MeshTally

note

MeshTally can only be added to problems when the input files contains a OpenMCCellAverageProblem in the [Problem] block. Otherwise, attempting to add this tally will result in an error.

Description

The MeshTally class wraps an OpenMC tally with an unstructured libMesh filter to directly enable tallying on an unstructured mesh. There are two options when using a MeshTally:

Do nothing, in which case OpenMC will tally on the [Mesh]
Specify a mesh_template, which provides a path to a mesh file

For the mesh_template option, it is possible to translate the same mesh to multiple locations in the OpenMC geometry (while only taking up the memory needed to store a single mesh) using the mesh_translations or mesh_translations_file parameters provided by the tallies block. This is a useful feature for geometries that consist of many repeated geometry units, such as pebble bed and pin fuel systems.

note

At present, unstructured mesh tallies are copied directly to the [Mesh] (without doing any type of nearest-node lookup). Suppose the mesh template consists of a mesh for a pincell with $var element = document.getElementById("moose-equation-bd9f4858-d6ed-46fd-8dd7-dcd34ef47783");katex.render("N", element, {displayMode:false,throwOnError:false});$ elements that you have translated to 3 different locations, giving a total of $var element = document.getElementById("moose-equation-ac14745c-e4dc-4475-8088-ecae86bcea81");katex.render("3N", element, {displayMode:false,throwOnError:false});$ tally bins. Because a direct copy is used to transfer the mesh tally results to the [Mesh], the first $var element = document.getElementById("moose-equation-a100ca82-4467-492f-bd4f-09d72c757a11");katex.render("3N", element, {displayMode:false,throwOnError:false});$ elements in the [Mesh] must exactly match the $var element = document.getElementById("moose-equation-f99e8956-50af-4e96-b3fa-ef3862e65b61");katex.render("3N", element, {displayMode:false,throwOnError:false});$ elements in the mesh tally (except for a possible mesh scaling, as described in Mesh Scaling ). This equivalence is required for the direct copy to be accurate - otherwise, the mesh tally results would be transferred to incorrect regions of space.

Cardinal supports several tally scores which can be specified in the score parameter when adding a tally. Options include:

heating: total nuclear heating
heating_local: same as the heating score, except that energy from secondary photons is deposited locally
kappa_fission: recoverable energy from fission, including prompt sources (fission fragments, prompt neutrons, prompt gammas) and delayed sources (delayed neutrons, delayed gammas, delayed betas). Neutrino energy is neglected. The energy from photons is assumed to deposit locally.
fission_q_prompt: the prompt components of the kappa_fission score, except that the energy released is a function of the incident energy by linking to optional fission energy release data.
fission_q_recoverable: same as the kappa_fission score, except that the score depends on the incident energy by linking to optional fission energy release data
damage_energy: damage energy production
flux: particle scalar flux
H3_production: tritium production reaction rate
total: the total reaction rate
absorption: the absorption reaction rate
scatter: the scatter reaction rate
fission: the fission reaction rate

For more information on the specific meanings of these various scores, please consult the OpenMC tally documentation. The names of the tally auxvariables added by the OpenMCCellAverageProblem can be modified by specifying a name for each score in name.

This tally is capable of controlling OpenMC execution through the use of tally triggers. Tallies currently support active batch termination through a relative error indicator, which can be enabled by setting trigger to rel_err for each score in the tally. Scores which do not need to control active batch termination can have a value of none set. If enabled, an appropriate relative error must be set for each score in trigger_threshold.

Certain aspects of tally results can be output as auxiliary variables to the mesh:

unrelaxed_tally: unrelaxed tally; this will append _raw to the tally name and output to the mesh mirror
unrelaxed_tally_std_dev: unrelaxed tally standard deviation; this will append _std_dev to the tally and output to the mesh mirror

note

At present time, libMesh unstructured mesh tallies only support collision and analog estimators. Attempting to set estimator to tracklength will result in a warning; the MeshTally will then manually reset the estimator to collision to prevent OpenMC from throwing an error.

Example Input File Syntax

As an example, this MeshTally scores kappa_fission (the default tally score) on the unstructured mesh found in mesh_in.e and stores it in a variable called heat_source. The [Tallies] block adds three MeshTally classes, each one located at a different point specified in mesh_translations which corresponds to the centroid of a fuel pebble.

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1500.0
  temperature_blocks = '0'
  normalize_by_global_tally = false
  cell_level = 1
  scaling = 100.0

  [Tallies]
    [heat_source]
      type = MeshTally
      mesh_translations = '0 0 0.02
                           0 0 0.06
                           0 0 0.10'
      mesh_template = mesh_in.e
      name = heat_source
    []
  []
[]

Input Parameters

estimatorType of tally estimator to use in OpenMC
C++ Type:MooseEnum
Options:collision, tracklength, analog
Controllable:No
Description:Type of tally estimator to use in OpenMC
filtersExternal filters to add to this tally.
C++ Type:std::vector<std::string>
Controllable:No
Description:External filters to add to this tally.
mesh_templateMesh tally template for OpenMC when using mesh tallies; at present, this mesh must exactly match the mesh used in the [Mesh] block because a one-to-one copy is used to get OpenMC's tally results on the [Mesh].
C++ Type:std::string
Controllable:No
Description:Mesh tally template for OpenMC when using mesh tallies; at present, this mesh must exactly match the mesh used in the [Mesh] block because a one-to-one copy is used to get OpenMC's tally results on the [Mesh].
mesh_translationCoordinate to which this mesh should be translated. Units must match those used to define the [Mesh].
C++ Type:libMesh::Point
Controllable:No
Description:Coordinate to which this mesh should be translated. Units must match those used to define the [Mesh].
nameAuxiliary variable name(s) to use for OpenMC tallies. If not specified, defaults to the names of the scores
C++ Type:std::vector<std::string>
Controllable:No
Description:Auxiliary variable name(s) to use for OpenMC tallies. If not specified, defaults to the names of the scores
outputUNRELAXED field(s) to output from OpenMC for each tally score. unrelaxed_tally_std_dev will write the standard deviation of each tally into auxiliary variables named *_std_dev. Unrelaxed_tally will write the raw unrelaxed tally into auxiliary variables named *_raw (replace * with 'name').
C++ Type:MultiMooseEnum
Options:unrelaxed_tally_std_dev, unrelaxed_tally
Controllable:No
Description:UNRELAXED field(s) to output from OpenMC for each tally score. unrelaxed_tally_std_dev will write the standard deviation of each tally into auxiliary variables named *_std_dev. Unrelaxed_tally will write the raw unrelaxed tally into auxiliary variables named *_raw (replace * with 'name').
scoreScore(s) to use in the OpenMC tallies. If not specified, defaults to 'kappa_fission'
C++ Type:MultiMooseEnum
Options:heating, heating_local, kappa_fission, fission_q_prompt, fission_q_recoverable, damage_energy, flux, H3_production, total, absorption, scatter, fission
Controllable:No
Description:Score(s) to use in the OpenMC tallies. If not specified, defaults to 'kappa_fission'
triggerTrigger criterion to determine when OpenMC simulation is complete based on tallies. If multiple scores are specified in 'score, this same trigger is applied to all scores.
C++ Type:MultiMooseEnum
Options:rel_err, none
Controllable:No
Description:Trigger criterion to determine when OpenMC simulation is complete based on tallies. If multiple scores are specified in 'score, this same trigger is applied to all scores.
trigger_ignore_zeros0 Whether tally bins with zero scores are ignored when computing the tally trigger. If only one value of 'trigger_ignore_zeros' is provided, that value is applied to all tally scores.
Default:0
C++ Type:std::vector<bool>
Controllable:No
Description:Whether tally bins with zero scores are ignored when computing the tally trigger. If only one value of 'trigger_ignore_zeros' is provided, that value is applied to all tally scores.
trigger_thresholdThreshold for the tally trigger
C++ Type:std::vector<double>
Controllable:No
Description:Threshold for the tally trigger

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:No
Description:Set the enabled status of the MooseObject.

Advanced Parameters

Input Files

(test/tests/neutronics/dagmc/mesh_tallies/csg_step_2/openmc.i)
(test/tests/neutronics/mesh_tally/no_coupling.i)
(test/tests/neutronics/filters/polar/mesh_sum.i)
(test/tests/openmc_errors/mesh_translations/invalid_row.i)
(test/tests/neutronics/dagmc/mesh_tallies/direct_tally.i)
(test/tests/neutronics/dagmc/mesh_tallies/with_scaling.i)
(test/tests/neutronics/filters/energy/mesh.i)
(test/tests/neutronics/mesh_tally/one_mesh_global.i)
(tutorials/csg_to_cad/openmc.i)
(test/tests/neutronics/dagmc/missing_graveyard.i)
(test/tests/neutronics/filters/polar/mesh.i)
(tutorials/lwr_solid/openmc_um.i)
(test/tests/neutronics/mesh_tally/different_units_and_translations.i)
(test/tests/neutronics/dagmc/incompatible_geom/mismatch/openmc.i)
(tutorials/msfr/openmc.i)
(test/tests/neutronics/symmetry/wrong_uo.i)
(test/tests/neutronics/filters/mesh_sum_gold.i)
(test/tests/openmc_errors/mesh_tally/incorrect_scaling.i)
(test/tests/neutronics/dagmc/mesh_tallies/disjoint_bins.i)
(test/tests/neutronics/mesh_tally/one_mesh_no_input_file.i)
(test/tests/neutronics/tally_system/multi_mesh_relax.i)
(test/tests/neutronics/relaxation/mesh_tallies/output_fission_tally.i)
(test/tests/neutronics/dagmc/no_symmetry.i)
(tutorials/tokamak/openmc.i)
(test/tests/neutronics/tally_system/multi_mesh_triggers.i)
(test/tests/neutronics/filters/azimuthal/mesh.i)
(test/tests/neutronics/tally_system/multi_mesh.i)
(test/tests/neutronics/mesh_tally/fission_tally_std_dev.i)
(test/tests/neutronics/tally_system/multi_diff.i)
(test/tests/neutronics/heat_source/multi_tally_mesh.i)
(test/tests/neutronics/mesh_tally/multiple_meshes_global.i)
(test/tests/neutronics/filters/xml/mesh.i)
(test/tests/neutronics/mesh_tally/multiple_meshes.i)
(test/tests/neutronics/filters/energy/mesh_sum.i)
(test/tests/neutronics/mesh_tally/one_mesh.i)
(test/tests/neutronics/mesh_tally/different_units.i)
(test/tests/openmc_errors/mesh_tally/incorrect_order.i)
(test/tests/neutronics/triggers/mesh_tally_rel_err.i)
(tutorials/pebbles/openmc_um.i)
(test/tests/neutronics/feedback/lattice/non_material_fluid.i)
(test/tests/openmc_errors/mesh_tally/incorrect_file.i)
(tutorials/dagmc/openmc.i)
(test/tests/neutronics/filters/azimuthal/mesh_sum.i)
(test/tests/neutronics/dagmc/mesh_tallies/openmc.i)
(test/tests/neutronics/dagmc/incompatible_geom/has_csg/openmc.i)
(test/tests/neutronics/dagmc/mesh_tallies/csg_step_1/openmc.i)
(doc/content/source/actions/multi_tally_example.i)
(test/tests/neutronics/dagmc/mesh_tallies/one_bin.i)
(test/tests/neutronics/relaxation/mesh_tallies/openmc.i)

(tutorials/pebbles/openmc_um.i)

[Mesh]
  [pebble]
    type = FileMeshGenerator
    file = mesh_in.e
  []
  [repeat]
    type = CombinerGenerator
    inputs = pebble
    positions = '0 0 0.02
                 0 0 0.06
                 0 0 0.10'
  []

  allow_renumbering = false
[]


[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1500.0
  temperature_blocks = '0'
  normalize_by_global_tally = false
  cell_level = 1
  scaling = 100.0

  [Tallies]
    [heat_source]
      type = MeshTally
      mesh_translations = '0 0 0.02
                           0 0 0.06
                           0 0 0.10'
      mesh_template = mesh_in.e
      name = heat_source
    []
  []
[]

[Executioner]
  type = Transient
[]

[Outputs]
  exodus = true
  csv = true
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = heat_source
  []
  [max_tally_rel_err]
    type = TallyRelativeError
  []
  [k]
    type = KEigenvalue
  []
[]

(test/tests/neutronics/dagmc/mesh_tallies/csg_step_2/openmc.i)

[Mesh]
  type = FileMesh
  file = ../slab.e
[]

x0 = 12.5
x1 = 37.5
x2 = 62.5

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

T0 = 600.0
dT = 50.0

[Functions]
  [temp]
    type = ParsedFunction
    expression = 'if (x <= ${x0}, ${fparse T0 - dT}, if (x <= ${x1}, ${T0}, if (x <= ${x2}, ${fparse T0 + dT}, ${fparse T0 + 2 * dT})))'
  []
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = temp
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true

  temperature_blocks = '1 2'
  cell_level = 0
  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../slab.e
    []
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 2
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/mesh_tally/no_coupling.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  check_tally_sum = false
  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [power]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
[]

[Outputs]
  csv = true
[]

(test/tests/neutronics/filters/polar/mesh_sum.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'Polar'
    []
  []

  [Filters]
    [Polar]
      type = PolarAngleFilter
      num_equal_divisions = 2
    []
  []
[]

[AuxVariables]
  [flux]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [total_flux]
    type = SumAux
    variable = flux
    values = 'flux_theta1 flux_theta2'
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
  hide = 'flux_theta1 flux_theta2'
[]

(test/tests/openmc_errors/mesh_translations/invalid_row.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../neutronics/meshes/sphere.e
  []
  [combine]
    type = CombinerGenerator
    inputs = 'sphere'
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../neutronics/meshes/sphere.e'
      mesh_translations_file = pebble_centers.txt
    []
  []
[]

[Executioner]
  type = Transient
[]

(test/tests/neutronics/dagmc/mesh_tallies/direct_tally.i)

[Mesh]
  type = FileMesh
  file = slab.e
  allow_renumbering = false
  parallel_type = replicated
[]

x0 = 12.5
x1 = 37.5
x2 = 62.5

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

T0 = 600.0
dT = 50.0

[Functions]
  [temp]
    type = ParsedFunction
    expression = 'if (x <= ${x0}, ${fparse T0 - dT}, if (x <= ${x1}, ${T0}, if (x <= ${x2}, ${fparse T0 + dT}, ${fparse T0 + 2 * dT})))'
  []
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = temp
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true

  temperature_blocks = '1 2'
  cell_level = 0
  power = 100.0

  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = ${fparse T0 - dT}
    temperature_max = ${fparse T0 + 2 * dT}
    n_temperature_bins = 4
    temperature = temp
    build_graveyard = true
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 2
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/dagmc/mesh_tallies/with_scaling.i)

scale = 100.0

[Mesh]
  [file]
    type = FileMeshGenerator
    file = scale_in.e
  []
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Functions]
  [temp]
    type = ParsedFunction
    expression = '500.0 + 10.0*x*${scale}'
  []
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = temp
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  scaling = ${scale}

  temperature_blocks = '1 2'
  cell_level = 0
  power = 16.0

  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = scale_in.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = 300.0
    temperature_max = 1500.0
    n_temperature_bins = 10
    temperature = temp
    build_graveyard = true
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/filters/energy/mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'Energy'
    []
  []

  [Filters]
    [Energy]
      type = EnergyFilter
      # CASMO 2 group structure for testing. May result in some missed particles
      energy_boundaries = '0.0 6.25e-1 2.0e7'
    []
  []
[]

[Postprocessors]
  [Total_Flux_1]
    type = ElementIntegralVariablePostprocessor
    variable = flux_g1
  []
  [Total_Flux_2]
    type = ElementIntegralVariablePostprocessor
    variable = flux_g2
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  csv = true
[]

(test/tests/neutronics/mesh_tally/one_mesh_global.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = true

  power = 100.0
  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere.e'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp  cell_instance cell_id'
[]

(tutorials/csg_to_cad/openmc.i)

power = 3000

[Problem]
  type = OpenMCCellAverageProblem
  power = ${power}

  temperature_blocks = '1'
  cell_level = 1

  skinner = skinner

  normalize_by_global_tally = false
  source_rate_normalization = 'kappa_fission'

  [Tallies]
    [mesh]
      type = MeshTally
      score = 'kappa_fission flux'
    []
  []
[]

[Mesh]
  [fuel]
    type = FileMeshGenerator
    file = krusty_fuel.e
  []
[]

[UserObjects]
  [skinner]
    type = MoabSkinner
    temperature = temp
    n_temperature_bins = 4
    temperature_min = 800
    temperature_max = 1000
    build_graveyard = true
  []
[]

[MultiApps]
  [conduction]
    type = TransientMultiApp
    input_files = 'fuel.i'
    execute_on = timestep_end
  []
[]

[Transfers]
  [heat_source_from_openmc]
    type = MultiAppGeneralFieldShapeEvaluationTransfer
    to_multi_app = conduction
    source_variable = kappa_fission
    variable = power
    from_postprocessors_to_be_preserved = tally_integral
    to_postprocessors_to_be_preserved = tally_integral
    search_value_conflicts = false
  []
  [temp_to_openmc]
    type = MultiAppGeneralFieldShapeEvaluationTransfer
    from_multi_app = conduction
    variable = temp
    source_variable = T
    search_value_conflicts = false
  []
[]

[ICs]
  [temp]
    type = ConstantIC
    variable = temp
    value = 800
  []
  [power]
    type = ConstantIC
    variable = kappa_fission
    value = ${fparse power/1.865e+03}
  []
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Postprocessors]
  [tally_integral]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    execute_on = 'initial transfer timestep_end'
  []
[]

[Executioner]
  type = Transient
  num_steps = 3
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/dagmc/missing_graveyard.i)

[Mesh]
  [file]
    type = FileMeshGenerator
    file = ../meshes/tet_cube.e
  []

  allow_renumbering = false
  parallel_type = replicated
[]

[Problem]
  type = OpenMCCellAverageProblem
  cell_level = 0
  temperature_blocks = '1'
  power = 1000.0
  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature = temp
    temperature_min = 0.0
    temperature_max = 900.0
    n_temperature_bins = 1
  []
[]

[Executioner]
  type = Steady
[]

(test/tests/neutronics/filters/polar/mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'Polar'
    []
  []

  [Filters]
    [Polar]
      type = PolarAngleFilter
      num_equal_divisions = 2
    []
  []
[]

[Postprocessors]
  [Total_Flux_Theta1]
    type = ElementIntegralVariablePostprocessor
    variable = flux_theta1
  []
  [Total_Flux_Theta2]
    type = ElementIntegralVariablePostprocessor
    variable = flux_theta2
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  csv = true
[]

(tutorials/lwr_solid/openmc_um.i)

[Mesh]
  [file]
    type = FileMeshGenerator
    file = mesh_in.e
  []

  allow_renumbering = false
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = ${fparse 3000e6 / 273 / (17 * 17)}
  temperature_blocks = '1 2 3'
  normalize_by_global_tally = false
  cell_level = 0

  particles = 20000
  inactive_batches = 500
  batches = 10000

  [Tallies]
    [heat_source]
      type = MeshTally
      name = heat_source
    []
  []
[]

[Executioner]
  type = Transient
[]

[Outputs]
  exodus = true
  csv = true
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = heat_source
  []
  [max_tally_rel_err]
    type = TallyRelativeError
  []
  [max_heat_source]
    type = ElementExtremeValue
    variable = heat_source
  []
[]

(test/tests/neutronics/mesh_tally/different_units_and_translations.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere_in_m.e
  []
  [solid1]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []
  [sphereb]
    type = FileMeshGenerator
    file = ../meshes/sphere_in_m.e
  []
  [solid2]
    type = SubdomainIDGenerator
    input = sphereb
    subdomain_id = '200'
  []
  [spherec]
    type = FileMeshGenerator
    file = ../meshes/sphere_in_m.e
  []
  [solid3]
    type = SubdomainIDGenerator
    input = spherec
    subdomain_id = '300'
  []
  [combine]
    type = CombinerGenerator
    inputs = 'solid1 solid2 solid3'
    positions_file = pebble_centers_in_m.txt
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100 200 300'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = false

  # Because the [Mesh] is in units of meters, the mesh translations and mesh template
  # must also be in units of meters
  scaling = 100.0

  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere_in_m.e'
      mesh_translations_file = pebble_centers_in_m.txt
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [kappa_fission]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
  [heat_pebble1]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '100'
  []
  [heat_pebble2]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '200'
  []
  [heat_pebble3]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '300'
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp cell_instance cell_id'
[]

(test/tests/neutronics/dagmc/incompatible_geom/mismatch/openmc.i)

[Mesh]
  [load]
    type = FileMeshGenerator
    file = ../../mesh_tallies/slab.e
  []
  [merge]
    type = RenameBlockGenerator
    input = load
    old_block = '2'
    new_block = '1'
  []

  allow_renumbering = false
  parallel_type = replicated
[]

[Problem]
  type = OpenMCCellAverageProblem

  temperature_blocks = '1'
  cell_level = 0
  power = 100.0

  initial_properties = xml
  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../../mesh_tallies/slab.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = 0.0
    temperature_max = 1000.0
    n_temperature_bins = 4
    temperature = temp
    build_graveyard = true
  []
[]

[Executioner]
  type = Steady
[]

(tutorials/msfr/openmc.i)

[Mesh]
  [mesh]
    type = FileMeshGenerator
    file = msr.e
  []
[]

[ICs]
  [temp]
    type = ConstantIC
    variable = temp
    value = 948.0
  []
  [density]
    type = ConstantIC
    variable = density
    value = ${fparse -0.882*948+4983.6}
  []
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
  [cell_density]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
  [cell_density]
    type = CellDensityAux
    variable = cell_density
  []
  [density]
    type = ParsedAux
    variable = density
    expression = '-0.882*temp+4983.6'
    coupled_variables = temp
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true

  # this will start each Picard iteration from the fission source from the previous one
  reuse_source = true

  scaling = 100.0

  density_blocks = '1'
  temperature_blocks = '1'
  cell_level = 0

  power = 300.0e6

  relaxation = dufek_gudowski
  first_iteration_particles = 5000

  skinner = moab

  [Tallies]
    [heat_source]
      type = MeshTally
      mesh_template = msr.e
      output = unrelaxed_tally_std_dev
    []
  []
[]

nb = 15.0
tmin = 800.0
tmax = 1150.0

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature = temp
    n_temperature_bins = ${nb}
    temperature_min = ${tmin}
    temperature_max = ${tmax}

    density = density
    n_density_bins = ${nb}
    density_min = ${fparse -0.882*tmax+4983.6}
    density_max = ${fparse -0.882*tmin+4983.6}

    build_graveyard = true
    output_skins = true
  []
[]

[MultiApps]
  [nek]
    type = TransientMultiApp
    input_files = 'nek.i'
    sub_cycling = true
    execute_on = timestep_end
  []
[]

[Transfers]
  [temp_to_openmc]
    type = MultiAppGeneralFieldNearestLocationTransfer
    from_multi_app = nek
    variable = temp
    source_variable = temp
  []
  [power_to_nek]
    type = MultiAppGeneralFieldNearestLocationTransfer
    to_multi_app = nek
    source_variable = kappa_fission
    variable = heat_source
  []
  [power_integral_to_nek]
    type = MultiAppPostprocessorTransfer
    to_postprocessor = source_integral
    from_postprocessor = power
    to_multi_app = nek
  []
  [synchronize_in]
    type = MultiAppPostprocessorTransfer
    to_postprocessor = transfer_in
    from_postprocessor = synchronize
    to_multi_app = nek
  []
[]

[Postprocessors]
  [power]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
  [k]
    type = KEigenvalue
  []
  [k_std_dev]
    type = KStandardDeviation
  []
  [max_tally_err]
    type = TallyRelativeError
  []
  [max_T]
    type = ElementExtremeValue
    variable = temp
  []
  [avg_T]
    type = ElementAverageValue
    variable = temp
  []
  [max_q]
    type = ElementExtremeValue
    variable = kappa_fission
  []
  [synchronize]
    type = Receiver
    default = 1.0
  []
[]

t_nek = ${fparse 2e-4 * 7.669}

[Executioner]
  type = Transient
  dt = ${fparse 2000 * t_nek}
[]

[Outputs]
  exodus = true
  csv = true
  hide = 'synchronize'
[]

(test/tests/neutronics/symmetry/wrong_uo.i)

num_layers = 1

channel_diameter = 0.016                 # diameter of the coolant channels (m)
height = 6.343                           # height of the full core (m)

[Mesh]
  [solid]
    type = FileMeshGenerator
    file = solid_mesh_in.e
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  power = 1000.0
  scaling = 100.0
  temperature_blocks = '1 2'
  cell_level = 1

  symmetry_mapper = sym

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = solid_mesh_in.e
    []
  []
[]

[UserObjects]
  [sym]
    type = NearestNodeNumberUO
    point = '0.0 0.0 0.0'
  []
[]

[Executioner]
  type = Steady
[]

(test/tests/neutronics/filters/mesh_sum_gold.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
[]

(test/tests/openmc_errors/mesh_tally/incorrect_scaling.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../neutronics/meshes/sphere_in_m.e
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100'
  initial_properties = xml
  verbose = true
  cell_level = 0

  power = 100.0
  check_tally_sum = false

  scaling = 100.0
  normalize_by_global_tally = false

  [Tallies]
    [Mesh]
      type = MeshTally
      # We incorrectly provide a mesh in units of centimeters
      mesh_template = '../../neutronics/meshes/sphere.e'
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

(test/tests/neutronics/dagmc/mesh_tallies/disjoint_bins.i)

[Mesh]
  type = FileMesh
  file = slab.e
  allow_renumbering = false
  parallel_type = replicated
[]

x0 = 12.5
x1 = 37.5
x2 = 62.5

T0 = 600.0
dT = 50.0

[Functions]
  [temp]
    type = ParsedFunction
    expression = 'if (x <= ${x0}, ${fparse T0 - dT}, if (x <= ${x1}, ${T0}, if (x <= ${x2}, ${fparse T0 - dT}, ${fparse T0 + 2 * dT})))'
  []
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = temp
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true

  temperature_blocks = '1 2'
  cell_level = 0
  power = 100.0

  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = slab.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = ${fparse T0 - dT}
    temperature_max = ${fparse T0 + 2 * dT}
    n_temperature_bins = 4
    temperature = temp
    build_graveyard = true
    output_skins = true
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 2
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/mesh_tally/one_mesh_no_input_file.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = false

  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp cell_instance cell_id'
[]

(test/tests/neutronics/tally_system/multi_mesh_relax.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = axial
    execute_on = initial
  []
[]

[Functions]
  [axial]
    type = ParsedFunction
    expression = '500 + z / 0.10 * 100'
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  relaxation = constant
  relaxation_factor = 0.5

  # The global tally check is disabled because we have a loosely fitting unstructured mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Mesh_1]
      type = MeshTally
      score = kappa_fission
      mesh_translations = '0 0 0'
      mesh_template = ../meshes/sphere.e
    []
    [Mesh_2]
      type = MeshTally
      score = flux
      mesh_translations = '0 0 0'
      mesh_template = ../meshes/sphere.e
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 3
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/relaxation/mesh_tallies/output_fission_tally.i)

[Mesh]
  [pebble]
    type = FileMeshGenerator
    file = ../../meshes/sphere_in_m.e
  []
  [repeat]
    type = CombinerGenerator
    inputs = pebble
    positions = '0 0 0.02
                 0 0 0.06
                 0 0 0.10'
  []
  [set_block_ids]
    type = SubdomainIDGenerator
    input = repeat
    subdomain_id = 0
  []

  allow_renumbering = false
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = axial
    execute_on = initial
  []
[]

[Functions]
  [axial]
    type = ParsedFunction
    expression = '500 + z / 0.10 * 100'
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1500.0
  temperature_blocks = '0'

  cell_level = 1
  scaling = 100.0

  relaxation = constant

  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../../meshes/sphere_in_m.e
      mesh_translations = '0.0 0.0 0.02
                           0.0 0.0 0.06
                           0.0 0.0 0.10'
      output = 'unrelaxed_tally'
    []
  []
[]


[Executioner]
  type = Transient
  num_steps = 3
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/dagmc/no_symmetry.i)

[Mesh]
  [file]
    type = FileMeshGenerator
    file = ../meshes/tet_cube.e
  []

  allow_renumbering = false
  parallel_type = replicated
[]

[Problem]
  type = OpenMCCellAverageProblem
  cell_level = 0
  temperature_blocks = '1'
  power = 1000.0
  skinner = moab
  symmetry_mapper = sym

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../meshes/tet_cube.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature = temp
    temperature_min = 0.0
    temperature_max = 900.0
    n_temperature_bins = 1
    build_graveyard = true
  []
  [sym]
    type = SymmetryPointGenerator
    normal = '1.0 0.0 0.0'
  []
[]

[Executioner]
  type = Steady
[]

(tutorials/tokamak/openmc.i)

[Mesh]
  [file]
    type = FileMeshGenerator
    file = tokamak.e
  []
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  scaling = 100.0

  source_strength = 2e18

  cell_level = 0
  temperature_blocks = 'plasma_facing multiplier breeder divertor vacuum_vessel'

  # this is a low number of particles; you will want to increase in order to obtain
  # high-quality results
  first_iteration_particles = 1000
  relaxation = dufek_gudowski

  skinner = moab

  [Tallies]
    [tokamak]
      type = MeshTally
      mesh_template = tokamak.e
      score = 'heating_local H3_production'
      output = unrelaxed_tally_std_dev
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = 0
    temperature_max = 2000
    n_temperature_bins = 40
    temperature = temp
    build_graveyard = true
    output_skins = true
  []
[]

[Postprocessors]
  [heating]
    type = ElementIntegralVariablePostprocessor
    variable = heating_local
  []
  [tritium_production]
    type = ElementIntegralVariablePostprocessor
    variable = H3_production
  []
  [tritium_error]
    type = TallyRelativeError
    tally_score = H3_production
    value_type = average
  []
  [heating_error]
    type = TallyRelativeError
    tally_score = heating_local
    value_type = average
  []
[]

[Executioner]
  type = Transient
[]

[Outputs]
  exodus = true
  csv = true
[]

(test/tests/neutronics/tally_system/multi_mesh_triggers.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # The global tally check is disabled because we have a loosely fitting unstructured mesh tally.
  normalize_by_global_tally = false

  particles = 100
  max_batches = 200

  [Tallies]
    [Mesh_1]
      type = MeshTally
      score = kappa_fission
      trigger = rel_err
      trigger_threshold = 5e-1
      mesh_translations = '0 0 0'
      mesh_template = ../meshes/sphere.e
    []
    [Mesh_2]
      type = MeshTally
      score = flux
      trigger = rel_err
      trigger_threshold = 5e-1
      mesh_translations = '0 0 0'
      mesh_template = ../meshes/sphere.e
    []
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/filters/azimuthal/mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'Azimuthal'
    []
  []

  [Filters]
    [Azimuthal]
      type = AzimuthalAngleFilter
      num_equal_divisions = 2
    []
  []
[]

[Postprocessors]
  [Total_Flux_Omega1]
    type = ElementIntegralVariablePostprocessor
    variable = flux_omega1
  []
  [Total_Flux_Omega2]
    type = ElementIntegralVariablePostprocessor
    variable = flux_omega2
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  csv = true
[]

(test/tests/neutronics/tally_system/multi_mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # The global tally check is disabled because we have a loosely fitting unstructured mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Mesh_1]
      type = MeshTally
      score = kappa_fission
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      mesh_template = ../meshes/sphere.e
    []
    [Mesh_2]
      type = MeshTally
      score = flux
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      mesh_template = ../meshes/sphere.e
    []
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/mesh_tally/fission_tally_std_dev.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = true

  power = 100.0
  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere.e'
      output = 'unrelaxed_tally_std_dev'
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

[Postprocessors]
  [heat_source_at_pt]
    type = PointValue
    variable = kappa_fission
    point = '0.896826 0.189852 0.608855' # centroid of first element in mesh
  []
  [std_dev_at_pt]
    type = PointValue
    variable = kappa_fission_std_dev
    point = '0.896826 0.189852 0.608855'
  []
[]

[Outputs]
  csv = true
[]

(test/tests/neutronics/tally_system/multi_diff.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  # The global tally check is disabled because we have a loosely fitting unstructured mesh tally.
  normalize_by_global_tally = false

  source_rate_normalization = 'kappa_fission'

  # Missing some hits in the model (only tallying a single pebble instead of 3)
  check_tally_sum = false

  [Tallies]
    [Cell]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Mesh]
      type = MeshTally
      score = 'flux'
      mesh_translations = '0 0 0'
      mesh_template = ../meshes/sphere.e
    []
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/heat_source/multi_tally_mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  power = 100.0
  particles = 1000.0
  temperature_blocks = '100'
  verbose = true
  cell_level = 0

  check_tally_sum = false

  initial_properties = xml

  [Tallies]
    [Mesh]
      type = MeshTally
      score = 'kappa_fission heating'
      mesh_template = ../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

[Postprocessors]
  [kappa_fission]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
  [heating]
    type = ElementIntegralVariablePostprocessor
    variable = heating
  []
[]

[Outputs]
  csv = true
[]

(test/tests/neutronics/mesh_tally/multiple_meshes_global.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid1]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []
  [sphereb]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid2]
    type = SubdomainIDGenerator
    input = sphereb
    subdomain_id = '200'
  []
  [spherec]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid3]
    type = SubdomainIDGenerator
    input = spherec
    subdomain_id = '300'
  []
  [combine]
    type = CombinerGenerator
    inputs = 'solid1 solid2 solid3'
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100 200 300'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = true

  power = 100.0
  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere.e'
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [kappa_fission]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
  [heat_pebble1]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '100'
  []
  [heat_pebble2]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '200'
  []
  [heat_pebble3]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '300'
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp  cell_instance cell_id'
[]

(test/tests/neutronics/filters/xml/mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  check_tally_sum = false
  normalize_by_global_tally = true

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'SPH_XML'
    []
  []

  [Filters]
    [SPH_XML]
      type = FromXMLFilter
      filter_id = 1
      bin_label = 'sph'
      allow_expansion_filters = true
    []
  []
[]

[Postprocessors]
  [Total_Flux_l0_m0]
    type = ElementIntegralVariablePostprocessor
    variable = flux_sph1
  []
  [Total_Flux_l1_mn1]
    type = ElementIntegralVariablePostprocessor
    variable = flux_sph2
  []
  [Total_Flux_l1_m0]
    type = ElementIntegralVariablePostprocessor
    variable = flux_sph3
  []
  [Total_Flux_l1_m1]
    type = ElementIntegralVariablePostprocessor
    variable = flux_sph4
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  csv = true
[]

(test/tests/neutronics/mesh_tally/multiple_meshes.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid1]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []
  [sphereb]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid2]
    type = SubdomainIDGenerator
    input = sphereb
    subdomain_id = '200'
  []
  [spherec]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid3]
    type = SubdomainIDGenerator
    input = spherec
    subdomain_id = '300'
  []
  [combine]
    type = CombinerGenerator
    inputs = 'solid1 solid2 solid3'
    positions_file = pebble_centers.txt
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100 200 300'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = false

  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_translations_file = pebble_centers.txt
      mesh_template = '../meshes/sphere.e'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [kappa_fission]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
  [heat_pebble1]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '100'
  []
  [heat_pebble2]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '200'
  []
  [heat_pebble3]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
    block = '300'
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp  cell_instance cell_id'
[]

(test/tests/neutronics/filters/energy/mesh_sum.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'Energy'
    []
  []

  [Filters]
    [Energy]
      type = EnergyFilter
      # CASMO 2 group structure for testing. May result in some missed particles
      energy_boundaries = '0.0 6.25e-1 2.0e7'
    []
  []
[]

[AuxVariables]
  [flux]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [total_flux]
    type = SumAux
    variable = flux
    values = 'flux_g1 flux_g2'
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
  hide = 'flux_g1 flux_g2'
[]

(test/tests/neutronics/mesh_tally/one_mesh.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100'
  initial_properties = xml
  verbose = true
  cell_level = 0
  normalize_by_global_tally = false

  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere.e'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp'
[]

(test/tests/neutronics/mesh_tally/different_units.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere_in_m.e
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '100'
  initial_properties = xml
  verbose = true
  cell_level = 0

  power = 100.0

  # the [Mesh] is in units of meters, so the mesh_template must also be in units of meters
  scaling = 100.0

  normalize_by_global_tally = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere_in_m.e'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Postprocessors]
  [kappa_fission]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
[]

[Outputs]
  execute_on = final
  exodus = true
  hide = 'temp  cell_instance cell_id'
[]

(test/tests/openmc_errors/mesh_tally/incorrect_order.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../neutronics/meshes/sphere.e
  []
  [combine]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [block]
    type = SubdomainIDGenerator
    input = combine
    subdomain_id = '0'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '0'
  initial_properties = xml
  verbose = true
  cell_level = 0

  power = 100.0
  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../../neutronics/meshes/sphere.e'
      # Make the mistake of listing the mesh template translations in a different order than
      # was used to create the [Mesh]. This should catch that the mesh template does not
      # exactly match the [Mesh]
      mesh_translations = '0 0 0
      0 0 8
      0 0 4'
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

(test/tests/neutronics/triggers/mesh_tally_rel_err.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 100.0
  normalize_by_global_tally = false

  particles = 1000
  max_batches = 200

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = '../meshes/sphere.e'
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      trigger = rel_err
      trigger_threshold = 5e-1
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

[Postprocessors]
  [max_tally_err]
    type = TallyRelativeError
  []
[]

[Outputs]
  csv = true
[]

(tutorials/pebbles/openmc_um.i)

[Mesh]
  [pebble]
    type = FileMeshGenerator
    file = mesh_in.e
  []
  [repeat]
    type = CombinerGenerator
    inputs = pebble
    positions = '0 0 0.02
                 0 0 0.06
                 0 0 0.10'
  []

  allow_renumbering = false
[]


[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1500.0
  temperature_blocks = '0'
  normalize_by_global_tally = false
  cell_level = 1
  scaling = 100.0

  [Tallies]
    [heat_source]
      type = MeshTally
      mesh_translations = '0 0 0.02
                           0 0 0.06
                           0 0 0.10'
      mesh_template = mesh_in.e
      name = heat_source
    []
  []
[]

[Executioner]
  type = Transient
[]

[Outputs]
  exodus = true
  csv = true
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = heat_source
  []
  [max_tally_rel_err]
    type = TallyRelativeError
  []
  [k]
    type = KEigenvalue
  []
[]

(test/tests/neutronics/feedback/lattice/non_material_fluid.i)

[Mesh]
  type = FileMesh
  file = ../../meshes/pincell.e
  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  power = 500.0

  temperature_blocks = '2'
  density_blocks = '2'

  cell_level = 0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../../meshes/pincell.e
    []
  []
[]

[Executioner]
  type = Transient
[]

[Outputs]
  exodus = true
[]

(test/tests/openmc_errors/mesh_tally/incorrect_file.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../neutronics/meshes/sphere.e
  []
  [block]
    type = SubdomainIDGenerator
    input = sphere
    subdomain_id = '0'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  temperature_blocks = '0'
  initial_properties = xml
  verbose = true
  cell_level = 0

  power = 100.0
  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      # make the mistake of clearly using a totally different mesh
      mesh_template = '../../neutronics/meshes/pincell.e'
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 1
[]

(tutorials/dagmc/openmc.i)

[Mesh]
  [file]
    type = FileMeshGenerator
    file = mesh_in.e
  []

  allow_renumbering = false
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  cell_level = 0
  temperature_blocks = '2 3'
  check_tally_sum = false
  normalize_by_global_tally = false

  power = 1000.0
  volume_calculation = vol

  [Tallies]
    [heat_source]
      type = MeshTally
      mesh_template = mesh_in.e
      name = heat_source
    []
  []
[]

[UserObjects]
  [vol]
    type = OpenMCVolumeCalculation
    n_samples = 200000
  []
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = heat_source
  []
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
[]

[Outputs]
  exodus = true
  csv = true
[]

(test/tests/neutronics/filters/azimuthal/mesh_sum.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = ../../meshes/sphere.e
  []
  [solid]
    type = CombinerGenerator
    inputs = sphere
    positions = '0 0 0
                 0 0 4
                 0 0 8'
  []
  [solid_ids]
    type = SubdomainIDGenerator
    input = solid
    subdomain_id = '100'
  []

  allow_renumbering = false
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  # Disable global normalization since we have a loosely fitting mesh tally.
  normalize_by_global_tally = false

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      blocks = '100'
    []
    [Flux]
      type = MeshTally
      score = 'flux'
      mesh_template = ../../meshes/sphere.e
      mesh_translations = '0 0 0
                           0 0 4
                           0 0 8'
      filters = 'Azimuthal'
    []
  []

  [Filters]
    [Azimuthal]
      type = AzimuthalAngleFilter
      num_equal_divisions = 2
    []
  []
[]

[AuxVariables]
  [flux]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [total_flux]
    type = SumAux
    variable = flux
    values = 'flux_omega1 flux_omega2'
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  exodus = true
  hide = 'flux_omega1 flux_omega2'
[]

(test/tests/neutronics/dagmc/mesh_tallies/openmc.i)

[Mesh]
  type = FileMesh
  file = slab.e
  allow_renumbering = false
[]

x0 = 12.5
x1 = 37.5
x2 = 62.5

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

T0 = 600.0
dT = 50.0

[Functions]
  [temp]
    type = ParsedFunction
    expression = 'if (x <= ${x0}, ${fparse T0 - dT}, if (x <= ${x1}, ${T0}, if (x <= ${x2}, ${fparse T0 + dT}, ${fparse T0 + 2 * dT})))'
  []
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = temp
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true

  temperature_blocks = '1 2'
  cell_level = 0
  power = 100.0

  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = slab.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = ${fparse T0 - dT}
    temperature_max = ${fparse T0 + 2 * dT}
    n_temperature_bins = 4
    temperature = temp
    build_graveyard = true
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 2
[]

[Outputs]
  exodus = true
[]

(test/tests/neutronics/dagmc/incompatible_geom/has_csg/openmc.i)

[Mesh]
  type = FileMesh
  file = ../../mesh_tallies/slab.e
  allow_renumbering = false
  parallel_type = replicated
[]

[Problem]
  type = OpenMCCellAverageProblem
  initial_properties = xml
  power = 100.0
  cell_level = 0
  temperature_blocks = '1 2'
  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../../mesh_tallies/slab.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature = temp
    n_temperature_bins = 2
    temperature_min = 0.0
    temperature_max = 1000.0
  []
[]

[Executioner]
  type = Steady
[]

(test/tests/neutronics/dagmc/mesh_tallies/csg_step_1/openmc.i)

[Mesh]
  type = FileMesh
  file = ../slab.e
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
  [material_id]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
  [material_id]
    type = CellMaterialIDAux
    variable = material_id
  []
[]

[AuxKernels]
  [temp]
    type = ConstantAux
    variable = temp
    value = 500.0
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true

  temperature_blocks = '1 2'
  cell_level = 0
  power = 100.0

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../slab.e
    []
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 2
[]

[Outputs]
  exodus = true
[]

(doc/content/source/actions/multi_tally_example.i)

[Mesh]
  [sphere]
    type = FileMeshGenerator
    file = mesh_in.e
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  particles = 10000
  inactive_batches = 100
  batches = 1000
  initial_properties = xml
  verbose = true
  cell_level = 0

  normalize_by_global_tally = true
  check_tally_sum = true

  power = 100.0

  source_rate_normalization = 'heating_local'

  [Tallies]
    [Mesh_Tally]
      type = MeshTally
      score = 'flux'
    []
    [Cell_Tally]
      type = CellTally
      score = 'heating_local'
    []
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  execute_on = final
  exodus = true
[]

(test/tests/neutronics/dagmc/mesh_tallies/one_bin.i)

[Mesh]
  type = FileMesh
  file = slab.e
  allow_renumbering = false
[]

[AuxVariables]
  [cell_temperature]
    family = MONOMIAL
    order = CONSTANT
  []
[]

[AuxKernels]
  [cell_temperature]
    type = CellTemperatureAux
    variable = cell_temperature
  []
[]

[AuxKernels]
  [temp]
    type = ConstantAux
    variable = temp
    value = 500.0
    execute_on = timestep_begin
  []
[]

[Problem]
  type = OpenMCCellAverageProblem

  temperature_blocks = '1 2'
  cell_level = 0
  power = 100.0

  skinner = moab

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = slab.e
    []
  []
[]

[UserObjects]
  [moab]
    type = MoabSkinner
    temperature_min = 0.0
    temperature_max = 1000.0
    n_temperature_bins = 1
    temperature = temp
    build_graveyard = true
  []
[]

[Postprocessors]
  [k]
    type = KEigenvalue
  []
[]

[Executioner]
  type = Transient
  num_steps = 2
[]

[Outputs]
  exodus = true
  hide = 'temp cell_instance'
[]

(test/tests/neutronics/relaxation/mesh_tallies/openmc.i)

[Mesh]
  [pebble]
    type = FileMeshGenerator
    file = ../../meshes/sphere_in_m.e
  []
  [repeat]
    type = CombinerGenerator
    inputs = pebble
    positions = '0 0 0.02
                 0 0 0.06
                 0 0 0.10'
  []
  [set_block_ids]
    type = SubdomainIDGenerator
    input = repeat
    subdomain_id = 0
  []

  allow_renumbering = false
[]

[AuxKernels]
  [temp]
    type = FunctionAux
    variable = temp
    function = axial
    execute_on = initial
  []
[]

[Functions]
  [axial]
    type = ParsedFunction
    expression = '500 + z / 0.10 * 100'
  []
[]

[Problem]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1500.0
  temperature_blocks = '0'

  cell_level = 1
  scaling = 100.0

  check_tally_sum = false

  [Tallies]
    [Mesh]
      type = MeshTally
      mesh_template = ../../meshes/sphere_in_m.e
      mesh_translations = '0.0 0.0 0.02
                           0.0 0.0 0.06
                           0.0 0.0 0.10'
    []
  []
[]

[Executioner]
  type = Transient
  num_steps = 3
[]

[Outputs]
  exodus = true
[]

[Postprocessors]
  [heat_source]
    type = ElementIntegralVariablePostprocessor
    variable = kappa_fission
  []
[]

Description
Example Input File Syntax
Input Parameters
Input Files