heat flux (i.e. thermal contact Lagrange multiplier) and the temperature difference between the contacting primary and secondary surface. The overall gap conductance value captures contributions from radiation, contact, and gap conductivity ThermalContactLWRMortarAction.
Example Input Syntax
[AuxKernels<<<{"href": "../../syntax/AuxKernels/index.html"}>>>]
[gap_conductance]
type = GapConductanceMortar<<<{"description": "Returns the gap conductance for mortar-based thermal contact. It uses the heat flux and the temperature gradient to perform a weighted integration and return a nodal value", "href": "GapConductanceMortar.html"}>>>
primary_boundary<<<{"description": "The name of the primary boundary sideset."}>>> = 100
secondary_boundary<<<{"description": "The name of the secondary boundary sideset."}>>> = 101
primary_subdomain<<<{"description": "The name of the primary subdomain."}>>> = 'mechanical_primary_subdomain'
secondary_subdomain<<<{"description": "The name of the secondary subdomain."}>>> = 'mechanical_secondary_subdomain'
heat_flux<<<{"description": "The thermal Lagrange multiplier variable, which corresponds to the gap heat flux."}>>> = thermal_contact_thermal_lm
temperature<<<{"description": "The temperature variable"}>>> = temperature
variable<<<{"description": "The name of the variable that this object applies to"}>>> = gap_conductance
[]
[]Input Parameters
- check_boundary_restrictedTrueWhether to check for multiple element sides on the boundary in the case of a boundary restricted, element aux variable. Setting this to false will allow contribution to a single element's elemental value(s) from multiple boundary sides on the same element (example: when the restricted boundary exists on two or more sides of an element, such as at a corner of a mesh
Default:True
C++ Type:bool
Controllable:No
Description:Whether to check for multiple element sides on the boundary in the case of a boundary restricted, element aux variable. Setting this to false will allow contribution to a single element's elemental value(s) from multiple boundary sides on the same element (example: when the restricted boundary exists on two or more sides of an element, such as at a corner of a mesh
- correct_edge_droppingFalseWhether to enable correct edge dropping treatment for mortar constraints. When disabled any Lagrange Multiplier degree of freedom on a secondary element without full primary contributions will be set (strongly) to 0.
Default:False
C++ Type:bool
Controllable:No
Description:Whether to enable correct edge dropping treatment for mortar constraints. When disabled any Lagrange Multiplier degree of freedom on a secondary element without full primary contributions will be set (strongly) to 0.
- debug_meshFalseWhether this constraint is going to enable mortar segment mesh debug information. An exodusfile will be generated if the user sets this flag to true
Default:False
C++ Type:bool
Controllable:No
Description:Whether this constraint is going to enable mortar segment mesh debug information. An exodusfile will be generated if the user sets this flag to true
- execute_onTIMESTEP_ENDThe list of flag(s) indicating when this object should be executed. For a description of each flag, see https://mooseframework.inl.gov/source/interfaces/SetupInterface.html.
Default:TIMESTEP_END
C++ Type:ExecFlagEnum
Options:XFEM_MARK, NONE, INITIAL, LINEAR, NONLINEAR_CONVERGENCE, NONLINEAR, POSTCHECK, TIMESTEP_END, TIMESTEP_BEGIN, MULTIAPP_FIXED_POINT_END, MULTIAPP_FIXED_POINT_BEGIN, FINAL, CUSTOM, PRE_DISPLACE
Controllable:No
Description:The list of flag(s) indicating when this object should be executed. For a description of each flag, see https://mooseframework.inl.gov/source/interfaces/SetupInterface.html.
- ghost_higher_d_neighborsFalseWhether we should ghost higher-dimensional neighbors. This is necessary when we are doing second order mortar with finite volume primal variables, because in order for the method to be second order we must use cell gradients, which couples in the neighbor cells.
Default:False
C++ Type:bool
Controllable:No
Description:Whether we should ghost higher-dimensional neighbors. This is necessary when we are doing second order mortar with finite volume primal variables, because in order for the method to be second order we must use cell gradients, which couples in the neighbor cells.
- ghost_point_neighborsTrueWhether we should ghost point neighbors of secondary face elements, and consequently also their mortar interface couples.
Default:True
C++ Type:bool
Controllable:No
Description:Whether we should ghost point neighbors of secondary face elements, and consequently also their mortar interface couples.
- incrementalFalseWhether to accumulate mortar auxiliary kernel value
Default:False
C++ Type:bool
Controllable:No
Description:Whether to accumulate mortar auxiliary kernel value
- interpolate_normalsTrueWhether to interpolate the nodal normals (e.g. classic idea of evaluating field at quadrature points). If this is set to false, then non-interpolated nodal normals will be used, and then the _normals member should be indexed with _i instead of _qp
Default:True
C++ Type:bool
Controllable:No
Description:Whether to interpolate the nodal normals (e.g. classic idea of evaluating field at quadrature points). If this is set to false, then non-interpolated nodal normals will be used, and then the _normals member should be indexed with _i instead of _qp
- minimum_projection_angle40Parameter to control which angle (in degrees) is admissible for the creation of mortar segments. If set to a value close to zero, very oblique projections are allowed, which can result in mortar segments solving physics not meaningfully, and overprojection of primary nodes onto the mortar segment mesh in extreme cases. This parameter is mostly intended for mortar mesh debugging purposes in two dimensions.
Default:40
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Parameter to control which angle (in degrees) is admissible for the creation of mortar segments. If set to a value close to zero, very oblique projections are allowed, which can result in mortar segments solving physics not meaningfully, and overprojection of primary nodes onto the mortar segment mesh in extreme cases. This parameter is mostly intended for mortar mesh debugging purposes in two dimensions.
- periodicFalseWhether this constraint is going to be used to enforce a periodic condition. This has the effect of changing the normals vector for projection from outward to inward facing
Default:False
C++ Type:bool
Controllable:No
Description:Whether this constraint is going to be used to enforce a periodic condition. This has the effect of changing the normals vector for projection from outward to inward facing
Optional Parameters
- control_tagsAdds user-defined labels for accessing object parameters via control logic.
C++ Type:std::vector<std::string>
Controllable:No
Description:Adds user-defined labels for accessing object parameters via control logic.
- enableTrueSet the enabled status of the MooseObject.
Default:True
C++ Type:bool
Controllable:Yes
Description:Set the enabled status of the MooseObject.
- seed0The seed for the master random number generator
Default:0
C++ Type:unsigned int
Controllable:No
Description:The seed for the master random number generator
- use_displaced_meshTrueWhether to use the displaced mesh to compute the auxiliary kernel value.
Default:True
C++ Type:bool
Controllable:No
Description:Whether to use the displaced mesh to compute the auxiliary kernel value.
Advanced Parameters
- prop_getter_suffixAn optional suffix parameter that can be appended to any attempt to retrieve/get material properties. The suffix will be prepended with a '_' character.
C++ Type:MaterialPropertyName
Unit:(no unit assumed)
Controllable:No
Description:An optional suffix parameter that can be appended to any attempt to retrieve/get material properties. The suffix will be prepended with a '_' character.
- use_interpolated_stateFalseFor the old and older state use projected material properties interpolated at the quadrature points. To set up projection use the ProjectedStatefulMaterialStorageAction.
Default:False
C++ Type:bool
Controllable:No
Description:For the old and older state use projected material properties interpolated at the quadrature points. To set up projection use the ProjectedStatefulMaterialStorageAction.
Material Property Retrieval Parameters
Input Files
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM073/BFM073.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFL031/BFL031.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BEN013/BEN013.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM071/BFM071.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFJ027/BFJ027.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/UFE067/UFE067.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFL009/BFL009.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM043/BFM043.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFG092/BFG092.i)
- (test/tests/gap_heat_transfer_mortar_action/gap_heat_transfer_mortar_transient_action_gap_conductance_second_order.i)
- (assessment/LWR/validation/Super_Ramp/analysis/Super_Ramp_Base.i)
- (assessment/LWR/validation/Riso_Base.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM034/BFM034.i)
- (test/tests/gap_heat_transfer_mortar_action/gap_heat_transfer_mortar_transient_action_gap_conductance.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM070/BFM070.i)
- (assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM156/BFM156.i)
References
No citations exist within this document.(test/tests/gap_heat_transfer_mortar_action/gap_heat_transfer_mortar_transient_action_gap_conductance.i)
[GlobalParams]
displacements = 'disp_x disp_y'
[]
[Mesh]
patch_update_strategy = auto
patch_size = 2
[file]
type = FileMeshGenerator
file = 2blk-gap_no1000.e
[]
[]
[Variables]
[temperature]
order = FIRST
family = LAGRANGE
block = '1 2'
initial_condition = 1
[]
[disp_x]
block = '1 2'
[]
[disp_y]
block = '1 2'
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 100
secondary_boundary = 101
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temperature
variable = gap_conductance
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[all]
strain = FINITE
block = '1 2'
use_automatic_differentiation = true
[]
[]
[Materials]
[left]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 750
specific_heat = 1
[]
[right]
type = HeatConductionMaterial
block = 2
thermal_conductivity = 750
specific_heat = 1
[]
[elasticity_tensor]
type = ADComputeIsotropicElasticityTensor
youngs_modulus = 1e5
poissons_ratio = 0.345
block = '1 2'
[]
[_elastic_strain]
type = ADComputeFiniteStrainElasticStress
block = '1 2'
[]
[]
[Kernels]
[hc_fixed]
type = HeatConduction
variable = temperature
use_displaced_mesh = false
block = '1'
[]
[hc_moving]
type = HeatConduction
variable = temperature
use_displaced_mesh = true
block = '2'
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temperature
primary_boundary = 100
secondary_boundary = 101
emissivity_primary = 0.5
emissivity_secondary = 0.8
gascond_scalef = 1.0
contact_pressure = mechanical_normal_lm
min_gap = 1e-3
meyer_hardness_model = MATPRO
use_displaced_mesh = true
correct_edge_dropping = true
[]
[]
[Contact]
[mechanical]
model = frictionless
formulation = mortar
primary = 100
secondary = 101
c_normal = 1e+05
correct_edge_dropping = true
[]
[]
[Functions]
[disp_bc]
type = PiecewiseLinear
x = '0 10.0 1000.0'
y = '0 -0.30 -0.301'
[]
[]
[BCs]
[left]
type = DirichletBC
variable = temperature
boundary = 'left'
value = 400
[]
[right]
type = DirichletBC
variable = temperature
boundary = 'right'
value = 2
[]
[left_x]
type = DirichletBC
variable = disp_x
boundary = 'left'
value = 0.0
[]
[left_y]
type = DirichletBC
variable = disp_y
boundary = 'left'
value = 0.0
[]
[right_x]
type = FunctionDirichletBC
variable = disp_x
boundary = 'right'
function = disp_bc
[]
[right_y]
type = FunctionDirichletBC
variable = disp_y
boundary = 'right'
function = 0
[]
[]
[VectorPostprocessors]
[temperature_post]
type = NodalValueSampler
variable = temperature
boundary = '100'
sort_by = x
[]
[]
[Preconditioning]
[fmp]
type = SMP
full = true
[]
[]
[Executioner]
solve_type = PJFNK
type = Transient
dt = 1.0
dtmin = 1.0
end_time = 10.0
nl_rel_tol = 1e-8
nl_abs_tol = 1e-10
l_tol = 1e-5
petsc_options_iname = '-pc_type -snes_linesearch_type -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu basic NONZERO 1e-15'
snesmf_reuse_base = false
[]
[Outputs]
perf_graph = true
csv = true
exodus = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM073/BFM073.i)
################################################################################
#
# Description: Calvert Cliffs BFM073
#
#
#
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFM073_power.csv
# axial peaking factor file BFM073_axial_peaking.csv
# flux boundary condition file BFM073_fast_flux.csv
################################################################################
initial_fuel_density = 10386.93
[GlobalParams]
density = ${initial_fuel_density} #94.662 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.31914
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFM073_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFM073_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 179191453 179191813'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 179191453 179191813'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFM073_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10386.93
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = MaxIncrement
variable = temp
max_increment = 50
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 179191813
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
exodus = true
csv = true
color = false
print_linear_residuals = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFL031/BFL031.i)
################################################################################
#
# Description: Calvert Cliffs BFL031
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFL031_power.csv
# axial peaking factor file BFL031_axial_peaking.csv
# flux boundary condition file BFL031_fast_flux.csv
#
################################################################################
initial_fuel_density = 10460.45
[GlobalParams]
density = ${initial_fuel_density} #95.332 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
patch_size = 20
patch_update_strategy = auto
partitioner = centroid # this will help with run time
centroid_partitioner_direction = y # this will help with run time
[mesh]
type = FileMeshGenerator
file = BFL031_mesh.e
[]
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFL031_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFL031_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 174660997 174661357'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 174660997 174661357'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFL031_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = clad
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
variable = oxide_thickness
boundary = 2
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0013589
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = 20
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = '9 13' # clad interior + fuel exterior
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10411.07
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[oxidationcladding]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = MaxIncrement
variable = temp
max_increment = 50
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 174661357
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_2984]
type = NodalVariableValue
nodeid = 2983
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
exodus = true
csv = true
color = false
print_linear_residuals = true
perf_graph = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BEN013/BEN013.i)
################################################################################
#
# Description: Calvert Cliffs BEN013
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BEN013_power.csv
# axial peaking factor file BEN013_axial_peaking.csv
# flux boundary condition file BEN013_fast_flux.csv
#
################################################################################
initial_fuel_density = 10411.07 #94.882 %TD Assume TD = 10972.65 kg/cm3
[GlobalParams]
density = ${initial_fuel_density}
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.28581
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 4.2e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BEN013_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BEN013_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 177922434 177922794'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 177922434 177922794'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BEN013_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = clad
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10411.07
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = MaxIncrement
variable = temp
max_increment = 50
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 177922794
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
exodus = true
csv = true
color = false
print_linear_residuals = true
perf_graph = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
# execute_on = 'FINAL'
sync_times = '3600 7200 10800 14400 177922434 177922794'
sync_only = true
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM071/BFM071.i)
################################################################################
#
# Description: Calvert Cliffs BFM071
#
#
#
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFM071_power.csv
# axial peaking factor file BFM071_axial_peaking.csv
# flux boundary condition file BFM071_fast_flux.csv
################################################################################
initial_fuel_density = 10386.93
[GlobalParams]
density = ${initial_fuel_density} #94.662 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.31727
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFM071_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFM071_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 178956096 178956456'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 178956096 178956456'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFM071_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10386.93
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 178956456
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
exodus = true
csv = true
color = false
print_linear_residuals = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFJ027/BFJ027.i)
################################################################################
#
# Description: Calvert Cliffs BFJ027
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFJ027_power.csv
# axial peaking factor file BFJ027_axial_peaking.csv
# flux boundary condition file BFJ027_fast_flux.csv
#
################################################################################
initial_fuel_density = 10411.07
[GlobalParams]
density = ${initial_fuel_density} #94.882 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.28943
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 4.2e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFJ027_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFJ027_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 177688931 177689291'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 177688931 177689291'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFJ027_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0366 .9634 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10411.07
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = MaxIncrement
variable = temp
max_increment = 50
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 177689291
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
exodus = true
csv = true
color = false
print_linear_residuals = true
perf_graph = true
[outfile_1]
type = CSV
execute_on = 'FINAL'
[]
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/UFE067/UFE067.i)
################################################################################
#
# Description: Calvert Cliffs UFE067
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file UFE067_power.csv
# axial peaking factor file UFE067_axial_peaking.csv
# flux boundary condition file UFE067_fast_flux.csv
#
################################################################################
initial_fuel_density = 10396.59
[GlobalParams]
density = ${initial_fuel_density} #94.75 %TD Assume TD = 10972.65 kg/m3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
volumetric_locking_correction = false
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.30013
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 4.2e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = UFE067_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = UFE067_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 141158832 141159192'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 141158832 141159192'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = UFE067_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx '
'strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy '
'creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = clad
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
variable = oxide_thickness
boundary = 2
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0398 .9602 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
layer_thickness = layer_thickness_action
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10411.07
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = BoundingValueNodalDamper
variable = temp
max_value = 3200
min_value = 273
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 60
l_tol = 8e-3
nl_max_its = 80
nl_rel_tol = 1e-4
nl_abs_tol = 1e-7
start_time = -100
end_time = 141159192
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
exodus = true
csv = true
color = false
print_linear_residuals = true
perf_graph = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage '
'maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFL009/BFL009.i)
################################################################################
#
# Description: Calvert Cliffs BFL009
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFL009_power.csv
# axial peaking factor file BFL009_axial_peaking.csv
# flux boundary condition file BFL009_fast_flux.csv
#
################################################################################
initial_fuel_density = 10460.45
[GlobalParams]
density = ${initial_fuel_density} #95.332 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[mesh]
type = FileMeshGenerator
file = BFL009_mesh.e
[]
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFL009_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFL009_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 167148794 167149154'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 167148794 167149154'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFL009_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0013589
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = 20
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = '9 13'
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10460.45
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = BoundingValueNodalDamper
variable = temp
max_value = 3200
min_value = 273
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 167149154
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_2984]
type = NodalVariableValue
nodeid = 2983
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
exodus = true
csv = true
color = false
print_linear_residuals = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM043/BFM043.i)
################################################################################
#
# Description: Calvert Cliffs BFM043
#
#
#
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFM043_power.csv
# axial peaking factor file BFM043_axial_peaking.csv
# flux boundary condition file BFM043_fast_flux.csv
################################################################################
initial_fuel_density = 10386.93
[GlobalParams]
density = ${initial_fuel_density} #94.662 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
volumetric_locking_correction = false
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.31834
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFM043_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFM043_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 179369250 179369610'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 179369250 179369610'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFM043_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10386.93
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Dampers]
[limitT]
type = MaxIncrement
variable = temp
max_increment = 50
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 179369610
dtmax = 2.5e5
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
exodus = true
csv = true
color = false
print_linear_residuals = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFG092/BFG092.i)
################################################################################
#
# Description: Calvert Cliffs BFG092
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFG092_power.csv
# axial peaking factor file BFG092_axial_peaking.csv
# flux boundary condition file BFG092_fast_flux.csv
#
################################################################################
initial_fuel_density = 10411.07
[GlobalParams]
density = ${initial_fuel_density} #94.882 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.28354
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 4.2e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFG092_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFG092_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 177711767 177712127'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 177711767 177712127'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFG092_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10411.07
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = BoundingValueNodalDamper
variable = temp
max_value = 3200
min_value = 273
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 177712127
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
exodus = true
csv = true
color = false
print_linear_residuals = true
perf_graph = true
[outfile_1]
type = CSV
execute_on = 'FINAL'
[]
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(test/tests/gap_heat_transfer_mortar_action/gap_heat_transfer_mortar_transient_action_gap_conductance_second_order.i)
[GlobalParams]
displacements = 'disp_x disp_y'
[]
[Mesh]
patch_update_strategy = auto
patch_size = 2
[file]
type = FileMeshGenerator
file = 2blk-gap_no1000.e
[]
second_order = true
[]
[Variables]
[temperature]
order = SECOND
family = LAGRANGE
block = '1 2'
initial_condition = 1
[]
[disp_x]
order = SECOND
family = LAGRANGE
block = '1 2'
[]
[disp_y]
order = SECOND
family = LAGRANGE
block = '1 2'
[]
[]
[AuxVariables]
[gap_conductance]
order = SECOND
family = LAGRANGE
block = 'mechanical_secondary_subdomain'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 100
secondary_boundary = 101
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temperature
variable = gap_conductance
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[all]
strain = FINITE
block = '1 2'
use_automatic_differentiation = true
[]
[]
[Materials]
[left]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 750
specific_heat = 1
[]
[right]
type = HeatConductionMaterial
block = 2
thermal_conductivity = 750
specific_heat = 1
[]
[elasticity_tensor]
type = ADComputeIsotropicElasticityTensor
youngs_modulus = 1e5
poissons_ratio = 0.345
block = '1 2'
[]
[_elastic_strain]
type = ADComputeFiniteStrainElasticStress
block = '1 2'
[]
[]
[Kernels]
[hc_fixed]
type = HeatConduction
variable = temperature
use_displaced_mesh = false
block = '1'
[]
[hc_moving]
type = HeatConduction
variable = temperature
use_displaced_mesh = true
block = '2'
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temperature
primary_boundary = 100
secondary_boundary = 101
emissivity_primary = 0.5
emissivity_secondary = 0.8
gascond_scalef = 1.0
contact_pressure = mechanical_normal_lm
min_gap = 1e-3
meyer_hardness_model = MATPRO
use_displaced_mesh = true
correct_edge_dropping = true
[]
[]
[Contact]
[mechanical]
model = frictionless
formulation = mortar
primary = 100
secondary = 101
c_normal = 1e+08
correct_edge_dropping = true
[]
[]
[Functions]
[disp_bc]
type = PiecewiseLinear
x = '0 10.0 1000.0'
y = '0 -0.30 -0.301'
[]
[]
[BCs]
[left]
type = DirichletBC
variable = temperature
boundary = 'left'
value = 400
[]
[right]
type = DirichletBC
variable = temperature
boundary = 'right'
value = 2
[]
[left_x]
type = DirichletBC
variable = disp_x
boundary = 'left'
value = 0.0
[]
[left_y]
type = DirichletBC
variable = disp_y
boundary = 'left'
value = 0.0
[]
[right_x]
type = FunctionDirichletBC
variable = disp_x
boundary = 'right'
function = disp_bc
[]
[right_y]
type = FunctionDirichletBC
variable = disp_y
boundary = 'right'
function = 0
[]
[]
[VectorPostprocessors]
[temperature_post]
type = NodalValueSampler
variable = temperature
boundary = '100'
sort_by = x
[]
[]
[Preconditioning]
[fmp]
type = SMP
full = true
[]
[]
[Executioner]
solve_type = PJFNK
type = Transient
dt = 0.25
dtmin = 0.25
end_time = 5.0
nl_rel_tol = 1e-8
nl_abs_tol = 1e-10
l_tol = 1e-5
petsc_options_iname = '-pc_type -snes_linesearch_type -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu basic NONZERO 1e-13'
snesmf_reuse_base = true
[]
[Outputs]
perf_graph = true
csv = true
exodus = true
[]
(assessment/LWR/validation/Super_Ramp/analysis/Super_Ramp_Base.i)
#This is a partial input file base with information/features common to several experiments within this assessment
#NOTE: This file will NOT run on its own, it requires a PK#X.params file and a PK##.params file to run
# physical constants
R = 8.3143 # (J/K*mol) -- THIS SHOULD BE EDITED TO USE PHYSICALCONSTANTS' VALUE
# fuel isotope fractions and fission energy
energy_per_fission = 3.28451e-11 # (J/fission)
isotope_fraction_Pu239 = 0.0
isotope_fraction_Pu240 = 0.0
isotope_fraction_Pu241 = 0.0
isotope_fraction_Pu242 = 0.0
# rod geometry
clad_bot_gap_height = 1.0e-3 # (m)
# variable and kernel initial values
initial_temperature = 293.15 # (K)
gravity_constant = -9.81 # (m/s^2)
# fuel/cladding contact
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
roughness_secondary = 1.0e-6 # (m)
roughness_primary = 2.0e-6 # (m)
roughness_coef = 3.2
jump_distance_model = LANNING
contact_pressure = mechanical_normal_lm
thermal_lm_scaling = 1.0e-2
# plenum parameters
initial_pressure = 2.25e6 # (Pa)
startup_time = 0 # (s)
# fuel/clad material properties
fuel_cracking_stress = 1.68e8
stress_free_temperature = 293.15 # (K)
clad_density = 6550.0 # (kg/m^3)
# numerical options
l_max_its = 100
l_tol = 1e-4
nl_max_its = 30
start_time = 0.0 # s
dtmin = 1.0 # s
[GlobalParams]
density = ${fuel_density}
displacements = 'disp_x disp_y'
order = SECOND
family = LAGRANGE
energy_per_fission = ${energy_per_fission}
volumetric_locking_correction = false
initial_porosity = ${initial_fuel_porosity}
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temperature'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
pellet_quantity = ${number_pellets}
pellet_height = ${pellet_height}
pellet_outer_radius = ${pellet_outer_radius}
pellet_mesh_density = customize
nx_p = 11
ny_p = 84
clad_mesh_density = customize
nx_c = 4
ny_c = 84
clad_gap_width = ${clad_gap_width}
clad_thickness = ${clad_thickness}
clad_bot_gap_height = ${clad_bot_gap_height}
bottom_clad_height = ${bottom_clad_height}
top_clad_height = ${top_clad_height}
clad_top_gap_height = ${clad_top_gap_height}
ny_cu = 3
ny_cl = 3
elem_type = QUAD8
[]
patch_size = 10
patch_update_strategy = iteration
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[temperature]
initial_condition = ${initial_temperature}
[]
[]
[Functions]
[power_history]
type = PiecewiseLinear
data_file = ${power_history_data_file}
format = columns
[]
[axial_power_factors]
type = PiecewiseBilinear
data_file = ${axial_power_factors_data_file}
axis = 1
[]
[clad_out_temp]
type = PiecewiseLinear
data_file = ${clad_out_temp_data_file}
format = columns
[]
[axial_temp_factors]
type = PiecewiseBilinear
data_file = ${axial_temp_factors_data_file}
axis = 1
[]
[clad_temp_bc]
type = CompositeFunction
functions = 'clad_out_temp axial_temp_factors'
[]
[coolant_pressure]
type = PiecewiseLinear
data_file = ${coolant_pressure_data_file}
format = columns
[]
[fast_flux]
type = PiecewiseLinear
data_file = ${fast_neutron_flux_data_file}
format = columns
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = clad
[]
[fast_neutron_fluence]
block = clad
[]
[grain_radius]
block = pellet
initial_condition = ${initial_grain_radius}
[]
[porosity]
order = CONSTANT
family = MONOMIAL
block = pellet
initial_condition = ${initial_fuel_porosity}
[]
[pellet_id]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[creep_strain_mag]
order = CONSTANT
family = MONOMIAL
block = clad
[]
[gas_gen_3]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[gas_grn_3]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[gas_bdr_3]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[gas_rel_3]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[bbl_bdr_2]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[prs_bbl_bdr]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[prseq_bbl_bdr]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[rad_bbl_bdr]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[GBCoverage]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[sat_coverage]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[eff_diff_coeff]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[deltav_v0_bd]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[gaseous_porosity]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[thermal_conductivity]
order = CONSTANT
family = MONOMIAL
block = pellet
[]
[layered_average_contact_pressure]
order = CONSTANT
family = MONOMIAL
[]
[volumetric_swelling_strain]
order = CONSTANT
family = MONOMIAL
[]
[gap_cond]
order = CONSTANT
family = MONOMIAL
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = pellet
temperature = temperature
add_variables = true
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain
fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy
stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = clad
temperature = temperature
add_variables = true
strain = FINITE
cylindrical_axis_point1 = '0 0 0'
cylindrical_axis_point2 = '0 1 0'
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz
creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx
strain_yy strain_zz hoop_stress'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temperature
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temperature
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temperature
block = pellet
burnup_function = burnup
extra_vector_tags = 'ref'
[]
[gravity]
type = Gravity
variable = disp_y
value = ${gravity_constant}
block = '1 3'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temperature
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = clad
function = fast_flux
execute_on = timestep_begin
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = pellet
variable = grain_radius
temperature = temperature
execute_on = linear
[]
[porosity]
type = PorosityAuxUO2
block = pellet
variable = porosity
execute_on = linear
[]
[pelletid]
type = PelletIdAux
block = pellet
variable = pellet_id
fuel_pin_geometry = pin_geometry
number_pellets = ${number_pellets}
execute_on = initial
[]
[oxi_thickness]
type = MaterialRealAux
variable = oxide_thickness
property = oxide_scale_thickness
boundary = 2
[]
[creep_strain_mag]
type = MaterialRealAux
property = effective_creep_strain
variable = creep_strain_mag
execute_on = timestep_end
[]
[fggen]
type = MaterialRealAux
variable = gas_gen_3
property = gas_concentration_generated_total
[]
[fggrn]
type = MaterialRealAux
variable = gas_grn_3
property = gas_concentration_intra_total
[]
[fgbdr]
type = MaterialRealAux
variable = gas_bdr_3
property = gas_concentration_GB_bubble_volume
[]
[fgrel]
type = MaterialRealAux
variable = gas_rel_3
property = gas_concentration_release_total
[]
[nbbl2]
type = MaterialRealAux
variable = bbl_bdr_2
property = bubble_GB_surface_density
[]
[prsbbl]
type = MaterialRealAux
variable = prs_bbl_bdr
property = bubble_GB_pressure
[]
[prseqbbl]
type = MaterialRealAux
variable = prseq_bbl_bdr
property = bubble_GB_pressure_equilibrium
[]
[radbbl]
type = MaterialRealAux
variable = rad_bbl_bdr
property = bubble_radius_GB
[]
[frcvrg]
type = MaterialRealAux
variable = GBCoverage
property = GBCoverage
[]
[stcvrg]
type = MaterialRealAux
variable = sat_coverage
property = sat_coverage
[]
[diffc]
type = MaterialRealAux
variable = eff_diff_coeff
property = eff_diff_coeff
[]
[dvv0bd]
type = MaterialRealAux
variable = deltav_v0_bd
property = deltav_v0_bubble_GB
[]
[gaspor]
type = MaterialRealAux
variable = gaseous_porosity
property = gaseous_porosity
[]
[fuel_conductivity]
type = MaterialRealAux
variable = thermal_conductivity
property = thermal_conductivity
[]
[layered_average_contact_pressure]
type = SpatialUserObjectAux
block = pellet
variable = layered_average_contact_pressure
execute_on = nonlinear
user_object = layered_average_contact_pressure
[]
[volumetric_swelling_strain]
type = MaterialRealAux
variable = volumetric_swelling_strain
property = volumetric_swelling_strain
block = pellet
execute_on = nonlinear
[]
[]
[Burnup]
[burnup]
block = pellet
rod_ave_lin_pow = power_history
axial_power_profile = axial_power_factors
num_radial = 80
num_axial = 20
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '${isotope_fraction_U235} ${isotope_fraction_U238} ${isotope_fraction_Pu239} ${isotope_fraction_Pu240} ${isotope_fraction_Pu241} ${isotope_fraction_Pu242}'
RPF = RPF
fuel_pin_geometry = pin_geometry
fuel_volume_ratio = 1.0
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = ${friction_coefficient}
c_normal = ${c_normal}
c_tangential = ${c_tangential}
tangential_lm_scaling = ${tangential_lm_scaling}
normal_lm_scaling = ${normal_lm_scaling}
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temperature
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
roughness_secondary = ${roughness_secondary}
roughness_primary = ${roughness_primary}
roughness_coef = ${roughness_coef}
plenum_pressure = plenum_pressure
jump_distance_model = ${jump_distance_model}
contact_pressure = ${contact_pressure}
thermal_lm_scaling = ${thermal_lm_scaling}
[]
[]
[PlenumTemperature]
[plenum_temp]
boundary = 5
inner_surfaces = 5
outer_surfaces = 10
temperature = temperature
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = 1
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = 1020
value = 0.0
[]
[temp]
type = FunctionDirichletBC
boundary = '1 2 3'
variable = temperature
function = clad_temp_bc
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
function = coolant_pressure
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = ${initial_pressure}
startup_time = ${startup_time}
R = ${R}
output_initial_moles = initial_moles
temperature = plenum_temp
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
[]
[]
[]
[Materials]
[fuel_thermal]
type = UO2Thermal
block = pellet
thermal_conductivity_model = NFIR
temperature = temperature
burnup_function = burnup
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
gas_swelling_model_type = SIFGRS
block = pellet
temperature = temperature
burnup_function = burnup
initial_fuel_density = ${fuel_density}
eigenstrain_name = fuel_volumetric_strain
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = pellet
density = ${fuel_density}
temperature = temperature
matpro_youngs_modulus = true
matpro_poissons_ratio = true
[]
[fuel_creep]
type = UO2CreepUpdate
block = pellet
temperature = temperature
burnup_function = burnup
initial_grain_radius = ${initial_grain_radius}
[]
[fuel_stress]
type = ComputeSmearedCrackingStress
block = pellet
cracking_stress = ${fuel_cracking_stress}
inelastic_models = 'fuel_creep'
softening_models = exponential_softening
shear_retention_factor = 0.1
max_stress_correction = 0
cracked_elasticity_type = DIAGONAL
output_properties = crack_damage
outputs = exodus
[]
[exponential_softening]
type = ExponentialSoftening
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = pellet
burnup_function = burnup
rod_ave_lin_pow = power_history
axial_power_profile = axial_power_factors
relocation_activation1 = 5000
relocation_model = ESCORE_modified
eigenstrain_name = fuel_relocation_strain
fuel_pin_geometry = pin_geometry
model_relocation_recovery = true
max_relocation_recovery_fraction = 0.5
relocation_scaling_factor = 1
volumetric_swelling_increment = vol_swell_increment
layered_average_contact_pressure = layered_average_contact_pressure
outputs = all
output_properties = 'relocation_strain recovered_relocation_strain'
[]
[fuel_thermal_expansion]
type = UO2ThermalExpansionMATPROEigenstrain
block = pellet
temperature = temperature
stress_free_temperature = ${stress_free_temperature}
eigenstrain_name = fuel_thermal_strain
[]
[fission_gas_release]
type = UO2Sifgrs
block = pellet
hydrostatic_stress = hydrostatic_stress
diff_coeff_option = TURNBULL_D1_4D2_D3
transient_option = MICROCRACKING_BURNUP
res_param_option = HETEROGENEOUS_WHITE
ig_bubble_model = NUCLEATION_RESOLUTION
ig_diff_algorithm = polypole2
temperature = temperature
burnup_function = burnup
grain_radius = grain_radius
gbs_model = true
pellet_id = pellet_id
pellet_brittle_zone = pbz
ath_model = true
rod_ave_lin_pow = power_history
axial_power_profile = axial_power_factors
[]
[fuel_density]
type = StrainAdjustedDensity
block = pellet
strain_free_density = ${fuel_density}
[]
[clad_thermal]
type = ZryThermal
block = clad
temperature = temperature
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
fast_neutron_fluence = fast_neutron_fluence
temperature = temperature
matpro_youngs_modulus = true
matpro_poissons_ratio = true
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = nonlinear
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temperature
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
zircaloy_material_type = stress_relief_annealed
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temperature
stress_free_temperature = ${stress_free_temperature}
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = clad
strain_free_density = ${clad_density}
[]
[clad_oxidation]
type = ZryOxidation
boundary = 2
temperature = temperature
normal_operating_temperature_model = epri_kwu_ce
high_temperature_model = leistikow
fuel_pin_geometry = pin_geometry
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type -pc_factor_shift_amount'
petsc_options_value = ${petsc_options_value}
line_search = 'none'
verbose = true
l_max_its = ${l_max_its}
l_tol = ${l_tol}
nl_max_its = ${nl_max_its}
nl_rel_tol = ${nl_rel_tol}
nl_abs_tol = ${nl_abs_tol}
start_time = ${start_time}
n_startup_steps = 1
end_time = ${end_time}
dtmax = ${dtmax}
dtmin = ${dtmin}
[TimeStepper]
type = IterationAdaptiveDT
dt = 100
optimal_iterations = ${optimal_iterations}
iteration_window = ${iteration_window}
timestep_limiting_function = power_history
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[central_fuel_temp]
type = NodalVariableValue
variable = temperature
nodeid = 3110 #Mesh dependent!
execute_on = 'initial timestep_end'
[]
[max_fuel_temp]
type = NodalExtremeValue
block = pellet
value_type = max
variable = temperature
execute_on = 'initial timestep_end'
[]
[max_clad_temp]
type = NodalExtremeValue
block = clad
value_type = max
variable = temperature
execute_on = 'initial timestep_end'
[]
[midplane_hoop_strain_inner_clad]
type = ElementalVariableValue
elementid = 209 # Mesh dependent
variable = strain_zz
execute_on = 'initial timestep_end'
[]
[midplane_hoop_stress_inner_clad]
type = ElementalVariableValue
elementid = 209 # Mesh dependent
variable = hoop_stress
execute_on = 'initial timestep_end'
[]
[midplane_contact_pressure]
type = NodalVariableValue
variable = contact_pressure
nodeid = 3141 # Mesh dependent
execute_on = 'initial timestep_end'
[]
[total_rod_integral_power]
type = ElementIntegralPower
variable = temperature
burnup_function = burnup
block = pellet
[]
[total_rod_input_power]
type = FunctionValuePostprocessor
function = power_history
scale_factor = ${scale_factor}
[]
[vol_swell_increment]
type = SideAverageIncrementTensorComponent
boundary = 10
variable = volumetric_swelling_strain
execute_on = nonlinear
[]
[midplane_clad_outer_temp]
type = NodalVariableValue
nodeid = 757 # Mesh dependent
variable = temperature
[]
[midplane_clad_inner_temp]
type = NodalVariableValue
nodeid = 747 # Mesh dependent
variable = temperature
[]
[]
[StandardLWRFuelRodOutputs]
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
color = false
[csv]
type = CSV
file_base = '${id}_csv'
[]
[exodus]
type = Exodus
file_base = '${id}_exodus'
[]
[console]
type = Console
max_rows = 25
[]
[chkfile]
type = CSV
file_base = '${id}_chkfile'
show = 'average_burnup fission_gas_released_percentage central_fuel_temp midplane_contact_pressure'
execute_on = 'FINAL'
[]
[]
[UserObjects]
[pin_geometry]
type = FuelPinGeometry
[]
[pbz]
type = PelletBrittleZone
block = pellet
pellet_id = pellet_id
temperature = temperature
fuel_pin_geometry = pin_geometry
number_pellets = ${number_pellets}
execute_on = 'initial linear'
[]
[layered_average_contact_pressure]
type = LayeredSideAverage
variable = contact_pressure
direction = y
num_layers = 1
execute_on = timestep_end
boundary = 10
[]
[]
(assessment/LWR/validation/Riso_Base.i)
# This is a partial input file base with information/features common to several assessments cases for Riso
# NOTE: This file will NOT run on its own, it requires a Riso_XX.i file to run, with XX specifying the case to be run.
# Physical constants
gravitational_acceleration_constant = -9.81 # m/s^2
ideal_gas_constant = 8.31446261815324 # J/mol-K - Consistent with PhysicalConstants.h
[GlobalParams]
density = ${initial_fuel_density}
displacements = 'disp_x disp_y'
order = SECOND
family = LAGRANGE
energy_per_fission = ${energy_per_fission}
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temperature'
[]
[Mesh]
coord_type = RZ
patch_size = ${patch_size}
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[mesh]
type = FileMeshGenerator
file = ${rod_mesh_file}
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temperature
variable = gap_conductance
[]
[]
[Functions]
[power_history]
type = PiecewiseLinear
data_file = ${power_history_data_file}
format = columns
scale_factor = ${power_history_scale_factor}
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = ${axial_peaking_data_file}
scale_factor = 1
axis = 1
[]
[flux]
type = PiecewiseLinear
data_file = ${flux_data_file}
format = columns
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = ${friction_coefficient}
c_normal = ${c_normal}
c_tangential = ${c_tangential}
tangential_lm_scaling = ${tangential_lm_scaling}
normal_lm_scaling = ${normal_lm_scaling}
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temperature
primary_boundary = '5'
secondary_boundary = '10'
layer_thickness = layer_thickness_action
initial_moles = initial_moles # coupling to a postprocessor which supplies the initial plenum/gap gas mass
gas_released = fission_gas_released # coupling to a postprocessor which supplies the fission gas addition
roughness_secondary = ${roughness_secondary}
roughness_primary = ${roughness_primary}
roughness_coef = ${roughness_coef}
plenum_pressure = plenum_pressure
jump_distance_model = LANNING
initial_gas_types = He
initial_fractions = 1
contact_pressure = mechanical_normal_lm
thermal_lm_scaling = ${thermal_lm_scaling}
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = 1
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = 20
value = 0.0
[]
[temperature]
type = FunctionDirichletBC
boundary = '1 2 3'
variable = temperature
function = clad_temperature_bc
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = ${initial_plenum_pressure}
startup_time = ${startup_time}
R = ${ideal_gas_constant}
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[Kernels]
[gravity]
type = Gravity
variable = disp_y
value = ${gravitational_acceleration_constant}
extra_vector_tags = 'ref'
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
solve_type = 'NEWTON'
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
l_max_its = ${l_max_its}
l_tol = ${l_tol}
nl_max_its = ${nl_max_its}
nl_rel_tol = ${nl_rel_tol}
nl_abs_tol = ${nl_abs_tol}
start_time = ${start_time}
end_time = ${end_time}
n_startup_steps = ${n_startup_steps}
dtmax = ${dtmax}
dtmin = ${dtmin}
[TimeStepper]
type = IterationAdaptiveDT
dt = ${TimeStepper_dt}
optimal_iterations = ${TimeStepper_optimal_iterations}
iteration_window = ${TimeStepper_iteration_window}
linear_iteration_ratio = ${TimeStepper_linear_iteration_ratio}
timestep_limiting_function = power_history
force_step_every_function_point = true
[]
[]
[Postprocessors]
[clad_inner_vol]
type = InternalVolume
boundary = 7
outputs = exodus
[]
[fission_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = ${blocks_fuel}
outputs = exodus
[]
[fission_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = ${blocks_fuel}
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temperature
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temperature
boundary = 10
diffusivity = thermal_conductivity
[]
[rod_total_power]
type = ElementIntegralPower
variable = temperature
burnup_function = burnup
block = ${blocks_fuel}
[]
[average_fission_rate]
type = ElementAverageValue
variable = fission_rate
block = ${blocks_fuel}
[]
[max_fuel_temperature]
type = NodalExtremeValue
block = ${blocks_fuel}
value_type = max
variable = temperature
[]
[max_clad_temperature]
type = NodalExtremeValue
block = clad
value_type = max
variable = temperature
[]
[]
[StandardLWRFuelRodOutputs]
fuel_pellet_blocks = ${blocks_fuel}
temperature = temperature
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
[chkfile]
type = CSV
file_base = '${id}_chkfile'
show = ${chkfile_show}
execute_on = 'FINAL'
[]
[console]
type = Console
max_rows = 25
[]
[csv]
type = CSV
file_base = '${id}_csv'
[]
[exodus]
type = Exodus
file_base = '${id}_exodus'
[]
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM034/BFM034.i)
################################################################################
#
# Description: Calvert Cliffs BFM034
#
#
#
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFM034_power.csv
# axial peaking factor file BFM034_axial_peaking.csv
# flux boundary condition file BFM034_fast_flux.csv
################################################################################
initial_fuel_density = 10386.93
[GlobalParams]
density = ${initial_fuel_density} #94.662 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.31392
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFM034_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFM034_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 179410295 179410655'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 179410295 179410655'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFM034_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10386.93
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Dampers]
[limitT]
type = MaxIncrement
variable = temp
max_increment = 50
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 179410655
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
exodus = true
csv = true
color = false
print_linear_residuals = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(test/tests/gap_heat_transfer_mortar_action/gap_heat_transfer_mortar_transient_action_gap_conductance.i)
[GlobalParams]
displacements = 'disp_x disp_y'
[]
[Mesh]
patch_update_strategy = auto
patch_size = 2
[file]
type = FileMeshGenerator
file = 2blk-gap_no1000.e
[]
[]
[Variables]
[temperature]
order = FIRST
family = LAGRANGE
block = '1 2'
initial_condition = 1
[]
[disp_x]
block = '1 2'
[]
[disp_y]
block = '1 2'
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 100
secondary_boundary = 101
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temperature
variable = gap_conductance
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[all]
strain = FINITE
block = '1 2'
use_automatic_differentiation = true
[]
[]
[Materials]
[left]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 750
specific_heat = 1
[]
[right]
type = HeatConductionMaterial
block = 2
thermal_conductivity = 750
specific_heat = 1
[]
[elasticity_tensor]
type = ADComputeIsotropicElasticityTensor
youngs_modulus = 1e5
poissons_ratio = 0.345
block = '1 2'
[]
[_elastic_strain]
type = ADComputeFiniteStrainElasticStress
block = '1 2'
[]
[]
[Kernels]
[hc_fixed]
type = HeatConduction
variable = temperature
use_displaced_mesh = false
block = '1'
[]
[hc_moving]
type = HeatConduction
variable = temperature
use_displaced_mesh = true
block = '2'
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temperature
primary_boundary = 100
secondary_boundary = 101
emissivity_primary = 0.5
emissivity_secondary = 0.8
gascond_scalef = 1.0
contact_pressure = mechanical_normal_lm
min_gap = 1e-3
meyer_hardness_model = MATPRO
use_displaced_mesh = true
correct_edge_dropping = true
[]
[]
[Contact]
[mechanical]
model = frictionless
formulation = mortar
primary = 100
secondary = 101
c_normal = 1e+05
correct_edge_dropping = true
[]
[]
[Functions]
[disp_bc]
type = PiecewiseLinear
x = '0 10.0 1000.0'
y = '0 -0.30 -0.301'
[]
[]
[BCs]
[left]
type = DirichletBC
variable = temperature
boundary = 'left'
value = 400
[]
[right]
type = DirichletBC
variable = temperature
boundary = 'right'
value = 2
[]
[left_x]
type = DirichletBC
variable = disp_x
boundary = 'left'
value = 0.0
[]
[left_y]
type = DirichletBC
variable = disp_y
boundary = 'left'
value = 0.0
[]
[right_x]
type = FunctionDirichletBC
variable = disp_x
boundary = 'right'
function = disp_bc
[]
[right_y]
type = FunctionDirichletBC
variable = disp_y
boundary = 'right'
function = 0
[]
[]
[VectorPostprocessors]
[temperature_post]
type = NodalValueSampler
variable = temperature
boundary = '100'
sort_by = x
[]
[]
[Preconditioning]
[fmp]
type = SMP
full = true
[]
[]
[Executioner]
solve_type = PJFNK
type = Transient
dt = 1.0
dtmin = 1.0
end_time = 10.0
nl_rel_tol = 1e-8
nl_abs_tol = 1e-10
l_tol = 1e-5
petsc_options_iname = '-pc_type -snes_linesearch_type -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu basic NONZERO 1e-15'
snesmf_reuse_base = false
[]
[Outputs]
perf_graph = true
csv = true
exodus = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM070/BFM070.i)
################################################################################
#
# Description: Calvert Cliffs BFM070
#
#
#
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFM070_power.csv
# axial peaking factor file BFM070_axial_peaking.csv
# flux boundary condition file BFM070_fast_flux.csv
################################################################################
initial_fuel_density = 10386.93
[GlobalParams]
density = ${initial_fuel_density} #94.662 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.32168
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 3.85e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFM070_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFM070_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 179225682 179226042'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 179225682 179226042'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFM070_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = 1
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
# temperature = temp
# fast_neutron_flux = fast_neutron_flux
variable = oxide_thickness
boundary = 2
# use_coolant_channel = true # true when oxide_thickness is coupled with coolant channel model
# oxide_scale_factor = 1.0 # a scale factor to increase oxidation rate
# model_option = 1
# lithium_concentration = 1.5 # average Li concentration
# tin_content = 1.45 # %
# execute_on = timestep_end
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155 # m
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10386.93
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 179226042
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
perf_graph = true
exodus = true
csv = true
color = false
print_linear_residuals = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]
(assessment/LWR/validation/Calvert_Cliffs-1_PROTOTYPE/analysis/BFM156/BFM156.i)
################################################################################
#
# Description: Calvert Cliffs BFM156
#
# Boundary condition: Inlet temperature and mass flux
#
# External files:
# power history file BFM156_power.csv
# axial peaking factor file BFM156_axial_peaking.csv
# flux boundary condition file BFM156_fast_flux.csv
#
################################################################################
initial_fuel_density = 10411.07
[GlobalParams]
density = ${initial_fuel_density} #94.882 %TD Assume TD = 10972.65 kg/cm3
displacements = 'disp_x disp_y'
order = SECOND
energy_per_fission = 3.2e-11
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = 'ref'
extra_tag_vectors = 'ref'
converge_on = 'disp_x disp_y temp'
[]
[Mesh]
coord_type = RZ
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_mesh_density = customize
clad_thickness = 7.112e-4
pellet_mesh_density = customize
ny_p = 200
nx_c = 4
nx_p = 12
pellet_outer_radius = .00478155
ny_cu = 3
ny_c = 200
clad_bot_gap_height = 2.54e-3
pellet_quantity = 1
pellet_height = 3.47218
ny_cl = 3
clad_top_gap_height = 0.34015
clad_gap_width = 9.525e-5
elem_type = QUAD8
[]
patch_size = 20
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
[]
[Variables]
[disp_x]
[]
[disp_y]
[]
[temp]
initial_condition = 293
[]
[]
[AuxVariables]
[gap_conductance]
block = 'mechanical_secondary_subdomain'
[]
[fast_neutron_flux]
block = 1
[]
[fast_neutron_fluence]
block = 1
[]
[grain_radius]
block = 3
initial_condition = 4.2e-6
[]
[effective_creep_strain]
block = 1
order = CONSTANT
family = MONOMIAL
[]
[gap_cond]
order = CONSTANT
family = MONOMIAL
[]
[oxide_thickness]
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[power_history]
type = PiecewiseConstant
data_file = BFM156_power.csv
direction = right
format = columns
[]
[axial_peaking_factors]
type = PiecewiseBilinear
data_file = BFM156_axial_peaking.csv
scale_factor = 1
axis = 1
[]
[pressure_ramp]
type = PiecewiseLinear
x = '-100 0 177406235 177406595'
y = '0.0065315 1 1 0.0065315'
[]
[temp_ramp]
type = PiecewiseLinear
x = '-100 0 177406235 177406595'
y = '293 557.15 557.15 293'
[]
[flux]
type = PiecewiseLinear
data_file = BFM156_fast_flux.csv
format = columns
[]
[]
[Physics/SolidMechanics/QuasiStatic]
[pellets]
block = 3
strain = FINITE
eigenstrain_names = 'fuel_relocation_strain fuel_thermal_strain fuel_volumetric_strain'
generate_output = 'vonmises_stress hydrostatic_stress stress_xx stress_yy stress_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[clad]
block = 1
strain = FINITE
eigenstrain_names = 'clad_thermal_eigenstrain clad_irradiation_strain'
generate_output = 'vonmises_stress stress_xx stress_yy stress_zz creep_strain_xx creep_strain_yy creep_strain_xy creep_strain_zz strain_xx strain_yy strain_zz'
extra_vector_tags = 'ref'
[]
[]
[Kernels]
[heat]
type = HeatConduction
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_ie]
type = HeatConductionTimeDerivative
variable = temp
extra_vector_tags = 'ref'
block = '1 3'
[]
[heat_source]
type = NeutronHeatSource
variable = temp
block = 3
fission_rate = fission_rate
extra_vector_tags = 'ref'
[]
[]
[AuxKernels]
[gap_conductance]
type = GapConductanceMortar
primary_boundary = 5
secondary_boundary = 10
primary_subdomain = 'mechanical_primary_subdomain'
secondary_subdomain = 'mechanical_secondary_subdomain'
heat_flux = thermal_contact_thermal_lm
temperature = temp
variable = gap_conductance
[]
[fast_neutron_flux]
type = FastNeutronFluxAux
variable = fast_neutron_flux
block = 1
axial_power_profile = axial_peaking_factors
function = flux
factor = 4.8e17 #n/m2-s
execute_on = timestep_begin
[]
[grain_radius]
type = GrainRadiusAux
block = 3
variable = grain_radius
temperature = temp
execute_on = linear
[]
[fast_neutron_fluence]
type = FastNeutronFluenceAux
variable = fast_neutron_fluence
fast_neutron_flux = fast_neutron_flux
execute_on = timestep_begin
[]
[effective_creep_strain]
type = MaterialRealAux
property = effective_creep_strain
variable = effective_creep_strain
block = clad
execute_on = timestep_end
[]
[oxide]
type = MaterialRealAux
property = oxide_scale_thickness
variable = oxide_thickness
boundary = 2
[]
[]
[Burnup]
[burnup]
block = 3
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
num_radial = 81
num_axial = 11
a_lower = 0.00478
a_upper = 3.47696
fuel_inner_radius = 0.0
fuel_outer_radius = 0.00478155
fuel_volume_ratio = 1
isotopes = 'U235 U238 Pu239 Pu240 Pu241 Pu242'
isotope_fractions = '0.0367 .9633 0 0 0 0'
RPF = RPF
[]
[]
[Contact]
[mechanical]
model = coulomb
formulation = mortar
primary = 5
secondary = 10
friction_coefficient = 0.4
c_normal = 1e+12
c_tangential = 1e+24
tangential_lm_scaling = 1.0e-16
normal_lm_scaling = 1.0e-10
[]
[]
[ThermalContactMortar]
[thermal_contact]
secondary_variable = temp
primary_boundary = '5'
secondary_boundary = '10'
initial_moles = initial_moles
gas_released = fission_gas_released
jump_distance_model = LANNING
plenum_pressure = plenum_pressure
contact_pressure = mechanical_normal_lm
roughness_primary = 2e-6
roughness_secondary = 1e-6
roughness_coef = 3.2
thermal_lm_scaling = 1.0e-2
[]
[]
[BCs]
[no_x_all]
type = DirichletBC
variable = disp_x
boundary = 12
value = 0.0
[]
[no_y_clad_bottom]
type = DirichletBC
variable = disp_y
boundary = '1'
value = 0.0
[]
[no_y_fuel_bottom]
type = DirichletBC
variable = disp_y
boundary = '1020'
value = 0.0
[]
[Pressure]
[coolantPressure]
boundary = '1 2 3'
factor = 15.51320391e6
function = pressure_ramp
[]
[]
[PlenumPressure]
[plenumPressure]
boundary = 9
initial_pressure = 2.72342913e6
startup_time = 0
R = 8.3143
output_initial_moles = initial_moles
temperature = plenum_temperature
volume = plenum_volume
material_input = fission_gas_released
output = plenum_pressure
displacements = 'disp_x disp_y'
[]
[]
[]
[CoolantChannel]
[convective_clad_surface]
boundary = '1 2 3'
variable = temp
inlet_temperature = temp_ramp
inlet_pressure = 15.51320391e6
inlet_massflux = 3682.143 # kg/m^2-sec
rod_diameter = 0.011176 # m
rod_pitch = 1.473e-2 # m
linear_heat_rate = power_history
axial_power_profile = axial_peaking_factors
oxide_thickness = oxide_thickness
[]
[]
[Materials]
[fuel_density]
type = StrainAdjustedDensity
block = 3
strain_free_density = ${initial_fuel_density}
[]
[fuel_thermal]
type = UO2Thermal
block = 3
thermal_conductivity_model = NFIR
temperature = temp
burnup = burnup
[]
[fuel_elasticity_tensor]
type = UO2ElasticityTensor
block = 3
temperature = temp
[]
[fuel_elastic_stress]
type = ComputeFiniteStrainElasticStress
block = 3
[]
[fuel_thermal_expansion]
type = ComputeThermalExpansionEigenstrain
block = 3
thermal_expansion_coeff = 10.0e-6
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = fuel_thermal_strain
[]
[fuel_relocation]
type = UO2RelocationEigenstrain
block = 3
burnup_function = burnup
diameter = 0.0095631 #Fuel pellet diameter in m
rod_ave_lin_pow = power_history
axial_power_profile = axial_peaking_factors
diametral_gap =190.5e-6
relocation_activation1 = 5000
burnup_relocation_stop = 0.029
eigenstrain_name = fuel_relocation_strain
[]
[fuel_volumetric_swelling]
type = UO2VolumetricSwellingEigenstrain
block = 3
temperature = temp
burnup = burnup
initial_fuel_density = 10411.07
total_densification = 0.01
initial_porosity = 0.05
eigenstrain_name = fuel_volumetric_strain
[]
[ZryOxidation]
type = ZryOxidation
boundary = 2
clad_inner_radius = 0.0048768
clad_outer_radius = 0.005588
use_coolant_channel = true
temperature = temp
fast_neutron_flux = fast_neutron_flux
[]
[clad_thermal]
type = HeatConductionMaterial
block = 1
thermal_conductivity = 16.0
specific_heat = 330.0
[]
[clad_elasticity_tensor]
type = ZryElasticityTensor
block = clad
[]
[clad_stress]
type = ComputeMultipleInelasticStress
tangent_operator = elastic
inelastic_models = 'clad_zrycreep'
block = clad
[]
[clad_zrycreep]
type = ZryCreepLimbackHoppeUpdate
block = clad
temperature = temp
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
model_irradiation_creep = true
model_primary_creep = true
model_thermal_creep = true
[]
[thermal_expansion]
type = ZryThermalExpansionMATPROEigenstrain
block = clad
temperature = temp
stress_free_temperature = 293.0
eigenstrain_name = clad_thermal_eigenstrain
[]
[irradiation_swelling]
type = ZryIrradiationGrowthEigenstrain
block = clad
fast_neutron_fluence = fast_neutron_fluence
zircaloy_material_type = stress_relief_annealed
eigenstrain_name = clad_irradiation_strain
[]
[clad_density]
type = StrainAdjustedDensity
block = 1
strain_free_density = 6551.0
[]
[fission_gas_release]
type = UO2Sifgrs
block = 3
temperature = temp
fission_rate = fission_rate
grain_radius = grain_radius
gbs_model = true
burnup = burnup
transient_option = MICROCRACKING
[]
[]
# [Dampers]
# [limitT]
# type = MaxIncrement
# variable = temp
# max_increment = 50
# []
# []
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
petsc_options = '-snes_converged_reason -ksp_converged_reason -snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package -mat_mffd_err -pc_factor_shift_type '
'-pc_factor_shift_amount'
petsc_options_value = 'lu superlu_dist 1e-5 NONZERO 1e-12'
line_search = 'none'
verbose = true
l_max_its = 100
l_tol = 8e-3
nl_max_its = 100
nl_rel_tol = 1e-4
nl_abs_tol = 1e-8
start_time = -100
end_time = 177406595
dtmax = 1e6
dtmin = 1
[TimeStepper]
type = IterationAdaptiveDT
dt = 1e2
optimal_iterations = 200
linear_iteration_ratio = 100
timestep_limiting_function = power_history
max_function_change = 3e20
force_step_every_function_point = true
[]
[]
[Postprocessors]
[avg_gap_conductance]
type = ElementAverageValue
block = 'mechanical_secondary_subdomain'
variable = gap_conductance
execute_on = 'initial timestep_end'
[]
[clad_inner_vol]
type = InternalVolume
boundary = 7
[]
[fis_gas_grain]
type = ElementIntegralFisGasGrainSifgrs
block = 3
outputs = exodus
[]
[fis_gas_boundary]
type = ElementIntegralFisGasBoundarySifgrs
block = 3
outputs = exodus
[]
[flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 5
diffusivity = thermal_conductivity
[]
[flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = temp
boundary = 10
diffusivity = thermal_conductivity
[]
[average_fission_rate]
type = ElementAverageValue
block = 3
variable = fission_rate
[]
[rod_ave_lin_pow]
type = ElementIntegralPower
block = 3
fission_rate = fission_rate
variable = temp
[]
[disp_y_3023]
type = NodalVariableValue
nodeid = 3022
variable = disp_y
[]
[]
[StandardLWRFuelRodOutputs]
temperature = temp
fuel_pellet_blocks = 3
[]
[PerformanceMetricOutputs]
[]
[Outputs]
exodus = true
csv = true
color = false
print_linear_residuals = true
perf_graph = true
[console]
type = Console
max_rows = 40
[]
[chkfile]
type = CSV
show = 'average_centerline_fuel_temperature fission_gas_released_percentage maximum_clad_elongation maximum_fuel_elongation'
execute_on = 'FINAL'
[]
[]
[Debug]
show_var_residual = 'disp_x disp_y temp'
show_var_residual_norms = true
[]