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187 lines
3.4 KiB
ReStructuredText
187 lines
3.4 KiB
ReStructuredText
------------------------------------
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:mod:`openmc` -- Basic Functionality
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------------------------------------
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Handling nuclear data
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---------------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.XSdata
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openmc.MGXSLibrary
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Simulation Settings
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-------------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Source
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openmc.VolumeCalculation
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openmc.Settings
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Material Specification
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----------------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Nuclide
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openmc.Element
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openmc.Macroscopic
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openmc.Material
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openmc.Materials
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Cross sections for nuclides, elements, and materials can be plotted using the
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following function:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myfunction.rst
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openmc.plot_xs
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Building geometry
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-----------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Plane
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openmc.XPlane
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openmc.YPlane
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openmc.ZPlane
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openmc.XCylinder
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openmc.YCylinder
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openmc.ZCylinder
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openmc.Sphere
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openmc.Cone
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openmc.XCone
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openmc.YCone
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openmc.ZCone
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openmc.Quadric
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openmc.Halfspace
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openmc.Intersection
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openmc.Union
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openmc.Complement
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openmc.Cell
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openmc.Universe
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openmc.RectLattice
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openmc.HexLattice
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openmc.Geometry
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Many of the above classes are derived from several abstract classes:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Surface
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openmc.Region
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openmc.Lattice
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.. _pythonapi_tallies:
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Constructing Tallies
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--------------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Filter
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openmc.UniverseFilter
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openmc.MaterialFilter
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openmc.CellFilter
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openmc.CellFromFilter
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openmc.CellbornFilter
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openmc.SurfaceFilter
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openmc.MeshFilter
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openmc.MeshSurfaceFilter
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openmc.EnergyFilter
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openmc.EnergyoutFilter
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openmc.MuFilter
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openmc.PolarFilter
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openmc.AzimuthalFilter
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openmc.DistribcellFilter
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openmc.DelayedGroupFilter
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openmc.EnergyFunctionFilter
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openmc.Mesh
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openmc.Trigger
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openmc.TallyDerivative
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openmc.Tally
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openmc.Tallies
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Coarse Mesh Finite Difference Acceleration
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------------------------------------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.CMFDMesh
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openmc.CMFD
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Geometry Plotting
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-----------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Plot
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openmc.Plots
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Running OpenMC
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--------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myfunction.rst
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openmc.run
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openmc.calculate_volumes
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openmc.plot_geometry
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openmc.plot_inline
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openmc.search_for_keff
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Post-processing
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---------------
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.Particle
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openmc.StatePoint
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openmc.Summary
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Various classes may be created when performing tally slicing and/or arithmetic:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.arithmetic.CrossScore
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openmc.arithmetic.CrossNuclide
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openmc.arithmetic.CrossFilter
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openmc.arithmetic.AggregateScore
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openmc.arithmetic.AggregateNuclide
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openmc.arithmetic.AggregateFilter
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