- axial_power_profileFunction that describes the axial power profile as a function of axial position and time.
C++ Type:FunctionName
Unit:(no unit assumed)
Controllable:No
Description:Function that describes the axial power profile as a function of axial position and time.
- initial_X_PuInitial atom fraction of plutonium
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Initial atom fraction of plutonium
- initial_X_ZrInitial atom fraction of zirconium
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Initial atom fraction of zirconium
- initial_densityInitial density of the fuel
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Initial density of the fuel
- pellet_radiusFuel pellet radius
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Fuel pellet radius
- rod_linear_powerFunction that describes the linear power as a function of time.
C++ Type:FunctionName
Unit:(no unit assumed)
Controllable:No
Description:Function that describes the linear power as a function of time.
UPuZrFastNeutronFlux
Computes fast neutron flux and fluence for UPuZr.
Description
The fast neutron flux, can be estimated by back-calculating the total flux, , from the axial fission rate density, , dividing by the macroscopic cross section estimated from the initial isotopics of the fuel, , and estimating the ratio of fast to total neutron flux, ,
The axial fission rate density can be calculated using the average rod power and axial profile, similar to the treatment in UPuZrFissionRate in cylindrical 2DRz geometry only (i.e. radial direction and axial direction ). is calculated based on the rod linear power and axial power profile as, where (J/fsn) is the energy released per fission event.
is passed as a Function given only as a function of time. This function corresponds to the power produced by the entire fuel pin.
is also passed as a Function, only as a function of time and axial position. This can be completed in any Function, but is typically provided via PowerPeakingFunction. represents the ratio between the power at any axial slice of the fuel and the total rod power , and must be normalized to return an average value of 1 over the entire length of the rod, where is the length of the rod.
The macroscopic cross section can be estimated from the weighted sum of number density of the individual fuel constituents by their microscopic fission cross-sections , where the set of all constituents is taken as {U-235, U-238, Pu-239, Pu-240}. The individual number densities are calculated from the atom weights of the constituents, , the atom fractions of each constituent , and the total fuel density, ,
The microscopic fission cross-sections implemented as defaults in UPuZrFastNeutronFlux are collapsed one-group cross-sections from the eight-group cross sections provided in Waltar et al. (2011), weighted for the EBR-II flux spectrum, as provided by Withop et al. (1969).
The ratio of the fast to total neutron flux, is estimated from Withop et al. (1969), and corresponds to the neutron flux with energies above 0.1 MeV.
Given the flux at each timestep, the fast neutron fluence can be optionally calculated via an average over the current and previous time step,
Similarly, the displacements per atom (dpa) can be calculated assuming a conversion factor of n/m per dpa from Waltar et al. (2011),
Example Input Syntax
[Materials<<<{"href": "../../syntax/Materials/index.html"}>>>]
[flux]
type = UPuZrFastNeutronFlux<<<{"description": "Computes fast neutron flux and fluence for UPuZr.", "href": "UPuZrFastNeutronFlux.html"}>>>
axial_power_profile<<<{"description": "Function that describes the axial power profile as a function of axial position and time."}>>> = power_history
rod_linear_power<<<{"description": "Function that describes the linear power as a function of time."}>>> = axial_peaking_factors
initial_X_Pu<<<{"description": "Initial atom fraction of plutonium"}>>> = 0.2
initial_X_Zr<<<{"description": "Initial atom fraction of zirconium"}>>> = 0.1
initial_density<<<{"description": "Initial density of the fuel"}>>> = 15800
pellet_radius<<<{"description": "Fuel pellet radius"}>>> = 0.003
enrichment_Pu240<<<{"description": "Initial ratio of Pu-240 to total plutonium"}>>> = 0.3
enrichment_U235<<<{"description": "Initial ratio of U-235 to total uranium"}>>> = 0.2
outputs<<<{"description": "Vector of output names where you would like to restrict the output of variables(s) associated with this object"}>>> = all
calculate_fluence<<<{"description": "Flag to calculate total neutron fluence from the fast flux."}>>> = true
[]
[]Input Parameters
- blockThe list of blocks (ids or names) that this object will be applied
C++ Type:std::vector<SubdomainName>
Controllable:No
Description:The list of blocks (ids or names) that this object will be applied
- boundaryThe list of boundaries (ids or names) from the mesh where this object applies
C++ Type:std::vector<BoundaryName>
Controllable:No
Description:The list of boundaries (ids or names) from the mesh where this object applies
- calculate_dpaFalseFlag to calculate dpa.
Default:False
C++ Type:bool
Controllable:No
Description:Flag to calculate dpa.
- calculate_dpa_rateFalseFlag to calculate dpa rate.
Default:False
C++ Type:bool
Controllable:No
Description:Flag to calculate dpa rate.
- calculate_fluenceFalseFlag to calculate total neutron fluence from the fast flux.
Default:False
C++ Type:bool
Controllable:No
Description:Flag to calculate total neutron fluence from the fast flux.
- computeTrueWhen false, MOOSE will not call compute methods on this material. The user must call computeProperties() after retrieving the MaterialBase via MaterialBasePropertyInterface::getMaterialBase(). Non-computed MaterialBases are not sorted for dependencies.
Default:True
C++ Type:bool
Controllable:No
Description:When false, MOOSE will not call compute methods on this material. The user must call computeProperties() after retrieving the MaterialBase via MaterialBasePropertyInterface::getMaterialBase(). Non-computed MaterialBases are not sorted for dependencies.
- constant_onNONEWhen ELEMENT, MOOSE will only call computeQpProperties() for the 0th quadrature point, and then copy that value to the other qps.When SUBDOMAIN, MOOSE will only call computeQpProperties() for the 0th quadrature point, and then copy that value to the other qps. Evaluations on element qps will be skipped
Default:NONE
C++ Type:MooseEnum
Options:NONE, ELEMENT, SUBDOMAIN
Controllable:No
Description:When ELEMENT, MOOSE will only call computeQpProperties() for the 0th quadrature point, and then copy that value to the other qps.When SUBDOMAIN, MOOSE will only call computeQpProperties() for the 0th quadrature point, and then copy that value to the other qps. Evaluations on element qps will be skipped
- declare_suffixAn optional suffix parameter that can be appended to any declared 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 declared properties. The suffix will be prepended with a '_' character.
- dpa_conversion_factor2e+25Conversion factor from fast neutron fluence to dpa, in [n/m^2 per dpa].
Default:2e+25
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Conversion factor from fast neutron fluence to dpa, in [n/m^2 per dpa].
- dpa_namedpaName of the dpa material property this object creates
Default:dpa
C++ Type:MaterialPropertyName
Unit:(no unit assumed)
Controllable:No
Description:Name of the dpa material property this object creates
- energy_per_fission3.28451e-11energy per fission
Default:3.28451e-11
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:energy per fission
- enrichment_Pu2400.1Initial ratio of Pu-240 to total plutonium
Default:0.1
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Initial ratio of Pu-240 to total plutonium
- enrichment_U2350.67Initial ratio of U-235 to total uranium
Default:0.67
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Initial ratio of U-235 to total uranium
- fast_neutron_fluence_namefast_neutron_fluenceName of the fast neutrom flux material property this object creates
Default:fast_neutron_fluence
C++ Type:MaterialPropertyName
Unit:(no unit assumed)
Controllable:No
Description:Name of the fast neutrom flux material property this object creates
- fast_neutron_flux_namefast_neutron_fluxName of the fast neutrom flux material property this object creates
Default:fast_neutron_flux
C++ Type:MaterialPropertyName
Unit:(no unit assumed)
Controllable:No
Description:Name of the fast neutrom flux material property this object creates
- fast_spectrum_ratio0.9Ratio of fast flux (greater than 0.1 MeV) to total flux.
Default:0.9
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Ratio of fast flux (greater than 0.1 MeV) to total flux.
- pellet_inner_radius0Pellet inner radius
Default:0
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Pellet inner radius
- sigma_Pu2391.658Collapsed one-group fission cross-section for plutonium-239 [b]
Default:1.658
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Collapsed one-group fission cross-section for plutonium-239 [b]
- sigma_Pu2400.703Collapsed one-group fission cross-section for plutonium-240 [b]
Default:0.703
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Collapsed one-group fission cross-section for plutonium-240 [b]
- sigma_U2351.327Collapsed one-group fission cross-section for uranium-235 [b]
Default:1.327
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Collapsed one-group fission cross-section for uranium-235 [b]
- sigma_U2380.095Collapsed one-group fission cross-section for uranium-238 [b]
Default:0.095
C++ Type:double
Unit:(no unit assumed)
Controllable:No
Description:Collapsed one-group fission cross-section for uranium-238 [b]
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.
- implicitTrueDetermines whether this object is calculated using an implicit or explicit form
Default:True
C++ Type:bool
Controllable:No
Description:Determines whether this object is calculated using an implicit or explicit form
- 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_meshFalseWhether or not this object should use the displaced mesh for computation. Note that in the case this is true but no displacements are provided in the Mesh block the undisplaced mesh will still be used.
Default:False
C++ Type:bool
Controllable:No
Description:Whether or not this object should use the displaced mesh for computation. Note that in the case this is true but no displacements are provided in the Mesh block the undisplaced mesh will still be used.
Advanced Parameters
- output_propertiesList of material properties, from this material, to output (outputs must also be defined to an output type)
C++ Type:std::vector<std::string>
Controllable:No
Description:List of material properties, from this material, to output (outputs must also be defined to an output type)
- outputsnone Vector of output names where you would like to restrict the output of variables(s) associated with this object
Default:none
C++ Type:std::vector<OutputName>
Controllable:No
Description:Vector of output names where you would like to restrict the output of variables(s) associated with this object
Outputs 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
References
- A.E. Waltar, D.R. Todd, and P.V. Tsvetkov.
Fast Spectrum Reactors.
Springer US, 2011.
ISBN 9781441995728.
URL: https://books.google.com/books?id=z8z\_RNUZSbEC.[BibTeX]
@book{waltar2011fast, author = "Waltar, A.E. and Todd, D.R. and Tsvetkov, P.V.", title = "Fast Spectrum Reactors", isbn = "9781441995728", lccn = "2011935931", url = "https://books.google.com/books?id=z8z\\_RNUZSbEC", year = "2011", publisher = "Springer US" } - A Withop, B A Hutchins, and G C Martin.
Analytical Procedures and Applications of Fluence Determinations from EBR-II Flux Wires.
Technical Report, General Electric Company, January 1969.[BibTeX]
@techreport{Withop:1969ct, author = "Withop, A and Hutchins, B A and Martin, G C", title = "{Analytical Procedures and Applications of Fluence Determinations from EBR-II Flux Wires}", institution = "General Electric Company", year = "1969", month = "January" }
(test/tests/upuzr_fast_neutron_flux/nonad.i)
# This test checks the fast neutron flux calculated UPuZrFastNeutronFlux coupled to a variable
[Mesh]
coord_type = RZ
[mesh]
type = GeneratedMeshGenerator
dim = 2
nx = 4
ny = 10
ymax = 0.343
xmax = 0.002
[]
[]
[Variables]
[damage]
[]
[]
[Kernels]
[damage_dt]
type = TimeDerivative
variable = damage
[]
[damage_generation]
type = FissionRateHeatSource
fission_rate = fast_neutron_flux
variable = damage
[]
[]
[Functions]
[power_history]
type = PiecewiseLinear
x = '0 1'
y = '0 30000'
[]
[axial_peaking_factors]
type = PowerPeakingFunction
fit = EBRII_ROW_3
pellet_length = 343.0e-3
pellet_y_start = 2.55e-3
[]
[]
[Materials]
[flux]
type = UPuZrFastNeutronFlux
axial_power_profile = power_history
rod_linear_power = axial_peaking_factors
initial_X_Pu = 0.2
initial_X_Zr = 0.1
initial_density = 15800
pellet_radius = 0.003
enrichment_Pu240 = 0.3
enrichment_U235 = 0.2
outputs = all
calculate_fluence = true
[]
[]
[Executioner]
type = Transient
dt = 0.1
num_steps = 5
[]
[Postprocessors]
[flux_avg]
type = ElementAverageValue
variable = fast_neutron_flux
[]
[fluence_avg]
type = ElementAverageValue
variable = fast_neutron_fluence
[]
[damage_avg]
type = ElementAverageValue
variable = damage
[]
[]
[Outputs]
exodus = true
[]
(test/tests/upuzr_fast_neutron_flux/nonad.i)
# This test checks the fast neutron flux calculated UPuZrFastNeutronFlux coupled to a variable
[Mesh]
coord_type = RZ
[mesh]
type = GeneratedMeshGenerator
dim = 2
nx = 4
ny = 10
ymax = 0.343
xmax = 0.002
[]
[]
[Variables]
[damage]
[]
[]
[Kernels]
[damage_dt]
type = TimeDerivative
variable = damage
[]
[damage_generation]
type = FissionRateHeatSource
fission_rate = fast_neutron_flux
variable = damage
[]
[]
[Functions]
[power_history]
type = PiecewiseLinear
x = '0 1'
y = '0 30000'
[]
[axial_peaking_factors]
type = PowerPeakingFunction
fit = EBRII_ROW_3
pellet_length = 343.0e-3
pellet_y_start = 2.55e-3
[]
[]
[Materials]
[flux]
type = UPuZrFastNeutronFlux
axial_power_profile = power_history
rod_linear_power = axial_peaking_factors
initial_X_Pu = 0.2
initial_X_Zr = 0.1
initial_density = 15800
pellet_radius = 0.003
enrichment_Pu240 = 0.3
enrichment_U235 = 0.2
outputs = all
calculate_fluence = true
[]
[]
[Executioner]
type = Transient
dt = 0.1
num_steps = 5
[]
[Postprocessors]
[flux_avg]
type = ElementAverageValue
variable = fast_neutron_flux
[]
[fluence_avg]
type = ElementAverageValue
variable = fast_neutron_fluence
[]
[damage_avg]
type = ElementAverageValue
variable = damage
[]
[]
[Outputs]
exodus = true
[]
(test/tests/upuzr_fast_neutron_flux/rods.i)
# This test checks the fast neutron flux calculated UPuZrFastNeutronFlux for a series of rods, and
# ensures the correct values are calculated depending on a mix of flux, fluence, and dpa calculation
# options.
[Problem]
solve = false
[]
[Mesh]
coord_type = RZ
# rod specific parameters
[smeared_pellet_mesh]
type = FuelPinMeshGenerator
clad_thickness = 0.381e-03
pellet_outer_radius = 2.197e-03
pellet_height = 344.3e-3
clad_top_gap_height = 2.979e-1
clad_gap_width = 0.348e-03
bottom_clad_height = 2.24e-3 # arbitrary
top_clad_height = 2.24e-3 # arbitrary
clad_bot_gap_height = 0.31e-3 # arbitrary
# meshing parameters
clad_mesh_density = customize
pellet_mesh_density = customize
nx_p = 3
ny_p = 10
nx_c = 4
ny_c = 30
ny_cu = 3
ny_cl = 3
pellet_quantity = 1
[]
# mesh options
partitioner = centroid
centroid_partitioner_direction = y
[]
[DefaultElementQuality]
failure_type = Warning
[]
[Functions]
[dp11]
type = PiecewiseLinear
x = '0 10 20'
y = '0 23000 32000'
[]
[dp16]
type = PiecewiseLinear
x = '0 10 20'
y = '0 44000 48000'
[]
[dp81]
type = PiecewiseLinear
x = '0 10 20'
y = '0 29000 32000'
[]
[t179]
type = PiecewiseLinear
x = '0 10 20'
y = '0 40000 42000'
[]
[row_3]
type = PowerPeakingFunction
fit = EBRII_ROW_3
pellet_length = 343.0e-3
pellet_y_start = 2.55e-3
zero_beyond_top_and_bottom = false
[]
[row_4]
type = PowerPeakingFunction
fit = EBRII_ROW_4
pellet_length = 343.0e-3
pellet_y_start = 2.55e-3
zero_beyond_top_and_bottom = false
[]
[]
[Materials]
[dp11]
type = UPuZrFastNeutronFlux
axial_power_profile = row_3
rod_linear_power = dp11
initial_X_Pu = 0
initial_X_Zr = 0.225
initial_density = 15800
pellet_radius = 2.192e-03
enrichment_U235 = 0.675
outputs = all
fast_neutron_flux_name = dp11_flux
[]
[dp16]
type = UPuZrFastNeutronFlux
axial_power_profile = dp16
rod_linear_power = row_4
initial_X_Pu = 0.163
initial_X_Zr = 0.225
initial_density = 15800
pellet_radius = 2.192e-03
enrichment_Pu240 = 0.109
enrichment_U235 = 0.697
outputs = all
fast_neutron_flux_name = dp16_flux
dpa_name = dp16_dpa
calculate_dpa = true
[]
[dp81]
type = UPuZrFastNeutronFlux
axial_power_profile = dp81
rod_linear_power = row_3
initial_X_Pu = 0
initial_X_Zr = 0.225
initial_density = 15800
pellet_radius = 2.192e-03
enrichment_U235 = 0.675310345
outputs = all
fast_neutron_flux_name = dp81_flux
fast_neutron_fluence_name = dp81_fluence
calculate_fluence = true
[]
[t179]
type = UPuZrFastNeutronFlux
axial_power_profile = t179
rod_linear_power = row_4
initial_X_Pu = 0.163
initial_X_Zr = 0.225
initial_density = 15800
pellet_radius = 2.192e-03
enrichment_Pu240 = 0.057
enrichment_U235 = 0.573
outputs = all
fast_neutron_flux_name = t179_flux
fast_neutron_fluence_name = t179_fluence
dpa_name = t179_dpa
calculate_dpa = true
calculate_fluence = true
[]
[]
[Executioner]
type = Transient
num_steps = 2
dt = 10
[]
[Postprocessors]
[dp11_flux_avg]
type = ElementAverageValue
variable = dp11_flux
[]
[dp16_flux_avg]
type = ElementAverageValue
variable = dp16_flux
[]
[dp81_flux_avg]
type = ElementAverageValue
variable = dp81_flux
[]
[t179_flux_avg]
type = ElementAverageValue
variable = t179_flux
[]
[dp16_dpa_avg]
type = ElementAverageValue
variable = dp16_dpa
[]
[dp81_fluence_avg]
type = ElementAverageValue
variable = dp81_fluence
[]
[t179_fluence_avg]
type = ElementAverageValue
variable = t179_fluence
[]
[t179_dpa_avg]
type = ElementAverageValue
variable = t179_dpa
[]
[]
[VectorPostprocessors]
[cladding_flux]
type = LineMaterialRealSampler
property = 'dp11_flux dp16_flux dp81_flux t179_flux'
start = '0.0027 0 0'
end = '0.0027 0.6469 0'
sort_by = y
[]
[]
[Outputs]
csv = true
[]
(assessment/metallic_fuel/FFTF/IFR1/analysis/IFR1_base.i)
# IFR-1 ASSESSMENT CASE
# BISON recreation of the 169-pin IFR-1 experiment, which was irradiated in the
# FFTF from 9/1986 to 10/1988 to a peak burnup of about 10 at%. The assessment
# consists of three generic pins (U-10Zr, U-8Pu-10Zr, and U-19Pu-10Zr) which
# are compared against all available legacy calculations and PIE measurements
# for all 169 pins in the experiment. Composition-specific values are stored in
# three '.params' files. Units are in standard SI: J, K, kg, m, Pa, s.
# For a more complete description of the experiment, see [Dodds, 1986-1],
# [Dodds, 1986-2], [Porter and Tsai, 2011], and [Tsai et al., 1986]. For a more
# complete description of development and results of this assessment, see
# [Greenquist et al., 2021].
#
# To simulate one of the cases, use the combined input file option
# with one of the '.params' files. For example:
# mpiexec -n 4 ../../../../../bison-opt -i 'IFR1_base.i U-10Zr.params'
initial_fuel_density = 15800
[GlobalParams]
dim = 2
order = SECOND
family = LAGRANGE
elem_type = QUAD8
energy_per_fission = 3.2e-11 # [Shultis and Faw, 2008]
volumetric_locking_correction = false
displacements = 'disp_x disp_y'
temperature = T
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = ref
extra_tag_vectors = ref
[]
[Mesh]
coord_type = RZ
# Mesh includes a fuel slug, top and bottom blanket slugs, and cladding. All
# dimensions are in meters (m). Nominal dimensions come from [Dodds, 1986-2].
type = MeshGeneratorMesh
patch_size = 30
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
# build cladding
[bottom_plug]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.00287
nx = 3
ymin = 0.0
ymax = 0.015
ny = 5
[]
[bottom_corner]
type = GeneratedMeshGenerator
xmin = 0.00287
xmax = 0.00343
nx = 4
ymin = 0.0
ymax = 0.015
ny = 5
[]
[bottom_corner_rename_side]
type = SideSetsFromNormalsGenerator
input = bottom_corner
normals = '0 1 0'
new_boundary = new_side
[]
[combine_bottom_and_bottom_corner]
type = StitchedMeshGenerator
inputs = 'bottom_plug bottom_corner_rename_side'
stitch_boundaries_pairs = 'right left'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[cladding_wall]
type = GeneratedMeshGenerator
xmin = 0.00287
xmax = 0.00343
nx = 4
ymin = 0.015
ymax = 2.239
ny = 400
[]
[cladding_wall_rename_side]
type = SideSetsFromNormalsGenerator
input = cladding_wall
normals = '0 1 0'
new_boundary = new_side
[]
[combine_bottom_and_wall]
type = StitchedMeshGenerator
inputs = 'combine_bottom_and_bottom_corner cladding_wall_rename_side'
stitch_boundaries_pairs = '4 bottom'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[top_corner]
type = GeneratedMeshGenerator
xmin = 0.00287
xmax = 0.00343
nx = 4
ymin = 2.239
ymax = 2.254
ny = 5
[]
[top_corner_rename_side]
type = SideSetsFromNormalsGenerator
input = top_corner
normals = '-1 0 0'
new_boundary = new_side
[]
[combine_wall_and_top_corner]
type = StitchedMeshGenerator
inputs = 'combine_bottom_and_wall top_corner_rename_side'
stitch_boundaries_pairs = '4 bottom'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[top_plug]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.00287
nx = 3
ymin = 2.239
ymax = 2.254
ny = 5
[]
[cladding_all]
type = StitchedMeshGenerator
inputs = 'combine_wall_and_top_corner top_plug'
stitch_boundaries_pairs = '4 right'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
# build fuel and blanket
[bottom_blanket]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.00249
nx = 6
ymin = 0.0162
ymax = 0.1812
ny = 40
[]
[fuel_slug]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.00249
nx = 6
ymin = 0.1812
ymax = 1.0956
ny = 300
[]
[top_blanket]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.00249
nx = 6
ymin = 1.0956
ymax = 1.2606
ny = 40
[]
[fuel_two]
type = StitchedMeshGenerator
inputs = 'bottom_blanket fuel_slug'
stitch_boundaries_pairs = 'top bottom'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[fuel_all]
type = StitchedMeshGenerator
inputs = 'fuel_two top_blanket'
stitch_boundaries_pairs = 'top bottom'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
# combine and name subdomains
[combine_fuel_cladding]
type = CombinerGenerator
inputs = 'cladding_all fuel_all'
[]
[name_cladding]
type = SubdomainBoundingBoxGenerator
input = combine_fuel_cladding
bottom_left = '0.0 0.0 0.0'
top_right = '0.00343 2.254 0'
location = INSIDE
block_id = 0
block_name = clad
[]
[name_blanket]
type = SubdomainBoundingBoxGenerator
input = name_cladding
bottom_left = '0.0 0.0162 0.0'
top_right = '0.00249 1.2606 0.0'
location = INSIDE
block_id = 1
block_name = blanket
[]
[name_fuel]
type = SubdomainBoundingBoxGenerator
input = name_blanket
bottom_left = '0.0 0.1812 0.0'
top_right = '0.00249 1.0956 0.0'
location = INSIDE
block_id = 2
block_name = pellet
[]
# name boundaries
[name_centerline]
type = SideSetsFromNormalsGenerator
input = name_fuel
normals = '-1 0 0'
new_boundary = centerline
replace = true
[]
[name_slug_outer_surface]
type = SideSetsFromNormalsGenerator
input = name_centerline
normals = '1 0 0'
new_boundary = pellet_outer_radial_surface
replace = true
[]
[name_slug_ends]
type = SideSetsFromPointsGenerator
input = name_slug_outer_surface
points = '0.50e-3 0.0162 0.0
0.50e-3 1.2606 0.0'
new_boundary = 'bottom_of_bottom_pellet top_of_top_pellet'
replace = true
[]
[name_cladding_inside]
type = SideSetsFromPointsGenerator
input = name_slug_ends
points = '0.50e-3 0.015 0.0
0.00287 1.0956 0.0
0.50e-3 2.239 0.0'
new_boundary = 'clad_inside_bottom clad_inside_right clad_inside_top'
replace = true
[]
[name_cladding_outer_surface]
type = SideSetsFromPointsGenerator
input = name_cladding_inside
points = '0.00343 1.0956 0.0
0.50e-3 0.0 0.0
0.50e-3 2.254 0.0'
new_boundary = 'clad_outside_right clad_outside_bottom clad_outside_top'
replace = true
[]
[]
[Variables]
[T] # Temperature (K)
initial_condition = 298
[]
[]
[AuxVariables]
[gap_conductance]
order = CONSTANT
family = MONOMIAL
[]
[fuel_clad_gap_width]
order = FIRST
family = LAGRANGE
[]
[element_failed]
order = CONSTANT
family = MONOMIAL
[]
[fuel_volumetric_strain]
block = 'pellet blanket'
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_stress]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_creep_strain]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_elastic_strain]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_total_strain]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[local_power]
block = 'pellet blanket'
order = CONSTANT
family = MONOMIAL
[]
[T_coolant]
order = CONSTANT
family = MONOMIAL
[]
[pin_lhr]
block = 'pellet blanket'
order = CONSTANT
family = MONOMIAL
[]
[eutectic_thickness]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[assembly_lhr_avg_function]
# Subassembly average power as a function of time. x: time (s), y: Average
# LHGR (W/m). See [Greenquist et al., 2021].
type = PiecewiseLinear
x = '0 3600 11900880 11904480 21097440 21101040 29542320 29545920
35274240 35277840 42665040 42668640 53615520 53619120 53705520 53791920'
y = '0 38276 36089 33902 31988 33355 31988 30074
29254 27614 25153 26520 26247 26.2 26.2 26.2'
[]
[lhr_peaking_factor_function]
# Axial variation from the average LHGR. See [Porter and Tsai, 2011] and
# [Greenquist et al., 2021].
type = ParsedFunction
symbol_names = 'a0 a1 a2 a3 a4 mb bb mt bt
z_bot z_top bu_final bu_now'
symbol_values = '0.68687 2.6352 -3.20026 1.35e-5 2.69e-5 0.279 0.084 -0.301 0.416
0.1812 1.0956 0.05 burnup_max'
expression = 'bu_frac := bu_now / bu_final;
p_bot := (mb * y + bb) * bu_frac;
p_top := (mt * y + bt) * bu_frac;
z_bbot := 0.0162; p_b := if(y < z_bbot, 0, p_bot);
z_btop := 1.2606; p_t := if(y > z_btop, 0, p_top);
z1 := y - z_bot;
p_mid := a0 + a1 * z1 + a2 * z1^2 + a3 * z1^3 + a4 * z1^4;
if(y < z_bot, p_b, if(y > z_top, p_t, p_mid))'
[]
[pin_lhr_function]
type = CompositeFunction
functions = 'assembly_lhr_avg_function lhr_peaking_factor_function'
[]
[coolant_flux_function]
# Subassembly coolant mass flux. x: time (s), y: flux (kg m^-2 s^-1). See
# [Porter and Tsai, 2011].
type = PiecewiseLinear
x = '0 3600 11900880 11904480 21097440 21101040 29542320 29545920
42665040 42668640 53615520 53619120 53791920'
y = '5690 5740 5740 5900 5900 5930 5930 6040
6040 6090 6090 5690 5690'
[]
[coolant_pressure_function]
# Constant coolant inlet pressure (Pa) taken from [Cabell, 1980].
type = ConstantFunction
value = 1018327
[]
[coolant_T_in_function]
# Sodium coolant inlet temperature (K). See [Porter and Tsai, 2011] and
# [Greenquist et al., 2021].
type = PiecewiseLinear
x = '0 3600 53619120 53705520 53791920'
y = '298.0 633.15 633.15 305.0 305.0'
[]
[sodium_volume_function]
# The initial sodium height is assumed to be equal to the initial fuel
# height and sodium infiltration is ignored.
type = ParsedFunction
symbol_names = 'pellet_outer_radius cladding_gap_width blanket_top blanket_bottom'
symbol_values = '0.00249 0.00038 1.2606 0.0162'
expression = 'pi * ((pellet_outer_radius + cladding_gap_width)^2 -
pellet_outer_radius^2) * (blanket_top - blanket_bottom)'
[]
[gas_volume_function]
type = ParsedFunction
symbol_names = 'clad_internal_volume fuel_volume sodium_volume'
symbol_values = 'clad_internal_volume fuel_volume sodium_volume'
expression = 'abs(clad_internal_volume) - abs(fuel_volume) - abs(sodium_volume)'
[]
[sodium_conductivity_function]
# Thermal conductivity (W m^-1 K^-1) of the pin gap sodium according to
# [Fink and Leibowitz, 1995]
type = ParsedFunction
symbol_names = 'A B C D'
symbol_values = '124.67 -0.11381 5.5226e-5 -1.1842e-8'
expression = 'A + B * t + C * t^2 + D * t^3'
[]
[creep_timestep_min_function]
type = ParsedFunction
symbol_names = 'creep_timestep_fuel creep_timestep_blanket creep_timestep_clad'
symbol_values = 'creep_timestep_fuel creep_timestep_blanket creep_timestep_clad'
expression = 'min(min(creep_timestep_fuel, creep_timestep_blanket),
creep_timestep_clad)'
[]
[fuel_axial_elongation_max_pct_function]
type = ParsedFunction
symbol_names = 'fuel_axial_elongation_min fuel_axial_elongation_max pellet_height'
symbol_values = 'fuel_axial_elongation_min fuel_axial_elongation_max 0.9144'
expression = '(fuel_axial_elongation_max - fuel_axial_elongation_min) /
pellet_height * 100'
[]
[fuel_radial_dilation_max_pct_function]
type = ParsedFunction
symbol_names = 'fuel_radial_dilation_max pellet_outer_radius'
symbol_values = 'fuel_radial_dilation_max 0.00249'
expression = 'fuel_radial_dilation_max / pellet_outer_radius * 100'
[]
[clad_axial_elongation_max_pct_function]
type = ParsedFunction
symbol_names = 'clad_axial_elongation_max plug_height cladding_total_height'
symbol_values = 'clad_axial_elongation_max 0.015 2.254'
expression = 'clad_axial_elongation_max / (plug_height + cladding_total_height) *
100'
[]
[clad_radial_dilation_max_pct_function]
type = ParsedFunction
symbol_names = 'clad_radial_dilation_max cladding_outer_radius'
symbol_values = 'clad_radial_dilation_max 0.00343'
expression = 'clad_radial_dilation_max / cladding_outer_radius * 100'
[]
[plenum_compressibility_function]
# Accounts for nonideality in fission gas [Hobbs and Charboneau, 2020].
type = ParsedFunction
symbol_names = 'plenum_pressure A B C'
symbol_values = 'plenum_pressure 1.002 -3.4e-8 -1.9e-15'
expression = 'A + B * plenum_pressure + C * plenum_pressure^2'
[]
[compressibility_times_temperature_function]
type = ParsedFunction
symbol_names = 'plenum_temperature plenum_compressibility'
symbol_values = 'plenum_temperature plenum_compressibility'
expression = 'plenum_temperature * plenum_compressibility'
[]
[]
[Physics/SolidMechanics/QuasiStatic]
add_variables = true
strain = FINITE
generate_output = 'stress_xx stress_yy stress_zz vonmises_stress
hydrostatic_stress creep_strain_xx creep_strain_yy
creep_strain_zz elastic_strain_xx elastic_strain_yy
elastic_strain_zz strain_xx strain_yy strain_zz'
[fuel_mechanics]
block = 'pellet blanket'
eigenstrain_names = 'fuel_thermal_strain fuel_gaseous_strain
fuel_solid_strain'
extra_vector_tags = ref
[]
[clad_mechanics]
block = clad
eigenstrain_names = 'clad_thermal_strain clad_gaseous_strain'
extra_vector_tags = ref
[]
[]
[Kernels]
[gravity]
type = Gravity
variable = disp_y
value = -9.81
extra_vector_tags = ref
[]
[heat_conduction_time_derivative]
type = HeatConductionTimeDerivative
variable = T
extra_vector_tags = ref
[]
[heat_conduction]
type = HeatConduction
variable = T
extra_vector_tags = ref
[]
[heat_source]
type = FissionRateHeatSource
block = 'pellet blanket'
variable = T
fission_rate = fission_rate
extra_vector_tags = ref
[]
[]
[AuxKernels]
[gap_conductance]
type = MaterialRealAux
variable = gap_conductance
property = gap_conductance
boundary = pellet_outer_radial_surface
[]
[fuel_clad_gap_width]
type = ParsedAux
variable = fuel_clad_gap_width
coupled_variables = penetration
expression = '-penetration'
[]
[failed_element]
type = MaterialRealAux
variable = element_failed
property = failed
boundary = clad_outside_right
[]
[fuel_volumetric_strain]
type = RankTwoScalarAux
block = 'pellet blanket'
variable = fuel_volumetric_strain
rank_two_tensor = total_strain
scalar_type = VolumetricStrain
[]
[clad_hoop_stress]
type = RankTwoAux
block = clad
variable = clad_hoop_stress
rank_two_tensor = stress
index_i = 2
index_j = 2
[]
[clad_hoop_creep_strain]
type = RankTwoAux
block = clad
variable = clad_hoop_creep_strain
rank_two_tensor = creep_strain
index_i = 2
index_j = 2
[]
[clad_hoop_elastic_strain]
type = RankTwoAux
block = clad
variable = clad_hoop_elastic_strain
rank_two_tensor = elastic_strain
index_i = 2
index_j = 2
[]
[clad_hoop_total_strain]
type = RankTwoAux
block = clad
variable = clad_hoop_total_strain
rank_two_tensor = total_strain
index_i = 2
index_j = 2
[]
[local_power]
type = FunctionAux
block = 'pellet blanket'
variable = local_power
function = lhr_peaking_factor_function
[]
[T_coolant]
type = MaterialRealAux
variable = T_coolant
property = coolant_temperature
boundary = clad_outside_right
[]
[pin_lhr]
type = FunctionAux
block = 'pellet blanket'
variable = pin_lhr
function = pin_lhr_function
[]
[eutectic_thickness]
type = DiffusionalEutecticThicknessFCCI
block = clad
variable = eutectic_thickness
temperature = T
boundary = clad_inside_right
execute_on = TIMESTEP_END
[]
[]
[Contact]
# Assessment uses frictionless contact. See [Greenquist et al., 2021] for
# a study comparing the various contact models.
[frictionless_fuel_clad_mechanical]
primary = clad_inside_right
secondary = pellet_outer_radial_surface
model = frictionless
formulation = kinematic
tangential_tolerance = 1e-3
normal_smoothing_distance = 0.1
[]
[]
[ThermalContact]
[thermal_contact]
type = GapHeatTransfer
variable = T
primary = clad_inside_right
secondary = pellet_outer_radial_surface
gap_geometry_type = CYLINDER
gap_conductivity_function = sodium_conductivity_function
gap_conductivity_function_variable = T
quadrature = true
min_gap = 0.00038 # Set to the initial gap width.
tangential_tolerance = 1e-4
[]
[]
[BCs]
[fix_disp_x_all]
type = DirichletBC
variable = disp_x
value = 0.0
boundary = centerline
[]
[fix_disp_y_all]
type = DirichletBC
variable = disp_y
value = 0.0
boundary = 'clad_outside_bottom bottom_of_bottom_pellet'
[]
[Pressure]
[coolant_pressure]
function = coolant_pressure_function
boundary = 'clad_outside_bottom clad_outside_right clad_outside_top'
[]
[]
[PlenumPressure]
[plenum_pressure]
boundary = 'clad_inside_bottom clad_inside_right clad_inside_top'
startup_time = 0
initial_pressure = 101325 # 1 atm [Greenquist et al., 2021]
volume = gas_volume
material_input = fission_gas_released
R = 8.3143
temperature = plenum_temperature
output = plenum_pressure
[]
[]
[]
[PlenumTemperature]
[plenum_temperature]
temperature = T
boundary = 'bottom_of_bottom_pellet pellet_outer_radial_surface
top_of_top_pellet clad_inside_bottom clad_inside_right
clad_inside_top'
inner_surfaces = 'bottom_of_bottom_pellet pellet_outer_radial_surface
top_of_top_pellet'
outer_surfaces = 'clad_inside_bottom clad_inside_right clad_inside_top'
[]
[]
[CoolantChannel]
[convective_clad_surface]
variable = T
inlet_temperature = coolant_T_in_function
inlet_pressure = coolant_pressure_function
inlet_massflux = coolant_flux_function
coolant_material = sodium
rod_diameter = 0.00686 # [Dodds, 1986-2]
rod_pitch = 0.00823 # [Greenquist et al., 2021]
linear_heat_rate = assembly_lhr_avg_function
axial_power_profile = lhr_peaking_factor_function
subchannel_geometry = triangular
boundary = 'clad_outside_bottom clad_outside_right clad_outside_top'
[]
[]
[Materials]
###### FUEL ######
[fuel_fission_rate]
type = UPuZrFissionRate
block = pellet
rod_linear_power = assembly_lhr_avg_function
axial_power_profile = lhr_peaking_factor_function
pellet_radius = 0.00249 # [Dodds, 1986-2]
initial_X_Zr = 0.224 # [Dodds, 1986-2]
X_Zr = 0.224
outputs = exodus
output_properties = fission_rate
[]
[fuel_burnup]
type = UPuZrBurnup
block = pellet
density = ${initial_fuel_density} # [Dodds, 1986-2]
initial_X_Pu = ${initial_X_Pu} # [Dodds, 1986-2]
initial_X_Zr = 0.224 # [Dodds, 1986-2]
outputs = exodus
output_properties = burnup
[]
[fuel_density]
type = StrainAdjustedDensity
block = pellet
strain_free_density = ${initial_fuel_density} # [Dodds, 1986-2]
[]
[fuel_sodium_logging]
type = UPuZrSodiumLogging
block = pellet
porosity = porosity
sodium_infiltration_fraction = ${Na_infiltration_fraction} # [Bauer and Holland, 1995]
outputs = exodus
output_properties = sodium_logged_porosity
[]
[fuel_thermal_properties]
type = UPuZrThermal
block = pellet
X_Pu = ${initial_X_Pu} # [Dodds, 1986-2]
X_Zr = 0.224 # [Dodds, 1986-2]
spheat_model = savage
thcond_model = lanl
porosity_model = logged
porosity = porosity
sodium_logged_porosity = sodium_logged_porosity
[]
[fuel_elasticity_tensor]
type = UPuZrElasticityTensor
block = pellet
X_Pu = ${initial_X_Pu} # [Dodds, 1986-2]
X_Zr = 0.224 # [Dodds, 1986-2]
porosity = porosity
[]
[fuel_creep]
type = UPuZrCreepUpdate
block = pellet
porosity = porosity
max_inelastic_increment = 3e-3
effective_inelastic_strain_name = fuel_effective_creep_strain
[]
[fuel_gaseous_swelling]
type = UPuZrGaseousEigenstrain
block = pellet
fission_rate = fission_rate
anisotropic_factor = 0.5 # [Pahl et al., 1990]
bubble_number_density = 5e17 # [Casagranda et al., 2020]
interconnection_initiating_porosity = ${interconnection_init_porosity} # [Casagranda et al., 2020]
interconnection_terminating_porosity = ${interconnection_term_porosity} # [Casagranda et al., 2020]
eigenstrain_name = fuel_gaseous_strain
outputs = exodus
output_properties = 'gas_swelling porosity interconnectivity'
[]
[fuel_solid_swelling]
type = BurnupDependentEigenstrain
block = pellet
eigenstrain_name = fuel_solid_strain
swelling_name = solid_swelling
outputs = exodus
output_properties = solid_swelling
swelling_factor = 0 # Solid swelling is negligible below 10% burnup
[]
[fuel_fission_gas_release]
type = UPuZrFissionGasRelease
block = pellet
fission_rate = fission_rate
porosity = porosity
critical_porosity = ${critical_porosity} # [Casagranda et al., 2020]
fractional_fgr_initial = ${fgr_init} # [Casagranda et al., 2020]
fractional_fgr_post = ${fgr_post} # [Casagranda et al., 2020]
[]
[fuel_thermal_expansion]
type = UPuZrThermalExpansionEigenstrain
block = pellet
stress_free_temperature = 298
eigenstrain_name = fuel_thermal_strain
[]
[fuel_elastic_stress]
type = ComputeMultipleInelasticStress
block = pellet
inelastic_models = fuel_creep
[]
###### BLANKET ######
[blanket_fission_rate]
type = UPuZrFissionRate
block = blanket
rod_linear_power = assembly_lhr_avg_function
axial_power_profile = lhr_peaking_factor_function
pellet_radius = 0.00249
initial_X_Zr = 0.224 # 10 wt% [Dodds, 1986-2]
X_Zr = 0.224
outputs = exodus
output_properties = fission_rate
[]
[blanket_burnup]
type = UPuZrBurnup
block = blanket
density = 15800 # [Dodds, 1986-2]
initial_X_Pu = 0 # [Dodds, 1986-2]
initial_X_Zr = 0.224 # [Dodds, 1986-2]
outputs = exodus
output_properties = burnup
[]
[blanket_density]
type = StrainAdjustedDensity
block = blanket
strain_free_density = 15800 # [Dodds, 1986-2]
[]
[blanket_sodium_logging]
type = UPuZrSodiumLogging
block = blanket
porosity = porosity
sodium_infiltration_fraction = 0.08 # [Bauer and Holland, 1995]
outputs = exodus
output_properties = sodium_logged_porosity
[]
[blanket_thermal_properties]
type = UPuZrThermal
block = blanket
X_Pu = 0 # [Dodds, 1986-2]
X_Zr = 0.224 # [Dodds, 1986-2]
spheat_model = savage
thcond_model = lanl
porosity_model = logged
porosity = porosity
sodium_logged_porosity = sodium_logged_porosity
[]
[blanket_elasticity_tensor]
type = UPuZrElasticityTensor
block = blanket
X_Pu = 0 # [Dodds, 1986-2]
X_Zr = 0.224 # [Dodds, 1986-2]
porosity = porosity
[]
[blanket_creep]
type = UPuZrCreepUpdate
block = blanket
porosity = porosity
max_inelastic_increment = 3e-3
effective_inelastic_strain_name = blanket_effective_creep_strain
[]
[blanket_gaseous_swelling]
type = UPuZrGaseousEigenstrain
block = blanket
fission_rate = fission_rate
anisotropic_factor = 0.5 # [Pahl et al., 1990]
bubble_number_density = 5e17 # [Casagranda et al., 2020]
interconnection_initiating_porosity = 0.25 # [Casagranda et al., 2020]
interconnection_terminating_porosity = 0.27 # [Casagranda et al., 2020]
eigenstrain_name = fuel_gaseous_strain
outputs = exodus
output_properties = 'gas_swelling porosity interconnectivity'
[]
[blanket_solid_swelling]
type = BurnupDependentEigenstrain
block = blanket
eigenstrain_name = fuel_solid_strain
swelling_name = solid_swelling
outputs = exodus
output_properties = solid_swelling
swelling_factor = 0 # Solid swelling is negligible below 10% burnup
[]
[blanket_fission_gas_release]
type = UPuZrFissionGasRelease
block = blanket
fission_rate = fission_rate
porosity = porosity
critical_porosity = 0.26 # [Casagranda et al., 2020]
fractional_fgr_initial = 0.454 # [Casagranda et al., 2020]
fractional_fgr_post = 0.714 # [Casagranda et al., 2020]
[]
[blanket_thermal_expansion]
type = UPuZrThermalExpansionEigenstrain
block = blanket
stress_free_temperature = 298
eigenstrain_name = fuel_thermal_strain
[]
[blanket_elastic_stress]
type = ComputeMultipleInelasticStress
block = blanket
inelastic_models = blanket_creep
[]
###### CLADDING ######
[fast_neutron_flux]
type = UPuZrFastNeutronFlux
pellet_radius = 0.00249
axial_power_profile = lhr_peaking_factor_function
rod_linear_power = assembly_lhr_avg_function
initial_density = 15800 # [Dodds, 1986-2]
initial_X_Pu = ${initial_X_Pu} # [Dodds, 1986-2]
initial_X_Zr = 0.224 # [Dodds, 1986-2]
enrichment_U235 = ${enrichment_U235} # [Dodds, 1986-2]
enrichment_Pu240 = 0.061 # [Dodds, 1986-2]
calculate_fluence = true
outputs = exodus
[]
[clad_density]
type = StrainAdjustedDensity
block = clad
strain_free_density = 7761 # [Hofman et al., 1989]
[]
[clad_thermal_properties]
type = D9Thermal
block = clad
[]
[clad_gaseous_swelling]
type = D9VolumetricSwellingEigenstrain
block = clad
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
eigenstrain_name = clad_gaseous_strain
[]
[clad_thermal_expansion]
type = D9ThermalExpansionEigenstrain
block = clad
eigenstrain_name = clad_thermal_strain
stress_free_temperature = 298
[]
[clad_elasticity_tensor]
type = D9ElasticityTensor
block = clad
[]
[clad_creep]
type = D9CreepUpdate
block = clad
max_inelastic_increment = 3e-3 # 1e-2
effective_inelastic_strain_name = clad_effective_creep_strain
[]
[clad_failure]
type = D9FailureClad
method = steady_state
hoop_stress = stress_zz
boundary = clad_outside_right
outputs = exodus
output_properties = cdf_failure
[]
[inner_clad_wastage]
type = MetallicFuelWastage
block = clad
method = flux_d9
burnup = 0 # not used but must be specified
outputs = exodus
output_properties = wastage_thickness
[]
[outer_clad_wastage]
type = MetallicFuelCoolantWastage
block = clad
clad_material = SS316 # does not have D9
use_effective_method = true
outputs = exodus
[]
[clad_wastage_fraction]
type = MetallicFuelWastageDamage
block = clad
wastage_thickness = wastage_thickness
pellet_length = 0.9144
pellet_y_start = 0.1812
cladding_thickness = 0.00056
outputs = exodus
[]
[clad_damage_fraction]
type = ScalarMaterialDamage
block = clad
damage_index = thinning_fraction
outputs = exodus
[]
[clad_elastic_stress]
type = ComputeMultipleInelasticStress
block = clad
inelastic_models = clad_creep
[]
[]
[Dampers]
[T_damper]
type = MaxIncrement
variable = T
max_increment = 25
[]
[disp_x_damper]
type = MaxIncrement
variable = disp_x
max_increment = 3.00E-04
[]
[disp_y_damper]
type = MaxIncrement
variable = disp_y
max_increment = 3.00E-04
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
solve_type = PJFNK
automatic_scaling = true
compute_scaling_once = false
petsc_options = '-snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package
-ksp_gmres_restart'
petsc_options_value = 'lu superlu_dist
51'
line_search = NONE
l_max_its = 30
l_tol = 1e-3
nl_max_its = 30
nl_rel_tol = 1e-4
nl_abs_tol = 5e-7
start_time = 0
end_time = 53791920
dtmin = 1e-2
dtmax = 1e6
verbose = true
[Quadrature]
order = FIFTH
side_order = SEVENTH
[]
[TimeStepper]
type = IterationAdaptiveDT
dt = 100
optimal_iterations = 10
iteration_window = 4
growth_factor = 1.25
cutback_factor = 0.512
linear_iteration_ratio = 100
force_step_every_function_point = true
timestep_limiting_function = assembly_lhr_avg_function
timestep_limiting_postprocessor = creep_timestep_min
[]
[]
[Postprocessors]
###### POWER ######
[fission_rate_density_avg]
type = ElementAverageValue
block = 'pellet blanket'
variable = fission_rate
outputs = csv
[]
[fast_neutron_fluence_avg]
type = ElementAverageValue
variable = fast_neutron_fluence
outputs = 'csv chkfile'
[]
[fast_neutron_fluence_max]
type = ElementExtremeValue
variable = fast_neutron_fluence
value_type = max
outputs = 'csv chkfile'
[]
[pin_hr_tot]
type = ElementIntegralPower
block = 'pellet blanket'
variable = T # required but not actually used
use_material_fission_rate = true
fission_rate_material = fission_rate
outputs = csv
[]
[pin_lhr_avg]
type = FunctionValuePostprocessor
function = assembly_lhr_avg_function
outputs = csv
[]
###### HEAT TRANSFER ######
[radial_heat_flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = T
boundary = pellet_outer_radial_surface
diffusivity = thermal_conductivity
outputs = csv
[]
[radial_heat_flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = T
boundary = clad_outside_right
diffusivity = thermal_conductivity
outputs = csv
[]
###### FISSION GAS ###### (needed for simulation to run)
[fission_gas_produced]
type = ElementIntegralMaterialProperty
mat_prop = fis_gas_prod
block = 'pellet blanket'
outputs = 'csv chkfile'
[]
[fission_gas_released]
type = ElementIntegralMaterialProperty
mat_prop = fis_gas_rel
block = 'pellet blanket'
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[fission_gas_released_pct]
type = FGRPercent
fission_gas_generated = fission_gas_produced
fission_gas_released = fission_gas_released
outputs = 'console csv chkfile'
[]
[clad_internal_volume]
type = InternalVolume
boundary = 'clad_inside_bottom clad_inside_right clad_inside_top'
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[fuel_volume]
type = InternalVolume
boundary = 'bottom_of_bottom_pellet pellet_outer_radial_surface
top_of_top_pellet'
scale_factor = -1 # makes the fuel volume positive
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[sodium_volume]
type = FunctionValuePostprocessor
function = sodium_volume_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[gas_volume]
type = FunctionValuePostprocessor
function = gas_volume_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[plenum_compressibility]
type = FunctionValuePostprocessor
function = plenum_compressibility_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[compressibility_times_temperature]
type = FunctionValuePostprocessor
function = compressibility_times_temperature_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
###### BURNUP ######
[burnup_max]
type = ElementExtremeValue
block = pellet
variable = burnup
value_type = max
outputs = csv
[]
[burnup_max_pct]
type = LinearCombinationPostprocessor
pp_names = burnup_max
pp_coefs = 100
outputs = 'csv chkfile'
[]
[burnup_avg]
type = ElementAverageValue
block = pellet
variable = burnup
outputs = csv
[]
[burnup_avg_pct]
type = LinearCombinationPostprocessor
pp_names = burnup_avg
pp_coefs = 100
outputs = 'console csv chkfile'
[]
###### FUEL TEMPERATURE ######
[fuel_T_max]
type = ElementExtremeValue
block = pellet
variable = T
value_type = max
outputs = csv
[]
[fuel_T_max_peak]
type = TimeExtremeValue
postprocessor = fuel_T_max
value_type = max
outputs = 'csv chkfile'
[]
[fuel_T_surface_max]
type = NodalExtremeValue
boundary = pellet_outer_radial_surface
variable = T
value_type = max
outputs = csv
[]
[fuel_T_surface_max_peak]
type = TimeExtremeValue
postprocessor = fuel_T_surface_max
value_type = max
outputs = 'csv chkfile'
[]
###### CLADDING TEMPERATURE ######
[clad_T_max]
type = ElementExtremeValue
block = clad
variable = T
value_type = max
outputs = csv
[]
[clad_T_max_peak]
type = TimeExtremeValue
postprocessor = clad_T_max
value_type = max
outputs = csv
[]
[clad_T_inner_surface_max]
type = NodalExtremeValue
boundary = clad_inside_right
variable = T
value_type = max
outputs = csv
[]
[clad_T_inner_surface_max_peak]
type = TimeExtremeValue
postprocessor = clad_T_inner_surface_max
value_type = max
outputs = 'csv chkfile'
[]
[clad_T_outer_surface_max]
type = NodalExtremeValue
boundary = clad_outside_right
variable = T
value_type = max
outputs = csv
[]
[clad_T_outer_surface_max_peak]
type = TimeExtremeValue
postprocessor = clad_T_outer_surface_max
value_type = max
outputs = 'csv chkfile'
[]
###### COOLANT PARAMETERS ######
[T_coolant_in]
type = FunctionValuePostprocessor
function = coolant_T_in_function
outputs = csv
[]
[T_coolant_out]
type = ElementExtremeValue
block = clad
variable = T_coolant
value_type = max
outputs = csv
[]
[coolant_flux]
type = FunctionValuePostprocessor
function = coolant_flux_function
outputs = csv
[]
###### FUEL DEFORMATION ######
[fuel_axial_elongation_min]
type = NodalExtremeValue
block = pellet
variable = disp_y
value_type = min
outputs = csv
[]
[fuel_axial_elongation_max]
type = NodalExtremeValue
block = pellet
variable = disp_y
value_type = max
outputs = csv
[]
[fuel_axial_elongation_max_pct]
type = FunctionValuePostprocessor
function = fuel_axial_elongation_max_pct_function
outputs = 'console csv chkfile'
[]
[fuel_radial_dilation_max]
type = NodalExtremeValue
variable = disp_x
boundary = pellet_outer_radial_surface
value_type = max
outputs = csv
[]
[fuel_radial_dilation_max_pct]
type = FunctionValuePostprocessor
function = fuel_radial_dilation_max_pct_function
outputs = csv
[]
###### CLADDING DEFORMATION ######
[clad_axial_elongation_max]
type = NodalExtremeValue
block = clad
variable = disp_y
value_type = max
outputs = csv
[]
[clad_axial_elongation_max_pct]
type = FunctionValuePostprocessor
function = clad_axial_elongation_max_pct_function
outputs = 'csv chkfile'
[]
[clad_radial_dilation_max]
type = NodalExtremeValue
variable = disp_x
boundary = clad_outside_right
value_type = max
outputs = csv
[]
[clad_radial_dilation_max_pct]
type = FunctionValuePostprocessor
function = clad_radial_dilation_max_pct_function
outputs = 'console csv chkfile'
[]
###### GAP DEFORMATION AND MECHANICS ######
[gap_width_min]
type = NodalExtremeValue
variable = fuel_clad_gap_width
boundary = pellet_outer_radial_surface
value_type = min
outputs = csv
[]
[gap_width_max]
type = NodalExtremeValue
variable = fuel_clad_gap_width
boundary = pellet_outer_radial_surface
value_type = max
outputs = csv
[]
[gap_width_avg]
type = SideAverageValue
variable = fuel_clad_gap_width
boundary = pellet_outer_radial_surface
outputs = csv
[]
[contact_pressure_max]
type = NodalExtremeValue
variable = contact_pressure
boundary = pellet_outer_radial_surface
value_type = max
outputs = csv
[]
###### FUEL MECHANICS ######
[fuel_hydrostatic_stress_min]
type = ElementExtremeValue
block = 'pellet blanket'
variable = hydrostatic_stress
value_type = min
outputs = csv
[]
[fuel_hydrostatic_stress_max]
type = ElementExtremeValue
block = 'pellet blanket'
variable = hydrostatic_stress
value_type = max
outputs = csv
[]
[fuel_hydrostatic_stress_avg]
type = ElementAverageValue
block = 'pellet blanket'
variable = hydrostatic_stress
outputs = csv
[]
[fuel_volumetric_strain_avg]
type = ElementAverageValue
block = 'pellet blanket'
variable = fuel_volumetric_strain
outputs = 'csv chkfile'
[]
###### CLADDING MECHANICS ######
[clad_hoop_stress_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_stress
value_type = max
outputs = csv
[]
[clad_hoop_creep_strain_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_creep_strain
value_type = max
outputs = 'csv chkfile'
[]
[clad_hoop_elastic_strain_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_elastic_strain
value_type = max
outputs = 'csv chkfile'
[]
[clad_hoop_total_strain_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_total_strain
value_type = max
outputs = 'csv chkfile'
[]
[cdf_max]
type = ElementExtremeValue
variable = cdf_failure
value_type = max
outputs = 'console csv'
[]
###### PERFORMANCE ######
[creep_timestep_fuel]
type = MaterialTimeStepPostprocessor
block = pellet
outputs = csv
[]
[creep_timestep_blanket]
type = MaterialTimeStepPostprocessor
block = blanket
outputs = csv
[]
[creep_timestep_clad]
type = MaterialTimeStepPostprocessor
block = clad
outputs = csv
[]
[creep_timestep_min]
type = FunctionValuePostprocessor
function = creep_timestep_min_function
outputs = csv
[]
###### SWELLING ######
[solid_swelling_avg]
type = ElementAverageValue
block = pellet
variable = solid_swelling
outputs = 'csv chkfile'
[]
[gas_swelling_avg]
type = ElementAverageValue
block = pellet
variable = gas_swelling
outputs = 'csv chkfile'
[]
[porosity_avg]
type = ElementAverageValue
block = pellet
variable = porosity
outputs = 'csv chkfile'
[]
[sodium_logged_porosity_avg]
type = ElementAverageValue
block = pellet
variable = sodium_logged_porosity
outputs = 'csv chkfile'
[]
###### CLADDING WASTAGE ######
[wastage_max]
type = ElementExtremeValue
block = clad
variable = wastage_thickness
value_type = max
outputs = 'csv chkfile'
[]
[wastage_min]
type = ElementExtremeValue
block = clad
variable = wastage_thickness
value_type = min
outputs = csv
[]
[wastage_avg]
type = ElementAverageValue
block = clad
variable = wastage_thickness
outputs = csv
[]
[eutectic_max]
type = ElementExtremeValue
block = clad
variable = eutectic_thickness
value_type = max
outputs = csv
[]
[eutectic_min]
type = ElementExtremeValue
block = clad
variable = eutectic_thickness
value_type = min
outputs = csv
[]
[eutectic_avg]
type = ElementAverageValue
block = clad
variable = eutectic_thickness
outputs = csv
[]
[]
[VectorPostprocessors]
[fuel_centerline]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = centerline
sort_by = y
outputs = csv
[]
[fuel_surface]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = pellet_outer_radial_surface
sort_by = y
outputs = csv
[]
[clad_inner_surface]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = clad_inside_right
sort_by = y
outputs = csv
[]
[clad_outer_surface]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = clad_outside_right
sort_by = y
outputs = csv
[]
[]
[PerformanceMetricOutputs]
outputs = 'csv performance'
[]
[Outputs]
color = true
perf_graph = true
file_base = '${composition}'
[console]
type = Console
output_screen = true
[]
[exodus]
type = Exodus
execute_on = 'INITIAL TIMESTEP_END FINAL'
time_step_interval = 50
file_base = '${composition}_exodus'
[]
[csv]
type = CSV
execute_postprocessors_on = 'INITIAL TIMESTEP_END'
execute_vector_postprocessors_on = FINAL
file_base = '${composition}_csv'
[]
[chkfile]
type = CSV
execute_postprocessors_on = FINAL
file_base = '${composition}_chkfile'
[]
[performance]
type = CSV
hide = 'plenum_pressure plenum_temperature'
execute_postprocessors_on = FINAL
file_base = '${composition}_performance'
[]
[]
# REFERENCES
# [Bauer and Holland, 1995]
# T.H. Bauer, J.W. Holland "In-Pile Measurement of the Thermal Conductivity
# of Irradiated Metallic Fuel" Nuclear Technology Vol 110 Issue 3, 407-421,
# (1995)
# [Cabell, 1980]
# C.P. Cabell "A Summary Description of the Fast Flux Test Facility"
# Westinghouse Hanford Company HEDL-400, Hanford, Washington (1980)
# [Casagranda et al., 2020]
# A. Casagranda, S. Novascone, L. Aagesen, W. Jiang, J.H. Ke, D. Stafford,
# C. Matthews, A. Toptan, K. Gamble, J. Hales, "Summary of BISON Milestones:
# NEAMS FY-20 Report" Idaho National Laboratory INL/EXT-20-60002-Rev000,
# 1768565, Idaho Falls, Idaho (2020)
# [Dodds, 1986-1]
# N.E. Dodds, "Test design description. Volumne 1B. IFR-1 metal fuel
# irradiation (AK-181)" Argonne National Laboratory ANL-iFR-43, Argonne,
# Illinois, (1986)
# [Dodds, 1986-2]
# N.E. Dodds, "Test design description Volume 2, Part 1. IFR-1 metal fuel
# irradiation test (AK-181) element as-built data" Argonne National
# Laboratory ANL-IFR-44, Argonne, Illinois (1986)
# [Fink and Leibowitz, 1995]
# J. K. Fink and L. Leibowitz, "Thermodynamic and transport properties of
# sodium liquid and vapor", Argonne National Laboratory ANL/RE--95/2, 94649,
# Argonne, Illinois (1995)
# [Greenquist et al., 2021]
# I. Greenquist, K.M. Cunningham, J. Hu, J.J. Powers, D.C. Crawford,
# "Development of a U-19Pu-10Zr fuel performance benchmark case based on the
# IFR-1 experiment" Journal of Nuclear Materials Vol. 553, 152997 (2021)
# [Hirschhorn and Powers, 2021]
# J. Hirschhorn, J. Powers "Assessment of the BISON Metallic Fuel
# Performance Models", Oak Ridge National Laboratory ORNLTM-2020/1824,
# 1763469, Oak Ridge, Tennessee (2021)
# [Hobbs and Charboneau, 2020]
# I.M. Hobbs, J.A. Charboneau "Compressibility of gas mixtures pertaining to
# nuclear fuel rods" Journal of Physics Comminications Vol. 4, Iss. 9,
# 095008 (2020)
# [Hofman et al., 1989]
# G. L. Hofman, M. C. Billone, J. F. Koenig, J. M. Kramer, J. D. B. Lambert,
# L. Leibowitz, Y. Orechwa, D. R. Pedersen, D. L. Porter, H. Tsai, A. E.
# Wright, "Metallic Fuels Handbook", Argonne National Laboratory ANL-NSE-3,
# Argonne, Illinois (1989)
# [Janney, 2018]
# Dawn E. Janney, "Metallic Fuels Handbook, Part 1: Alloys Based on U-Zr,
# Pu-Zr, U-Pu, or U-Pu-Zr, Including Those with Minor Actinides (Np, Am,
# Cm), Rare-earth Elements (La, Ce, Pr, Nd, Gd), and Y", Idaho National
# Laboratory INL/EXT-15-36520, Idaho Falls, Idaho (2018)
# [Pahl et al., 1990]
# R.G. Pahl, D.L. Porter, C.E. Lahm, G.L. Hofman "Experimental studies of
# U-Pu-Zr fast reactor fuel pins in the Experimental Breeder Reactor-II"
# Metallurgic Transactions A Vol 21A, 1863-1870, (1990)
# [Porter and Tsai, 2011]
# D. L. Porter and H. Tsai, "Full-Length Metallic Fast Reactor Fuel Pin Test
# in FFTF (IFR-1)"", Idaho National Laboratory INL/LTD-11-21062, Idaho
# Falls, Idaho (2011)
# [Shultis and Faw, 2008]
# J.K. Shultis, R.E. Faw "Fundamentals of Nuclear Science and Engineering
# Second Edition" CRC Press, Boca Raton, Florida (2008)
# [Tsai et al., 1986]
# H. Tsai, L.A. Neimark, M.C. Billone, R.M. Fryer, J.F. Koenig, W.K. Lehto,
# D.J. Malloy, "Test Design Description (TDD). Volume 1A. Design description
# and safety analysis for IFR-1 metal fuels irradiation test in FFTF"
# Argonne National Laboratory ANL-IFR-33, Argonne, Illinois (1986)
(assessment/metallic_fuel/EBRII/X430/analysis/template.i)
# TEMPLATE FILE
# This is not an input file. It is a template used to populate the input files.
# Changes made to this file will be applied to all 25 X430 input files.
# Values used for individual pins are stored in pin_inputs.csv. Input files are
# generated using the Python script generate_input_files.py.
# X430 ASSESSMENT CASE
# BISON recreation of the 52-pin X430 experiment series, which was irradiated in
# EBR-II from 1987-88 to a peak burnup of about 10 at%. The subassembly
# contained 37 pins and was irradiated in three experiments: X430, X430A, and
# X430B. After each experiment, pins were removed, examined, replaced as
# necessary, and the subassembly was reconstructed. BISON simulations were
# developed for 25 of the pins, of which 2 are
# assessments. Legacy calculations and PIE measurements are available for all 25
# pins. Units are in standard SI: J, K, kg, m, Pa, s.
# For a more complete description of the experiments, see [Hayes et al., 1994].
# For a more complete description of the development and results of this
# assessment, see [Greenquist and Powers, 2021].
# This file simulates pin %{pin} with a composition of %{composition}.
[GlobalParams]
dim = 2
order = SECOND
family = LAGRANGE
elem_type = QUAD8
energy_per_fission = 3.2e-11 # [Shultis and Faw, 2008]
volumetric_locking_correction = false
displacements = 'disp_x disp_y'
temperature = T
[]
[Problem]
type = ReferenceResidualProblem
reference_vector = ref
extra_tag_vectors = ref
[]
[Mesh]
coord_type = RZ
# Mesh includes a fuel slug and cladding. All dimensions are in meters. See
# [Hayes et al., 1994] and [Greenquist and Powers, 2021] for more complete
# descriptions.
type = MeshGeneratorMesh
patch_size = 30
patch_update_strategy = auto
partitioner = centroid
centroid_partitioner_direction = y
# build cladding
[bottom_plug]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.0032786
nx = 5
ymin = 0.0
ymax = 0.015
ny = 4
[]
[bottom_corner]
type = GeneratedMeshGenerator
xmin = 0.0032786
xmax = 0.003685
nx = 8
ymin = 0.0
ymax = 0.015
ny = 4
[]
[bottom_corner_rename_side]
type = SideSetsFromNormalsGenerator
input = bottom_corner
normals = '0 1 0'
new_boundary = new_side
[]
[combine_bottom_and_bottom_corner]
type = StitchedMeshGenerator
inputs = 'bottom_plug bottom_corner_rename_side'
stitch_boundaries_pairs = 'right left'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[cladding_wall]
type = GeneratedMeshGenerator
xmin = 0.0032786
xmax = 0.003685
nx = 8
ymin = 0.015
ymax = 0.72565
ny = 120
[]
[cladding_wall_rename_side]
type = SideSetsFromNormalsGenerator
input = cladding_wall
normals = '0 1 0'
new_boundary = new_side
[]
[combine_bottom_and_wall]
type = StitchedMeshGenerator
inputs = 'combine_bottom_and_bottom_corner cladding_wall_rename_side'
stitch_boundaries_pairs = '4 bottom'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[top_corner]
type = GeneratedMeshGenerator
xmin = 0.0032786
xmax = 0.003685
nx = 8
ymin = 0.72565
ymax = 0.74065
ny = 4
[]
[top_corner_rename_side]
type = SideSetsFromNormalsGenerator
input = top_corner
normals = '-1 0 0'
new_boundary = new_side
[]
[combine_wall_and_top_corner]
type = StitchedMeshGenerator
inputs = 'combine_bottom_and_wall top_corner_rename_side'
stitch_boundaries_pairs = '4 bottom'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
[top_plug]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = 0.0032786
nx = 5
ymin = 0.72565
ymax = 0.74065
ny = 4
[]
[cladding_all]
type = StitchedMeshGenerator
inputs = 'combine_wall_and_top_corner top_plug'
stitch_boundaries_pairs = '4 right'
clear_stitched_boundary_ids = true
prevent_boundary_ids_overlap = false
[]
# build fuel
[fuel_slug]
type = GeneratedMeshGenerator
xmin = 0.0
xmax = %{fuel_r}
nx = 5
ymin = 0.019
ymax = %{fuel_top}
ny = 250
[]
# combine and name subdomains
[combine_fuel_cladding]
type = CombinerGenerator
inputs = 'cladding_all fuel_slug'
[]
[name_cladding]
type = SubdomainBoundingBoxGenerator
input = combine_fuel_cladding
bottom_left = '0.0 0.0 0.0'
top_right = '0.003685 0.74065 0.0'
location = INSIDE
block_id = 0
block_name = clad
[]
[name_fuel]
type = SubdomainBoundingBoxGenerator
input = name_cladding
bottom_left = '0.0 0.019 0.0'
top_right = '%{fuel_r} %{fuel_top} 0.0'
location = INSIDE
block_id = 1
block_name = pellet
[]
# name boundaries
[name_centerline]
type = SideSetsFromNormalsGenerator
input = name_fuel
normals = '-1 0 0'
new_boundary = centerline
replace = true
[]
[name_slug_outer_surface]
type = SideSetsFromNormalsGenerator
input = name_centerline
normals = '1 0 0'
new_boundary = pellet_outer_radial_surface
replace = true
[]
[name_slug_ends]
type = SideSetsFromPointsGenerator
input = name_slug_outer_surface
points = '0.50e-3 0.019 0.0
0.50e-3 %{fuel_top} 0.0'
new_boundary = 'bottom_of_bottom_pellet top_of_top_pellet'
replace = true
[]
[name_cladding_inside]
type = SideSetsFromPointsGenerator
input = name_slug_ends
points = '0.50e-3 0.015 0.0
0.0032786 0.36 0.0
0.50e-3 0.72565 0.0'
new_boundary = 'clad_inside_bottom clad_inside_right clad_inside_top'
replace = true
[]
[name_cladding_outer_surface]
type = SideSetsFromPointsGenerator
input = name_cladding_inside
points = '0.003685 0.36 0.0
0.50e-3 0.0 0.0
0.50e-3 0.74065 0.0'
new_boundary = 'clad_outside_right clad_outside_bottom clad_outside_top'
replace = true
[]
[]
[Variables]
[T]
initial_condition = 298
[]
[]
[AuxVariables]
[gap_conductance]
order = CONSTANT
family = MONOMIAL
[]
[fuel_clad_gap_width]
order = FIRST
family = LAGRANGE
[]
[element_failed]
order = CONSTANT
family = MONOMIAL
[]
[fuel_volumetric_strain]
block = pellet
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_stress]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_creep_strain]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_elastic_strain]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[clad_hoop_total_strain]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[local_power]
block = pellet
order = CONSTANT
family = MONOMIAL
[]
[T_coolant]
order = CONSTANT
family = MONOMIAL
[]
[pin_lhr]
block = pellet
order = CONSTANT
family = MONOMIAL
[]
[eutectic_thickness]
block = clad
order = CONSTANT
family = MONOMIAL
[]
[]
[Functions]
[assembly_lhr_avg_function]
# Subassembly average LHR as a function of time. x: time (s), y: average
# LHGR (W/m). See [Greenquist and Powers, 2021].
type = PiecewiseLinear
x = ' 0 3600 8203212 8206812 13814423 13818023 14428975 14432575
21312419 21316019 25596874 25600474 26261755 26265355 32714598 32718198
32721798 32725398 32728998 32896765 32900365 39574695 39578295 42194062
42197662 43820808 43824408 43895709 43899309 44401212 44404812 47385472
47389072 48198548 48202148 48205748 48209348 48212948 52079977 52083577
53874489 53878089 62125235 62128835 62256058 62259658 62620357 62623957
64516928 64520528 64766586 64770186 67535546 67539146 72155534 72159134
72185697 72189297 76833647 76837247 77340548 77344148 77738400 77742000
80444447 80448047 80451647 80455247'
y = ' 0.0 44225.3 44225.3 43106.1 43106.1 41403.6 41403.6 41119.9
41119.9 38881.4 38881.4 38353.3 38353.3 39472.5 39472.5 0.0
0.0 0.0 33490.2 33490.2 36863.6 36863.6 37123.7 37123.7
32717.8 32717.8 38534.6 38534.6 38432.1 38432.1 36784.8 36784.8
36036.0 36036.0 0.0 0.0 0.0 35153.3 35153.3 35153.3
35153.3 35271.5 35271.5 33663.6 33663.6 34459.7 34459.7 34640.9
34640.9 34428.1 34428.1 34026.2 34026.2 33624.2 33624.2 33624.2
33624.2 33718.8 33718.8 34057.7 34057.7 34057.7 34057.7 34215.3
34215.3 0.0 0.0 0.0'
[]
[radial_peaking_factor_function]
# Adjusts the pin's average LHR based on its location in the subassembly.
# x: time [s], y: relative LHR change. See [Greenquist and Powers, 2021].
type = PiecewiseLinear
x = ' 0 32718198
32725398 48202148
48209348 80455247'
y = '%{rad_LHR_X430} %{rad_LHR_X430}
%{rad_LHR_X430a} %{rad_LHR_X430a}
%{rad_LHR_X430b} %{rad_LHR_X430b}'
[]
[lhr_peaking_factor_function]
# Axial variation from the average LHR. x: axial position (m), y: time (s),
# z: peaking factor. See [Hayes et al., 1994] and
# [Greenquist and Powers, 2021].
#
type = PiecewiseBilinear
xaxis = 1
yaxis = 0
y = '0 32725398 48209348 80455247'
x = '0.018 0.019 %{z01} %{z02} %{z03} %{z04}
%{z05} %{z06} %{z07} %{z08} %{z09}
%{fuel_top} %{z11}'
z = '0.0000 %{pX430_00} %{pX430_01} %{pX430_02} %{pX430_03} %{pX430_04}
%{pX430_05} %{pX430_06} %{pX430_07} %{pX430_08} %{pX430_09}
%{pX430_10} 0.0000
0.0000 %{pX430a_00} %{pX430a_01} %{pX430a_02} %{pX430a_03} %{pX430a_04}
%{pX430a_05} %{pX430a_06} %{pX430a_07} %{pX430a_08} %{pX430a_09}
%{pX430a_10} 0.0000
0.0000 %{pX430b_00} %{pX430b_01} %{pX430b_02} %{pX430b_03} %{pX430b_04}
%{pX430b_05} %{pX430b_06} %{pX430b_07} %{pX430b_08} %{pX430b_09}
%{pX430b_10} 0.0000
0.0000 %{pEOL_00} %{pEOL_01} %{pEOL_02} %{pEOL_03} %{pEOL_04}
%{pEOL_05} %{pEOL_06} %{pEOL_07} %{pEOL_08} %{pEOL_09}
%{pEOL_10} 0.0000'
[]
[coolant_flux_function]
# Subassembly coolant mass flux. x: time (s), y: flux (kg m^-2 s^-1). See
# [Hayes et al., 1994] and [Greenquist and Powers, 2021].
type = PiecewiseLinear
x = ' 0 3600 8203212 8206812 13814423 13818023 14428975 14432575
21312419 21316019 25596874 25600474 26261755 26265355 32714598 32718198
32721798 32725398 32728998 32896765 32900365 39574695 39578295 42194062
42197662 43820808 43824408 43895709 43899309 44401212 44404812 47385472
47389072 48198548 48202148 48205748 48209348 48212948 52079977 52083577
53874489 53878089 62125235 62128835 62256058 62259658 62620357 62623957
64516928 64520528 64766586 64770186 67535546 67539146 72155534 72159134
72185697 72189297 76833647 76837247 77340548 77344148 77738400 77742000
80444447 80448047 80451647 80455247'
y = ' 2699.1 2699.1 2699.1 2724.0 2724.0 2697.2 2697.2 2781.0
2781.0 2721.1 2721.1 2696.9 2696.9 2785.4 2785.4 2785.4
2785.4 2785.4 2793.7 2793.7 2803.5 2803.5 2814.2 2814.2
2799.6 2799.6 2840.1 2840.1 2839.6 2839.6 2873.7 2873.7
2855.7 2855.7 2855.7 2855.7 2855.7 2826.4 2826.4 2826.4
2826.4 2788.4 2788.4 2780.6 2780.6 2771.8 2771.8 2781.5
2781.5 2817.1 2817.1 2807.4 2807.4 2777.1 2777.1 2777.1
2777.1 2746.4 2746.4 2765.9 2765.9 2765.9 2765.9 2777.1
2777.1 2777.1 2777.1 2777.1'
[]
[pin_lhr_avg_function]
type = CompositeFunction
functions = 'assembly_lhr_avg_function radial_peaking_factor_function'
[]
[pin_lhr_function]
type = CompositeFunction
functions = 'pin_lhr_avg_function lhr_peaking_factor_function'
[]
[coolant_pressure_function]
type = ConstantFunction
value = 347702.6 # [Snyder, 1988]
[]
[T_coolant_in_function]
# Sodium coolant inlet temperature. x: time (s), y: temperature (K). See
# [Hayes et al., 1994].
type = PiecewiseLinear
x = ' 0 3600 32718198 32721798 32725398 32728998 48202148 48205748
48209348 48212948 80448047 80451647 80455247'
y = ' 298.00 644.15 644.15 305.00 305.00 644.15 644.15 305.00
305.00 644.15 644.15 305.00 305.00'
[]
[sodium_volume_function]
# the initial sodium height is assumed to be equal to the initial fuel
# height and sodium infiltration is ignored.
type = ParsedFunction
symbol_names = 'pellet_outer_radius cladding_gap_width pellet_height'
symbol_values = '%{fuel_r} %{gap_width} %{fuel_h}'
expression = 'pi * ((pellet_outer_radius + cladding_gap_width)^2 -
pellet_outer_radius^2) * pellet_height'
[]
[gas_volume_function]
type = ParsedFunction
symbol_names = 'clad_internal_volume fuel_volume sodium_volume'
symbol_values = 'clad_internal_volume fuel_volume sodium_volume'
expression = 'abs(clad_internal_volume) - abs(fuel_volume) - abs(sodium_volume)'
[]
[sodium_conductivity_function]
# Thermal conductivity (W m^-1 K^-1) of the pin gap sodium according to
# [Fink and Leibowitz, 1995]. t: temperature (K).
type = ParsedFunction
symbol_names = 'A B C D'
symbol_values = '124.67 -0.11381 5.5226e-5 -1.1842e-8'
expression = 'A + B * t + C * t^2 + D * t^3'
[]
[creep_timestep_min_function]
type = ParsedFunction
symbol_names = 'creep_timestep_fuel creep_timestep_clad'
symbol_values = 'creep_timestep_fuel creep_timestep_clad'
expression = 'min(creep_timestep_fuel, creep_timestep_clad)'
[]
[fuel_axial_elongation_max_pct_function]
type = ParsedFunction
symbol_names = 'fuel_axial_elongation_min fuel_axial_elongation_max pellet_height'
symbol_values = 'fuel_axial_elongation_min fuel_axial_elongation_max %{fuel_h}'
expression = '(fuel_axial_elongation_max - fuel_axial_elongation_min) /
pellet_height * 100'
[]
[fuel_radial_dilation_max_pct_function]
type = ParsedFunction
symbol_names = 'fuel_radial_dilation_max pellet_outer_radius'
symbol_values = 'fuel_radial_dilation_max %{fuel_r}'
expression = 'fuel_radial_dilation_max / pellet_outer_radius * 100'
[]
[clad_axial_elongation_max_pct_function]
type = ParsedFunction
symbol_names = 'clad_axial_elongation_max plug_height cladding_total_height'
symbol_values = 'clad_axial_elongation_max 0.015 0.74065'
expression = 'clad_axial_elongation_max /
(plug_height + cladding_total_height) * 100'
[]
[clad_radial_dilation_max_pct_function]
type = ParsedFunction
symbol_names = 'clad_radial_dilation_max cladding_outer_radius'
symbol_values = 'clad_radial_dilation_max 0.003685'
expression = 'clad_radial_dilation_max / cladding_outer_radius * 100'
[]
[plenum_compressibility_function]
# Accounts for nonideality in fission gas [Hobbs and Charboneau, 2020]
type = ParsedFunction
symbol_names = 'plenum_pressure A B C'
symbol_values = 'plenum_pressure 1.002 -3.4e-8 -1.9e-15'
expression = 'A + B * plenum_pressure + C * plenum_pressure^2'
[]
[compressibility_times_temperature_function]
type = ParsedFunction
symbol_names = 'plenum_temperature plenum_compressibility'
symbol_values = 'plenum_temperature plenum_compressibility'
expression = 'plenum_temperature * plenum_compressibility'
[]
[]
[Physics/SolidMechanics/QuasiStatic]
add_variables = true
strain = FINITE
generate_output = 'stress_xx stress_yy stress_zz vonmises_stress
hydrostatic_stress creep_strain_xx creep_strain_yy
creep_strain_zz elastic_strain_xx elastic_strain_yy
elastic_strain_zz strain_xx strain_yy strain_zz'
[fuel_mechanics]
block = pellet
eigenstrain_names = 'fuel_thermal_strain fuel_gaseous_strain
fuel_solid_strain'
extra_vector_tags = ref
[]
[clad_mechanics]
block = clad
eigenstrain_names = 'clad_thermal_strain clad_gaseous_strain'
extra_vector_tags = ref
[]
[]
[Kernels]
[gravity]
type = Gravity
variable = disp_y
value = -9.81
extra_vector_tags = ref
[]
[heat_conduction_time_derivative]
type = HeatConductionTimeDerivative
variable = T
extra_vector_tags = ref
[]
[heat_conduction]
type = HeatConduction
variable = T
extra_vector_tags = ref
[]
[heat_source]
type = FissionRateHeatSource
block = pellet
variable = T
fission_rate = fission_rate
extra_vector_tags = ref
[]
[]
[AuxKernels]
[gap_conductance]
type = MaterialRealAux
variable = gap_conductance
property = gap_conductance
boundary = pellet_outer_radial_surface
[]
[fuel_clad_gap_width]
type = ParsedAux
variable = fuel_clad_gap_width
coupled_variables = penetration
expression = '-penetration'
[]
[failed_element]
type = MaterialRealAux
variable = element_failed
property = failed
boundary = clad_outside_right
[]
[fuel_volumetric_strain]
type = RankTwoScalarAux
block = pellet
variable = fuel_volumetric_strain
rank_two_tensor = total_strain
scalar_type = VolumetricStrain
[]
[clad_hoop_stress]
type = RankTwoAux
block = clad
variable = clad_hoop_stress
rank_two_tensor = stress
index_i = 2
index_j = 2
[]
[clad_hoop_creep_strain]
type = RankTwoAux
block = clad
variable = clad_hoop_creep_strain
rank_two_tensor = creep_strain
index_i = 2
index_j = 2
[]
[clad_hoop_elastic_strain]
type = RankTwoAux
block = clad
variable = clad_hoop_elastic_strain
rank_two_tensor = elastic_strain
index_i = 2
index_j = 2
[]
[clad_hoop_total_strain]
type = RankTwoAux
block = clad
variable = clad_hoop_total_strain
rank_two_tensor = total_strain
index_i = 2
index_j = 2
[]
[local_power]
type = FunctionAux
block = pellet
variable = local_power
function = lhr_peaking_factor_function
[]
[T_coolant]
type = MaterialRealAux
variable = T_coolant
property = coolant_temperature
boundary = clad_outside_right
[]
[pin_lhr]
type = FunctionAux
block = pellet
variable = pin_lhr
function = pin_lhr_function
[]
[eutectic_thickness]
type = DiffusionalEutecticThicknessFCCI
block = clad
variable = eutectic_thickness
temperature = T
boundary = clad_inside_right
execute_on = TIMESTEP_END
[]
[]
[Contact]
[frictionless_fuel_clad_mechanical]
primary = clad_inside_right
secondary = pellet_outer_radial_surface
model = frictionless
formulation = kinematic
tangential_tolerance = 1e-3
normal_smoothing_distance = 0.1
[]
[]
[ThermalContact]
[thermal_contact]
type = GapHeatTransfer
variable = T
primary = clad_inside_right
secondary = pellet_outer_radial_surface
gap_geometry_type = CYLINDER
gap_conductivity_function = sodium_conductivity_function
gap_conductivity_function_variable = T
quadrature = true
min_gap = %{gap_width} # Initial gap thickness according to dimensions.
tangential_tolerance = 1e-4
[]
[]
[BCs]
[fix_disp_x_all]
type = DirichletBC
variable = disp_x
value = 0.0
boundary = centerline
[]
[fix_disp_y_all]
type = DirichletBC
variable = disp_y
value = 0.0
boundary = 'clad_outside_bottom bottom_of_bottom_pellet'
[]
[Pressure]
[coolant_pressure]
function = coolant_pressure_function
boundary = 'clad_outside_bottom clad_outside_right clad_outside_top'
[]
[]
[PlenumPressure]
[plenum_pressure]
boundary = 'clad_inside_bottom clad_inside_right clad_inside_top'
startup_time = 0
initial_pressure = 84000 # [Hayes et al., 1994]
volume = gas_volume
material_input = fission_gas_released
R = 8.3143
temperature = plenum_temperature
output = plenum_pressure
[]
[]
[]
[PlenumTemperature]
[plenum_temperature]
temperature = T
boundary = 'bottom_of_bottom_pellet pellet_outer_radial_surface
top_of_top_pellet clad_inside_bottom clad_inside_right
clad_inside_top'
inner_surfaces = 'bottom_of_bottom_pellet pellet_outer_radial_surface
top_of_top_pellet'
outer_surfaces = 'clad_inside_bottom clad_inside_right clad_inside_top'
[]
[]
[CoolantChannel]
[convective_clad_surface]
variable = T
inlet_temperature = T_coolant_in_function
inlet_pressure = coolant_pressure_function
inlet_massflux = coolant_flux_function
coolant_material = sodium
rod_diameter = 0.00737 # [Hayes et al., 1994]
rod_pitch = %{pin_pitch}
linear_heat_rate = pin_lhr_avg_function
axial_power_profile = lhr_peaking_factor_function
subchannel_geometry = triangular
boundary = 'clad_outside_bottom clad_outside_right clad_outside_top'
[]
[]
[Materials]
###### FUEL ######
[fuel_fission_rate]
type = UPuZrFissionRate
block = pellet
rod_linear_power = pin_lhr_avg_function
axial_power_profile = lhr_peaking_factor_function
pellet_radius = %{fuel_r}
initial_X_Zr = %{x_Zr}
X_Zr = %{x_Zr}
outputs = exodus
output_properties = fission_rate
[]
[fuel_burnup]
type = UPuZrBurnup
block = pellet
density = %{fuel_density}
initial_X_Pu = %{x_Pu}
initial_X_Zr = %{x_Zr}
outputs = exodus
output_properties = burnup
[]
[fuel_density]
type = StrainAdjustedDensity
block = pellet
strain_free_density = %{fuel_density}
[]
[fuel_sodium_logging]
type = UPuZrSodiumLogging
block = pellet
porosity = porosity
sodium_infiltration_fraction = %{na_infiltration}
outputs = exodus
output_properties = sodium_logged_porosity
[]
[fuel_thermal_properties]
type = UPuZrThermal
block = pellet
X_Pu = %{x_Pu}
X_Zr = %{x_Zr}
spheat_model = savage
thcond_model = lanl
porosity_model = logged
porosity = porosity
sodium_logged_porosity = sodium_logged_porosity
[]
[fuel_elasticity_tensor]
type = UPuZrElasticityTensor
block = pellet
X_Pu = %{x_Pu}
X_Zr = %{x_Zr}
porosity = porosity
[]
[fuel_creep]
type = UPuZrCreepUpdate
block = pellet
porosity = porosity
max_inelastic_increment = 3e-3
effective_inelastic_strain_name = fuel_effective_creep_strain
[]
[fuel_gaseous_swelling]
type = UPuZrGaseousEigenstrain
block = pellet
fission_rate = fission_rate
anisotropic_factor = 0.5
bubble_number_density = 5e17
interconnection_initiating_porosity = %{fgr_initiating_porosity}
interconnection_terminating_porosity = %{fgr_terminating_porosity}
eigenstrain_name = fuel_gaseous_strain
outputs = exodus
output_properties = 'gas_swelling porosity interconnectivity'
[]
[fuel_solid_swelling]
type = BurnupDependentEigenstrain
block = pellet
eigenstrain_name = fuel_solid_strain
swelling_name = solid_swelling
swelling_factor = 0 # Solid swelling is negligible below 10% burnup
outputs = exodus
output_properties = solid_swelling
[]
[fuel_fission_gas_release]
type = UPuZrFissionGasRelease
block = pellet
fission_rate = fission_rate
porosity = porosity
critical_porosity = %{critical_porosity}
fractional_fgr_initial = %{fgr_initial}
fractional_fgr_post = %{fgr_post}
[]
[fuel_thermal_expansion]
type = UPuZrThermalExpansionEigenstrain
block = pellet
stress_free_temperature = 298
eigenstrain_name = fuel_thermal_strain
[]
[fuel_elastic_stress]
type = ComputeMultipleInelasticStress
block = pellet
inelastic_models = fuel_creep
[]
###### CLADDING ######
[fast_neutron_flux]
type = UPuZrFastNeutronFlux
pellet_radius = %{fuel_r}
axial_power_profile = lhr_peaking_factor_function
rod_linear_power = pin_lhr_avg_function
initial_density = %{fuel_density}
initial_X_Pu = %{x_Pu}
initial_X_Zr = %{x_Zr}
enrichment_U235 = %{enrichment_U}
enrichment_Pu240 = %{enrichment_Pu}
calculate_fluence = true
outputs = exodus
[]
[clad_density]
type = StrainAdjustedDensity
block = clad
strain_free_density = 7771
[]
[clad_thermal_properties]
type = HT9Thermal
block = clad
[]
[clad_gaseous_swelling]
type = HT9VolumetricSwellingEigenstrain
block = clad
fast_neutron_flux = fast_neutron_flux
fast_neutron_fluence = fast_neutron_fluence
eigenstrain_name = clad_gaseous_strain
[]
[clad_thermal_expansion]
type = HT9ThermalExpansionEigenstrain
block = clad
eigenstrain_name = clad_thermal_strain
stress_free_temperature = 298
[]
[clad_elasticity_tensor]
type = HT9ElasticityTensor
block = clad
[]
[clad_creep]
type = HT9CreepUpdate
block = clad
first_thermal_scalar = 1
second_thermal_scalar = 1
irradiation_scalar = 1
max_inelastic_increment = 3e-3 # 1e-2
effective_inelastic_strain_name = clad_effective_creep_strain
[]
[clad_failure]
type = HT9FailureClad
method = cdf_long
hoop_stress = stress_zz
boundary = clad_outside_right
outputs = exodus
output_properties = cdf_failure
[]
[inner_clad_wastage]
type = MetallicFuelWastage
block = clad
method = flux_ht9
burnup = 0 # not used but must be specified
outputs = exodus
output_properties = wastage_thickness
[]
[outer_clad_wastage]
type = MetallicFuelCoolantWastage
block = clad
clad_material = HT9
use_effective_method = true
outputs = exodus
[]
[clad_wastage_fraction]
type = MetallicFuelWastageDamage
block = clad
wastage_thickness = wastage_thickness
pellet_length = %{fuel_h}
pellet_y_start = 0.019
cladding_thickness = 0.0004064
outputs = exodus
[]
[clad_damage_fraction]
type = ScalarMaterialDamage
block = clad
damage_index = thinning_fraction
outputs = exodus
[]
[clad_elastic_stress]
type = ComputeMultipleInelasticStress
block = clad
inelastic_models = clad_creep
[]
[]
[Dampers]
[T_damper]
type = MaxIncrement
variable = T
max_increment = 25
[]
[disp_x_damper]
type = MaxIncrement
variable = disp_x
max_increment = 3.00E-04
[]
[disp_y_damper]
type = MaxIncrement
variable = disp_y
max_increment = 3.00E-04
[]
[]
[Preconditioning]
[SMP]
type = SMP
full = true
[]
[]
[Executioner]
type = Transient
solve_type = PJFNK
automatic_scaling = true
compute_scaling_once = false
petsc_options = '-snes_ksp_ew'
petsc_options_iname = '-pc_type -pc_factor_mat_solver_package
-ksp_gmres_restart'
petsc_options_value = 'lu superlu_dist
51'
line_search = NONE
l_max_its = 30
l_tol = 1e-3
nl_max_its = 30
nl_rel_tol = 1e-4
nl_abs_tol = 5e-7
start_time = %{t_start}
end_time = %{t_end}
dtmin = 1e-2
dtmax = 1e6
verbose = true
[Quadrature]
order = FIFTH
side_order = SEVENTH
[]
[TimeStepper]
type = IterationAdaptiveDT
dt = 1
optimal_iterations = 10
iteration_window = 4
growth_factor = 1.25
cutback_factor = 0.512
linear_iteration_ratio = 100
force_step_every_function_point = true
timestep_limiting_function = assembly_lhr_avg_function
timestep_limiting_postprocessor = creep_timestep_min
[]
[]
[Postprocessors]
###### POWER ######
[fission_rate_density_avg]
type = ElementAverageValue
block = pellet
variable = fission_rate
outputs = csv
[]
[fast_neutron_fluence_avg]
type = ElementAverageValue
variable = fast_neutron_fluence
outputs = 'csv chkfile'
[]
[fast_neutron_fluence_max]
type = ElementExtremeValue
variable = fast_neutron_fluence
value_type = max
outputs = 'csv chkfile'
[]
[pin_hr_tot]
type = ElementIntegralPower
block = pellet
variable = T # required but not actually used
use_material_fission_rate = true
fission_rate_material = fission_rate
outputs = csv
[]
[pin_lhr_avg]
type = FunctionValuePostprocessor
function = pin_lhr_avg_function
outputs = csv
[]
###### HEAT TRANSFER ######
[radial_heat_flux_from_fuel]
type = SideDiffusiveFluxIntegral
variable = T
boundary = pellet_outer_radial_surface
diffusivity = thermal_conductivity
outputs = csv
[]
[radial_heat_flux_from_clad]
type = SideDiffusiveFluxIntegral
variable = T
boundary = clad_outside_right
diffusivity = thermal_conductivity
outputs = csv
[]
###### FISSION GAS ###### (needed for simulation to run)
[fission_gas_produced]
type = ElementIntegralMaterialProperty
block = pellet
mat_prop = fis_gas_prod
outputs = 'csv chkfile'
[]
[fission_gas_released]
type = ElementIntegralMaterialProperty
block = pellet
mat_prop = fis_gas_rel
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[fission_gas_released_pct]
type = FGRPercent
fission_gas_generated = fission_gas_produced
fission_gas_released = fission_gas_released
outputs = 'console csv chkfile'
[]
[clad_internal_volume]
type = InternalVolume
boundary = 'clad_inside_bottom clad_inside_right clad_inside_top'
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[fuel_volume]
type = InternalVolume
boundary = 'bottom_of_bottom_pellet pellet_outer_radial_surface
top_of_top_pellet'
scale_factor = -1 # makes the fuel volume positive
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[sodium_volume]
type = FunctionValuePostprocessor
function = sodium_volume_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[gas_volume]
type = FunctionValuePostprocessor
function = gas_volume_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[plenum_compressibility]
type = FunctionValuePostprocessor
function = plenum_compressibility_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
[compressibility_times_temperature]
type = FunctionValuePostprocessor
function = compressibility_times_temperature_function
execute_on = 'INITIAL LINEAR TIMESTEP_END'
outputs = csv
[]
###### BURNUP ######
[burnup_max]
type = ElementExtremeValue
block = pellet
variable = burnup
value_type = max
outputs = csv
[]
[burnup_max_pct]
type = LinearCombinationPostprocessor
pp_names = burnup_max
pp_coefs = 100
outputs = 'csv chkfile'
[]
[burnup_avg]
type = ElementAverageValue
block = pellet
variable = burnup
outputs = csv
[]
[burnup_avg_pct]
type = LinearCombinationPostprocessor
pp_names = burnup_avg
pp_coefs = 100
outputs = 'console csv chkfile'
[]
###### FUEL TEMPERATURE ######
[fuel_T_max]
type = ElementExtremeValue
block = pellet
variable = T
value_type = max
outputs = csv
[]
[fuel_T_max_peak]
type = TimeExtremeValue
postprocessor = fuel_T_max
value_type = max
outputs = 'csv chkfile'
[]
[fuel_T_surface_max]
type = NodalExtremeValue
boundary = pellet_outer_radial_surface
variable = T
value_type = max
outputs = csv
[]
[fuel_T_surface_max_peak]
type = TimeExtremeValue
postprocessor = fuel_T_surface_max
value_type = max
outputs = 'csv chkfile'
[]
###### CLADDING TEMPERATURE ######
[clad_T_max]
type = ElementExtremeValue
block = clad
variable = T
value_type = max
outputs = csv
[]
[clad_T_max_peak]
type = TimeExtremeValue
postprocessor = clad_T_max
value_type = max
outputs = csv
[]
[clad_T_inner_surface_max]
type = NodalExtremeValue
boundary = clad_inside_right
variable = T
value_type = max
outputs = csv
[]
[clad_T_inner_surface_max_peak]
type = TimeExtremeValue
postprocessor = clad_T_inner_surface_max
value_type = max
outputs = 'csv chkfile'
[]
[clad_T_outer_surface_max]
type = NodalExtremeValue
boundary = clad_outside_right
variable = T
value_type = max
outputs = csv
[]
[clad_T_outer_surface_max_peak]
type = TimeExtremeValue
postprocessor = clad_T_outer_surface_max
value_type = max
outputs = 'csv chkfile'
[]
###### COOLANT PARAMETERS ######
[T_coolant_in]
type = FunctionValuePostprocessor
function = T_coolant_in_function
outputs = csv
[]
[T_coolant_out]
type = ElementExtremeValue
block = clad
variable = T_coolant
value_type = max
outputs = csv
[]
[coolant_flux]
type = FunctionValuePostprocessor
function = coolant_flux_function
outputs = csv
[]
###### FUEL DEFORMATION ######
[fuel_axial_elongation_min]
type = NodalExtremeValue
block = pellet
variable = disp_y
value_type = min
outputs = csv
[]
[fuel_axial_elongation_max]
type = NodalExtremeValue
block = pellet
variable = disp_y
value_type = max
outputs = csv
[]
[fuel_axial_elongation_max_pct]
type = FunctionValuePostprocessor
function = fuel_axial_elongation_max_pct_function
outputs = 'console csv chkfile'
[]
[fuel_radial_dilation_max]
type = NodalExtremeValue
variable = disp_x
boundary = pellet_outer_radial_surface
value_type = max
outputs = csv
[]
[fuel_radial_dilation_max_pct]
type = FunctionValuePostprocessor
function = fuel_radial_dilation_max_pct_function
outputs = csv
[]
###### CLADDING DEFORMATION ######
[clad_axial_elongation_max]
type = NodalExtremeValue
block = clad
variable = disp_y
value_type = max
outputs = csv
[]
[clad_axial_elongation_max_pct]
type = FunctionValuePostprocessor
function = clad_axial_elongation_max_pct_function
outputs = 'csv chkfile'
[]
[clad_radial_dilation_max]
type = NodalExtremeValue
variable = disp_x
boundary = clad_outside_right
value_type = max
outputs = csv
[]
[clad_radial_dilation_max_pct]
type = FunctionValuePostprocessor
function = clad_radial_dilation_max_pct_function
outputs = 'console csv chkfile'
[]
###### GAP DEFORMATION AND MECHANICS ######
[gap_width_min]
type = NodalExtremeValue
variable = fuel_clad_gap_width
boundary = pellet_outer_radial_surface
value_type = min
outputs = csv
[]
[gap_width_max]
type = NodalExtremeValue
variable = fuel_clad_gap_width
boundary = pellet_outer_radial_surface
value_type = max
outputs = csv
[]
[gap_width_avg]
type = SideAverageValue
variable = fuel_clad_gap_width
boundary = pellet_outer_radial_surface
outputs = csv
[]
[contact_pressure_max]
type = NodalExtremeValue
variable = contact_pressure
boundary = pellet_outer_radial_surface
value_type = max
outputs = csv
[]
###### FUEL MECHANICS ######
[fuel_hydrostatic_stress_min]
type = ElementExtremeValue
block = pellet
variable = hydrostatic_stress
value_type = min
outputs = csv
[]
[fuel_hydrostatic_stress_max]
type = ElementExtremeValue
block = pellet
variable = hydrostatic_stress
value_type = max
outputs = csv
[]
[fuel_hydrostatic_stress_avg]
type = ElementAverageValue
block = pellet
variable = hydrostatic_stress
outputs = csv
[]
[fuel_volumetric_strain_avg]
type = ElementAverageValue
block = pellet
variable = fuel_volumetric_strain
outputs = 'csv chkfile'
[]
###### CLADDING MECHANICS ######
[clad_hoop_stress_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_stress
value_type = max
outputs = csv
[]
[clad_hoop_creep_strain_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_creep_strain
value_type = max
outputs = 'csv chkfile'
[]
[clad_hoop_elastic_strain_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_elastic_strain
value_type = max
outputs = 'csv chkfile'
[]
[clad_hoop_total_strain_max]
type = ElementExtremeValue
block = clad
variable = clad_hoop_total_strain
value_type = max
outputs = 'csv chkfile'
[]
[cdf_max]
type = ElementExtremeValue
variable = cdf_failure
value_type = max
outputs = 'console csv'
[]
###### PERFORMANCE ######
[creep_timestep_fuel]
type = MaterialTimeStepPostprocessor
block = pellet
outputs = csv
[]
[creep_timestep_clad]
type = MaterialTimeStepPostprocessor
block = clad
outputs = csv
[]
[creep_timestep_min]
type = FunctionValuePostprocessor
function = creep_timestep_min_function
outputs = csv
[]
###### SWELLING ######
[solid_swelling_avg]
type = ElementAverageValue
block = pellet
variable = solid_swelling
outputs = 'csv chkfile'
[]
[gas_swelling_avg]
type = ElementAverageValue
block = pellet
variable = gas_swelling
outputs = 'csv chkfile'
[]
[porosity_avg]
type = ElementAverageValue
block = pellet
variable = porosity
outputs = 'csv chkfile'
[]
[sodium_logged_porosity_avg]
type = ElementAverageValue
block = pellet
variable = sodium_logged_porosity
outputs = 'csv chkfile'
[]
###### CLADDING WASTAGE ######
[wastage_max]
type = ElementExtremeValue
block = clad
variable = wastage_thickness
value_type = max
outputs = 'csv chkfile'
[]
[wastage_min]
type = ElementExtremeValue
block = clad
variable = wastage_thickness
value_type = min
outputs = csv
[]
[wastage_avg]
type = ElementAverageValue
block = clad
variable = wastage_thickness
outputs = csv
[]
[eutectic_max]
type = ElementExtremeValue
block = clad
variable = eutectic_thickness
value_type = max
outputs = csv
[]
[eutectic_min]
type = ElementExtremeValue
block = clad
variable = eutectic_thickness
value_type = min
outputs = csv
[]
[eutectic_avg]
type = ElementAverageValue
block = clad
variable = eutectic_thickness
outputs = csv
[]
[]
[VectorPostprocessors]
[fuel_centerline]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = centerline
sort_by = y
outputs = csv
[]
[fuel_surface]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = pellet_outer_radial_surface
sort_by = y
outputs = csv
[]
[clad_inner_surface]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = clad_inside_right
sort_by = y
outputs = csv
[]
[clad_outer_surface]
type = SideValueSampler
variable = 'T disp_x disp_y'
boundary = clad_outside_right
sort_by = y
outputs = csv
[]
[]
[PerformanceMetricOutputs]
outputs = 'csv performance'
[]
[Outputs]
color = false
perf_graph = true
[console]
type = Console
output_screen = true
[]
[exodus]
type = Exodus
execute_on = 'INITIAL TIMESTEP_END FINAL'
time_step_interval = 50
[]
[csv]
type = CSV
execute_postprocessors_on = 'INITIAL TIMESTEP_END'
execute_vector_postprocessors_on = FINAL
[]
[chkfile]
type = CSV
execute_postprocessors_on = FINAL
[]
[performance]
type = CSV
hide = 'plenum_pressure plenum_temperature'
execute_postprocessors_on = FINAL
[]
[]
# REFERENCES
# [Fink and Leibowitz, 1995]
# J. K. Fink and L. Leibowitz, "Thermodynamic and transport properties of
# sodium liquid and vapor", Argonne National Laboratory ANL/RE--95/2, 94649,
# Argonne, Illinois (1995)
# [Greenquist and Powers, 2021]
# I. Greenquist, J.J. Powers "25-Pin metallic fuel performance benchmark
# case based on the EBR-II X430 experiment series" Journal of Nuclear
# Materials Vol 556, 153211 (2021)
# [Hayes et al., 1994]
# S.L. Hayes, D.C. Crawford, R.G. Phal "Test Design and Postirradiation
# Examination of the HT9 Advanced Driver Fuel Test (X430)" Argonne National
# Laboratory ANL-IFR-225, Idaho Falls, Idaho (1994)
# [Hobbs and Charboneau, 2020]
# I.M. Hobbs, J.A. Charboneau "Compressibility of gas mixtures pertaining to
# nuclear fuel rods" Journal of Physics Comminications Vol. 4, Iss. 9,
# 095008 (2020)
# [Shultis and Faw, 2008]
# J.K. Shultis, R.E. Faw "Fundamentals of Nuclear Science and Engineering
# Second Edition" CRC Press, Boca Raton, Florida (2008)
# [Snyder, 1988]
# E. Snyder "Report of EBR-II Operations: Run 146 and 147", Argonne National
# Laboratory ANLEBR.R146 ANLEBR.R147, Idaho Falls, Idaho (1988)
(test/tests/upuzr_fast_neutron_flux/exact.i)
# This test checks UPuZrFastNeutronFlux against a hand calculation while varying all possible input
# parameters.
#
# dpa should compute to 1 at the final timestep to ensure fluence and dpa are being calculated correctly
[Problem]
solve = false
[]
[Mesh]
coord_type = RZ
[mesh]
type = GeneratedMeshGenerator
dim = 2
nx = 1
ny = 8
ymax = 8
[]
[]
[Functions]
[linear_power]
type = ParsedFunction
expression = 't'
[]
[axial_profile]
type = ParsedFunction
expression = 'y'
[]
[flux_exact_fcn]
type = ParsedFunction
symbol_names = 'linear_power axial_profile'
symbol_values = 'linear_power axial_profile'
expression = 'epf := 1 / pi / 10.0;
rad_outer := 2;
rad_inner := 1;
ratio := 0.3;
fsnrateden := ratio * linear_power * axial_profile / (rad_outer^2 - rad_inner^2) / pi / epf;
U_ratio := 0.2;
Pu_ratio := 0.3;
X_Pu := 0.2;
X_Zr := 0.1;
X_U := 1.0 - X_Pu - X_Zr;
X_U235 := X_U * U_ratio;
X_U238 := X_U - X_U235;
X_Pu240 := X_Pu * Pu_ratio;
X_Pu239 := X_Pu - X_Pu240;
A_U235 := 0.2350439231;
A_U238 := 0.2380507826;
A_Pu239 := 0.2390521565;
A_Pu240 := 0.2400538075;
A_Zr := 0.091224;
Atot := X_U235 * A_U235 + X_U238 * A_U238 + X_Pu239 * A_Pu239 + X_Pu240 * A_Pu240 + X_Zr * A_Zr;
sigma_U235 := 1.0e4;
sigma_U238 := 1.0e3;
sigma_Pu239 := 1.0e4;
sigma_Pu240 := 8199.0380426;
density := 4;
Ntot := density * 6.022e23 * 1.0e-28 / Atot;
sigma_tot := Ntot * (X_U235 * sigma_U235 + X_U238 * sigma_U238 + X_Pu239 * sigma_Pu239 + X_Pu240 * sigma_Pu240);
fsnrateden / sigma_tot'
[]
[]
[Materials]
[flux]
type = UPuZrFastNeutronFlux
axial_power_profile = axial_profile
rod_linear_power = linear_power
fast_spectrum_ratio = 0.3
initial_X_Pu = 0.2
initial_X_Zr = 0.1
initial_density = 4
pellet_inner_radius = 1.0
pellet_radius = 2.0
enrichment_Pu240 = 0.3
enrichment_U235 = 0.2
sigma_U235 = 1.0e4
sigma_U238 = 1.0e3
sigma_Pu239 = 1.0e4
sigma_Pu240 = 8199.0380426
energy_per_fission = 0.031830989
dpa_conversion_factor = 1.9245015
outputs = all
calculate_fluence = true
calculate_dpa = true
calculate_dpa_rate = true
fast_neutron_flux_name = 'asdf_fast_neutron_flux'
fast_neutron_fluence_name = 'asdf_fast_neutron_fluence'
dpa_name = 'asdf_dpa'
[]
[flux_exact]
type = GenericFunctionMaterial
prop_names = 'flux_exact'
prop_values = 'flux_exact_fcn'
outputs = all
[]
[]
[Executioner]
type = Transient
num_steps = 2
[]
[Postprocessors]
[flux_old]
type = ElementAverageValue
variable = asdf_fast_neutron_flux
execute_on = 'TIMESTEP_BEGIN'
[]
[flux_avg]
type = ElementAverageValue
variable = 'asdf_fast_neutron_flux'
[]
[flux_exact_avg]
type = ElementAverageValue
variable = 'flux_exact'
[]
[flux_error]
type = ElementL2Error
variable = asdf_fast_neutron_flux
function = flux_exact_fcn
[]
[dt]
type = TimestepSize
[]
[fluence_avg]
type = ElementAverageValue
variable = 'asdf_fast_neutron_fluence'
[]
[dfluence_exact]
type = ParsedPostprocessor
pp_names = 'flux_avg flux_old dt'
expression = 'dt * (flux_avg + flux_old) / 2'
[]
[fluence_exact]
type = CumulativeValuePostprocessor
postprocessor = dfluence_exact
[]
[fluence_diff]
type = ParsedPostprocessor
pp_names = 'fluence_avg fluence_exact'
expression = '(fluence_avg - fluence_exact) / fluence_exact'
outputs = console
[]
[fluence_max_diff]
type = TimeExtremeValue
postprocessor = fluence_diff
value_type = abs_max
[]
[dpa_rate_avg]
type = ElementAverageValue
variable = 'asdf_dpa_rate'
[]
[dpa_rate_exact]
type = ParsedPostprocessor
pp_names = 'flux_avg flux_old dt'
expression = '(flux_avg + flux_old) / 2 / 1.9245015'
[]
[dpa_rate_diff]
type = ParsedPostprocessor
pp_names = 'dpa_rate_avg dpa_rate_exact'
expression = '(dpa_rate_avg - dpa_rate_exact) / dpa_rate_exact'
outputs = console
[]
[dpa_rate_max_diff]
type = TimeExtremeValue
postprocessor = dpa_rate_diff
value_type = abs_max
[]
[dpa_avg]
type = ElementAverageValue
variable = 'asdf_dpa'
[]
[dpa_exact]
type = CumulativeValuePostprocessor
postprocessor = 'dpa_rate_exact'
[]
[dpa_diff]
type = ParsedPostprocessor
pp_names = 'dpa_avg dpa_exact'
expression = '(dpa_avg - dpa_exact) / dpa_exact'
outputs = console
[]
[dpa_max_diff]
type = TimeExtremeValue
postprocessor = dpa_diff
value_type = abs_max
[]
[]
[Outputs]
csv = true
[]
(test/tests/upuzr_fast_neutron_flux/ad.i)
# This test checks the fast neutron flux calculated UPuZrFastNeutronFlux coupled to a variable
[Mesh]
coord_type = RZ
[mesh]
type = GeneratedMeshGenerator
dim = 2
nx = 4
ny = 10
ymax = 0.343
xmax = 0.002
[]
[]
[Variables]
[damage]
[]
[]
[Kernels]
[damage_dt]
type = ADTimeDerivative
variable = damage
[]
[damage_generation]
type = ADFissionRateHeatSource
fission_rate = fast_neutron_flux
variable = damage
[]
[]
[Functions]
[power_history]
type = PiecewiseLinear
x = '0 1'
y = '0 30000'
[]
[axial_peaking_factors]
type = PowerPeakingFunction
fit = EBRII_ROW_3
pellet_length = 343.0e-3
pellet_y_start = 2.55e-3
[]
[]
[Materials]
[flux]
type = ADUPuZrFastNeutronFlux
axial_power_profile = power_history
rod_linear_power = axial_peaking_factors
initial_X_Pu = 0.2
initial_X_Zr = 0.1
initial_density = 15800
pellet_radius = 0.003
enrichment_Pu240 = 0.3
enrichment_U235 = 0.2
outputs = all
calculate_fluence = true
[]
[]
[Executioner]
type = Transient
dt = 0.1
num_steps = 5
[]
[Postprocessors]
[flux_avg]
type = ElementAverageValue
variable = fast_neutron_flux
[]
[fluence_avg]
type = ElementAverageValue
variable = fast_neutron_fluence
[]
[damage_avg]
type = ElementAverageValue
variable = damage
[]
[]
[Outputs]
exodus = true
[]