Neutronics make_csg tests

[OceanNuclear]

Tests required for bluemira/codes/openmc/make_csg.py

• [ ] is_monotonically_increasing
• [x] plot_surfaces
• [x] plot_surface_at_1000cm
• [ ] get_depth_values
• [ ] check_inboard_outboard
• [ ] torus_from_3points
• [ ] torus_from_circle
• [ ] z_torus
• [ ] choose_halfspace
• [ ] choose_plane_cylinders
• [ ] (Will need to add a new class/function to enforce CNF, i.e. conjunctive normal form, to minimize the amount of checks required per expression)
  • [ ] flat_intersection
  • [ ] intersection_dictionary
  • [ ] flat_union
  • [ ] union_dictionary
• [ ] round_up_next_openmc_ids
• [ ] exterior_vertices
• [ ] interior_vertices
• [ ] make_universe_box
• [ ] make_radiation_shield_box
• [ ] make_coils
• [ ] make_dividing_surface
• [ ] blanket_and_divertor_outer_regions
• [ ] plasma_void
• [ ] make_void_cells
• [ ] make_cell_arrays
• [ ] BluemiraNeutronicsCSG (should be renamed to OpenMCEnvironment later)
• [ ] BlanketCell (only testing that __init__ errors when the vertices are mis-ordered)
• [ ] BlanketCellStack
• [ ] BlanketCellArray
• [ ] DivertorCell
• [ ] DivertorCellStack
• [ ] DivertorCellArray

This is just one file, other files/functions in bluemira/codes/openmc/ that may need testing includes:

• [ ] tallying.py - needs to be broken down into more functions
• [ ] source.py::create_ring_source and source.py::make_ring_source
• [x] solver.py
• [ ] params.py::minor_radius
• [x] materials.py