Refactor discussion about openmc-dagmc-wrapper HOT 8 OPEN

    def checks(self, h5m_filename):
        materials_in_h5m = di.get_materials_from_h5m(h5m_filename)
        # # checks all the required materials are present
        for reactor_material in self.correspondence_dict.keys():
            if reactor_material not in materials_in_h5m:
                msg = (
                    f"material with tag {reactor_material} was not found in "
                    f"the dagmc h5m file. The DAGMC file {h5m_filename} "
                    f"contains the following material tags {materials_in_h5m}."
                )
                raise ValueError(msg)

        if "graveyard" in materials_in_h5m:
            required_nb_of_materials = len(materials_in_h5m) - 1
        else:
            required_nb_of_materials = len(materials_in_h5m)

        if required_nb_of_materials != len(self.correspondence_dict.keys()):
            msg = (
                f"the number of materials provided in the correspondence_dict "
                f"{len(self.correspondence_dict.keys())} "
                f"is not equal to the number of materials specified in the "
                f"DAGMC h5m file {required_nb_of_materials}"
            )
            raise ValueError(msg)

        silently_remove_file("materials.xml")

h5m_filename = "neutronics_workflow-0.0.2/example_02_multi_volume_cell_tally/stage_2_output/dagmc.h5m"


geometry = odw.Geometry(h5m_filename=h5m_filename)

materials = odw.Materials(
    correspondence_dict={
        "blanket_mat": "Li4SiO4",
        "blanket_rear_wall_mat": "Be",
        "center_column_shield_mat": "Be",
        "divertor_mat": "Be",
        "firstwall_mat": "Be",
        "inboard_tf_coils_mat": "Be",
        "pf_coil_case_mat": "Be",
        "pf_coil_mat": "Be",
        "tf_coil_mat": "Be",
    },
)


tally1 = odw.MeshTally2D(
    tally_type="photon_effective_dose",
    plane="xy"
    )
tally2 = odw.MeshTally2D(
    tally_type="neutron_effective_dose",
    plane="xy"
    )

tallies = openmc.Tallies([tally1, tally2])

settings = odw.FusionSettings()
settings.batches = 2
settings.particles = 100
settings.photon_transport = True
settings.source = FusionRingSource(fuel="DT", radius=350)

my_model = odw.Model(
    materials=materials, geometry=geometry, settings=settings, tallies=tallies
)
statepoint_file = my_model.run()

my_mesh = odw.RegularMesh2D(resolution=(400, 400))