- azimuthal_angle_boundariesThe azimuthal angle boundaries in $[-\pi, \pi)$ which must be provided in increasing order. If $-\pi$ and $\pi$ are not included this filter may result in some missed particles during normalization.
C++ Type:std::vector<double>
Unit:(no unit assumed)
Controllable:No
Description:The azimuthal angle boundaries in $[-\pi, \pi)$ which must be provided in increasing order. If $-\pi$ and $\pi$ are not included this filter may result in some missed particles during normalization.
- num_equal_divisionsThe number of equally spaces subdivisions of $[-\pi, \pi)$ to use if equal subdivisions are desired.
C++ Type:unsigned int
Controllable:No
Description:The number of equally spaces subdivisions of $[-\pi, \pi)$ to use if equal subdivisions are desired.
AzimuthalAngleFilter
AzimuthalAngleFilter
can only be added to problems when the input file contains a OpenMCCellAverageProblem in the [Problem]
block. Otherwise, attempting to add this filter will result in an error.
Description
The AzimuthalAngleFilter
object provides a thin wrapper around an OpenMC AzimuthalFilter which local tallies (added through the tally system) can access. Two bin options are available; equally spaced bins (setting num_equal_divisions
) or custom bins (setting azimuthal_angle_boundaries
).
Example Input File Syntax
As an example, a MeshTally named Flux
applies an AzimuthalAngleFilter
named Azimuthal
to break the total flux up into two hemispheres.
[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'
# Disable global normalization since we have a loosely fitting mesh tally.
normalize_by_global_tally = false
[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, cell tallies will be applied over the entire mesh."}>>> = '100'
[]
[Flux]
type = MeshTally<<<{"description": "A class which implements unstructured mesh tallies.", "href": "../tallies/MeshTally.html"}>>>
score<<<{"description": "Score(s) to use in the OpenMC tallies. If not specified, defaults to 'kappa_fission'"}>>> = 'flux'
mesh_template<<<{"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]."}>>> = ../../meshes/sphere.e
mesh_translations = '0 0 0
0 0 4
0 0 8'
filters<<<{"description": "External filters to add to this tally."}>>> = 'Azimuthal'
[]
[]
[Filters<<<{"href": "../../syntax/Problem/Filters/index.html"}>>>]
[Azimuthal]
type = AzimuthalAngleFilter<<<{"description": "A class which provides a thin wrapper around an OpenMC AzimuthalFilter. Bins can either be equally spaced by setting 'num_equal_divisions', or a set of azimuthal angles can be provided by setting 'azimuthal_angle_boundaries'.", "href": "AzimuthalAngleFilter.html"}>>>
num_equal_divisions<<<{"description": "The number of equally spaces subdivisions of $[-\\pi, \\pi)$ to use if equal subdivisions are desired."}>>> = 2
[]
[]
[]
(cardinal/test/tests/neutronics/filters/azimuthal/mesh.i)Input 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.