DelayedGroupFilter

Description

The DelayedGroupFilter object provides a thin wrapper around an OpenMC DelayedGroupFilter which local tallies (added through the tally system) can access. The delayed groups tallied over can be specified by setting dnp_groups. Presently, only the ENDF delayed group structure is supported; valid groups are therefore 1, 2, 3, 4, 5, and 6.

Example Input File Syntax

As an example, a CellTally named DNP applies an DelayedGroupFilter named Delayed to break up the decay rate and delayed neutron source term into the ENDF six group structure.

[Problem<<<{"href": "../../syntax/Problem/index.html"}>>>]
  type = OpenMCCellAverageProblem
  verbose = true
  power = 1e4
  temperature_blocks = '100'
  cell_level = 0
  initial_properties = xml

  source_rate_normalization = 'kappa_fission'

  [Tallies<<<{"href": "../../syntax/Problem/Tallies/index.html"}>>>]
    [Heating]
      type = CellTally<<<{"description": "A class which implements distributed cell tallies.", "href": "../tallies/CellTally.html"}>>>
      score<<<{"description": "Score(s) to use in the OpenMC tallies. If not specified, defaults to 'kappa_fission'"}>>> = 'kappa_fission'
      block<<<{"description": "Subdomains for which to add tallies in OpenMC. If not provided, tallies will be applied over the entire domain corresponding to the [Mesh] block."}>>> = '100 200'
    []
    [DNP]
      type = CellTally<<<{"description": "A class which implements distributed cell tallies.", "href": "../tallies/CellTally.html"}>>>
      score<<<{"description": "Score(s) to use in the OpenMC tallies. If not specified, defaults to 'kappa_fission'"}>>> = 'delayed_nu_fission decay_rate'
      block<<<{"description": "Subdomains for which to add tallies in OpenMC. If not provided, tallies will be applied over the entire domain corresponding to the [Mesh] block."}>>> = '100 200'
      filters<<<{"description": "External filters to add to this tally."}>>> = 'Delayed'
    []
  []

  [Filters<<<{"href": "../../syntax/Problem/Filters/index.html"}>>>]
    [Delayed]
      type = DelayedGroupFilter<<<{"description": "A class which provides a thin wrapper around an OpenMC DelayedGroupFilter.", "href": "DelayedGroupFilter.html"}>>>
      dnp_groups<<<{"description": "The delayed neutron precursor bins to filter for. Valid bin indices are integers between 1 and 6 (inclusive)."}>>> = '1 2 3 4 5 6'
    []
  []
[]

Input Parameters

dnp_groupsThe delayed neutron precursor bins to filter for. Valid bin indices are integers between 1 and 6 (inclusive).
C++ Type:std::vector<int>
Controllable:No
Description:The delayed neutron precursor bins to filter for. Valid bin indices are integers between 1 and 6 (inclusive).

Required 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

(cardinal/test/tests/neutronics/filters/delayed/cell.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'
  []
  [fluid]
    type = FileMeshGenerator
    file = ../../heat_source/stoplight.exo
  []
  [fluid_ids]
    type = SubdomainIDGenerator
    input = fluid
    subdomain_id = '200'
  []
  [combine]
    type = CombinerGenerator
    inputs = 'solid_ids fluid_ids'
  []

  allow_renumbering = false
[]

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

  source_rate_normalization = 'kappa_fission'

  [Tallies]
    [Heating]
      type = CellTally
      score = 'kappa_fission'
      block = '100 200'
    []
    [DNP]
      type = CellTally
      score = 'delayed_nu_fission decay_rate'
      block = '100 200'
      filters = 'Delayed'
    []
  []

  [Filters]
    [Delayed]
      type = DelayedGroupFilter
      dnp_groups = '1 2 3 4 5 6'
    []
  []
[]

[Postprocessors]
  [Pebble_1_DFiss_1]
    type = PointValue
    point = '0 0 0'
    variable = delayed_nu_fission_d1
  []
  [Pebble_1_DFiss_2]
    type = PointValue
    point = '0 0 0'
    variable = delayed_nu_fission_d2
  []
  [Pebble_1_DFiss_3]
    type = PointValue
    point = '0 0 0'
    variable = delayed_nu_fission_d3
  []
  [Pebble_1_DFiss_4]
    type = PointValue
    point = '0 0 0'
    variable = delayed_nu_fission_d4
  []
  [Pebble_1_DFiss_5]
    type = PointValue
    point = '0 0 0'
    variable = delayed_nu_fission_d5
  []
  [Pebble_1_DFiss_6]
    type = PointValue
    point = '0 0 0'
    variable = delayed_nu_fission_d6
  []

  [Pebble_1_DRate_1]
    type = PointValue
    point = '0 0 0'
    variable = decay_rate_d1
  []
  [Pebble_1_DRate_2]
    type = PointValue
    point = '0 0 0'
    variable = decay_rate_d2
  []
  [Pebble_1_DRate_3]
    type = PointValue
    point = '0 0 0'
    variable = decay_rate_d3
  []
  [Pebble_1_DRate_4]
    type = PointValue
    point = '0 0 0'
    variable = decay_rate_d4
  []
  [Pebble_1_DRate_5]
    type = PointValue
    point = '0 0 0'
    variable = decay_rate_d5
  []
  [Pebble_1_DRate_6]
    type = PointValue
    point = '0 0 0'
    variable = decay_rate_d6
  []
[]

[Executioner]
  type = Steady
[]

[Outputs]
  execute_on = 'TIMESTEP_END'
  csv = true
[]

Description
Example Input File Syntax
Input Parameters