------------------------------------ :mod:`openmc` -- Basic Functionality ------------------------------------ Handling nuclear data --------------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.XSdata openmc.MGXSLibrary Simulation Settings ------------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Source openmc.VolumeCalculation openmc.Settings Material Specification ---------------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Nuclide openmc.Element openmc.Macroscopic openmc.Material openmc.Materials Cross sections for nuclides, elements, and materials can be plotted using the following function: .. autosummary:: :toctree: generated :nosignatures: :template: myfunction.rst openmc.plot_xs Building geometry ----------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Plane openmc.XPlane openmc.YPlane openmc.ZPlane openmc.XCylinder openmc.YCylinder openmc.ZCylinder openmc.Sphere openmc.Cone openmc.XCone openmc.YCone openmc.ZCone openmc.Quadric openmc.Halfspace openmc.Intersection openmc.Union openmc.Complement openmc.Cell openmc.Universe openmc.RectLattice openmc.HexLattice openmc.Geometry Many of the above classes are derived from several abstract classes: .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Surface openmc.Region openmc.Lattice .. _pythonapi_tallies: Constructing Tallies -------------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Filter openmc.UniverseFilter openmc.MaterialFilter openmc.CellFilter openmc.CellFromFilter openmc.CellbornFilter openmc.SurfaceFilter openmc.MeshFilter openmc.MeshSurfaceFilter openmc.EnergyFilter openmc.EnergyoutFilter openmc.MuFilter openmc.PolarFilter openmc.AzimuthalFilter openmc.DistribcellFilter openmc.DelayedGroupFilter openmc.EnergyFunctionFilter openmc.LegendreFilter openmc.SpatialLegendreFilter openmc.SphericalHarmonicsFilter openmc.ZernikeFilter openmc.ZernikeRadialFilter openmc.ParticleFilter openmc.Mesh openmc.Trigger openmc.TallyDerivative openmc.Tally openmc.Tallies Geometry Plotting ----------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Plot openmc.Plots Running OpenMC -------------- .. autosummary:: :toctree: generated :nosignatures: :template: myfunction.rst openmc.run openmc.calculate_volumes openmc.plot_geometry openmc.plot_inline openmc.search_for_keff Post-processing --------------- .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.Particle openmc.StatePoint openmc.Summary The following classes and functions are used for functional expansion reconstruction. .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.ZernikeRadial .. autosummary:: :toctree: generated :nosignatures: :template: myfunction.rst openmc.legendre_from_expcoef Various classes may be created when performing tally slicing and/or arithmetic: .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.arithmetic.CrossScore openmc.arithmetic.CrossNuclide openmc.arithmetic.CrossFilter openmc.arithmetic.AggregateScore openmc.arithmetic.AggregateNuclide openmc.arithmetic.AggregateFilter Coarse Mesh Finite Difference Acceleration ------------------------------------------ CMFD is implemented in OpenMC and allows users to accelerate fission source convergence during inactive neutron batches. To run CMFD, the CMFDRun class should be used. .. autosummary:: :toctree: generated :nosignatures: :template: myclass.rst openmc.CMFDMesh openmc.CMFDRun At the minimum, a CMFD mesh needs to be specified in order to run CMFD. Once these properties are set, an OpenMC simulation can be run with CMFD turned on with the function: .. autosummary:: :toctree: generated :nosignatures: :template: myfunction.rst openmc.CMFDRun.run