bluemira.radiation_transport.neutronics.geometry

dataclasses containing parameters used to set up the openmc model.

Classes

`BlanketThickness`	Give the depth of the interfaces between blanket layers.
`DivertorThickness`	Divertor dimensions.
`ToroidalFieldCoilDimension`	Gives the toroidal field coil diameters. Working with the simplest assumption, we
`RadiationShieldThickness`	Radiation shield dimensions.
`TokamakDimensions`	The dimensions of the simplest axis-symmetric case of the tokamak.

Module Contents

class bluemira.radiation_transport.neutronics.geometry.BlanketThickness

Give the depth of the interfaces between blanket layers.

Parameters:

surface – Thickness of the surface layer of the blanket. Can be zero. Only used for tallying purpose, i.e. not a physical component.
first_wall – Thickness of the first wall.
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.

surface: float

first_wall: float

breeding_zone: float

manifold: float

get_interface_depths()

Depth of at each interface layers = the thickness of all the layers before it.

Returns:: Depths of the interface between layers.

class bluemira.radiation_transport.neutronics.geometry.DivertorThickness

Divertor dimensions. For now it only has 1 value: the surface layer thickness.

Parameters:: 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.

surface: float

class bluemira.radiation_transport.neutronics.geometry.ToroidalFieldCoilDimension

Gives the toroidal field coil diameters. Working with the simplest assumption, we assume that the tf coil is circular for now.

Parameters:

inner_diameter – (i.e. inner diameter of the windings.)
outer_diameter – Outer diameter of the windings.

thickness: float

inner_radius: float

class bluemira.radiation_transport.neutronics.geometry.RadiationShieldThickness

Radiation shield dimensions. For now it only has 1 value: the wall layer thickness.

Parameters:: wall – The wall thickness of the radiation shield.

wall: float

class bluemira.radiation_transport.neutronics.geometry.TokamakDimensions

The dimensions of the simplest axis-symmetric case of the tokamak.

Parameters:

inboard – thicknesses of the inboard blanket
outboard – thicknesses of the outboard blanket
divertor – thicknesses of the divertor components
cs_coil – diameters of the toroidal field coil in the

inboard: BlanketThickness

inboard_outboard_transition_radius: float

outboard: BlanketThickness

divertor: DivertorThickness

cs_coil: ToroidalFieldCoilDimension

rad_shield: RadiationShieldThickness

classmethod from_parameterframe(params: bluemira.radiation_transport.neutronics.neutronics_axisymmetric.NeutronicsReactorParameterFrame, r_inner_cut: float)

Setup tokamak dimensions

Parameters:

params (bluemira.radiation_transport.neutronics.neutronics_axisymmetric.NeutronicsReactorParameterFrame) – parameter frame containing all the relevant thickness parameters
r_inner_cut (float) – 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.