bluemira.radiation_transport.neutronics.geometry ================================================ .. py:module:: bluemira.radiation_transport.neutronics.geometry .. autoapi-nested-parse:: dataclasses containing parameters used to set up the openmc model. Classes ------- .. autoapisummary:: bluemira.radiation_transport.neutronics.geometry.BlanketThickness bluemira.radiation_transport.neutronics.geometry.DivertorThickness bluemira.radiation_transport.neutronics.geometry.ToroidalFieldCoilDimension bluemira.radiation_transport.neutronics.geometry.RadiationShieldThickness bluemira.radiation_transport.neutronics.geometry.TokamakDimensions Module Contents --------------- .. py:class:: BlanketThickness Give the depth of the interfaces between blanket layers. :param surface: Thickness of the surface layer of the blanket. Can be zero. Only used for tallying purpose, i.e. not a physical component. :param first_wall: Thickness of the first wall. :param breeding_zone: Thickness of the breedng zone. Could be zero if the breeding zone is absent. .. note:: Thickness of the vacuum vessel is not required because we we assume it fills up the remaining space between the manifold's end and the outer_boundary. .. py:attribute:: surface :type: float .. py:attribute:: first_wall :type: float .. py:attribute:: breeding_zone :type: float .. py:attribute:: manifold :type: float .. py:method:: get_interface_depths() Depth of at each interface layers = the thickness of all the layers before it. :returns: Depths of the interface between layers. .. py:class:: DivertorThickness Divertor dimensions. For now it only has 1 value: the surface layer thickness. :param surface: The surface layer of the divertor, which we expect to be made of a different material (e.g. Tungsten or alloy of Tungsten) from the bulk support & cooling structures of the divertor. .. py:attribute:: surface :type: float .. py:class:: ToroidalFieldCoilDimension Gives the toroidal field coil diameters. Working with the simplest assumption, we assume that the tf coil is circular for now. :param inner_diameter: (i.e. inner diameter of the windings.) :param outer_diameter: Outer diameter of the windings. .. py:attribute:: thickness :type: float .. py:attribute:: inner_radius :type: float .. py:class:: RadiationShieldThickness Radiation shield dimensions. For now it only has 1 value: the wall layer thickness. :param wall: The wall thickness of the radiation shield. .. py:attribute:: wall :type: float .. py:class:: TokamakDimensions The dimensions of the simplest axis-symmetric case of the tokamak. :param inboard: thicknesses of the inboard blanket :param outboard: thicknesses of the outboard blanket :param divertor: thicknesses of the divertor components :param cs_coil: diameters of the toroidal field coil in the .. py:attribute:: inboard :type: BlanketThickness .. py:attribute:: inboard_outboard_transition_radius :type: float .. py:attribute:: outboard :type: BlanketThickness .. py:attribute:: divertor :type: DivertorThickness .. py:attribute:: cs_coil :type: ToroidalFieldCoilDimension .. py:attribute:: rad_shield :type: RadiationShieldThickness .. py:method:: from_parameterframe(params: bluemira.radiation_transport.neutronics.neutronics_axisymmetric.NeutronicsReactorParameterFrame, r_inner_cut: float) :classmethod: Setup tokamak dimensions :param params: parameter frame containing all the relevant thickness parameters :param r_inner_cut: Major radius value beyond which it's considered the "outboard", and within which it's considered the inboard part of the tokamak. :returns: TokamakDimensions object with the appropriate dimensions extracted from params.