<filename>examples/plot_regular_mesh_tally_with_geometry.py
import regular_mesh_plotter as rmp
import openmc

# loads in the statepoint file containing tallies
statepoint = openmc.StatePoint(filepath="statepoint.2.h5")

# gets one tally from the available tallies
my_tally = statepoint.get_tally(name="neutron_effective_dose_on_2D_mesh_xy")

# creates a plot of the mesh
my_plot = rmp.plot_regular_mesh_tally_with_geometry(
    tally=my_tally,
    dagmc_file_or_trimesh_object="dagmc.h5m",
    std_dev_or_tally_value="tally_value",
    filename="plot_regular_mesh_tally_with_geometry.png",
    scale=None,  # LogNorm(),
    vmin=None,
    label="",
    x_label="X [cm]",
    y_label="Y [cm]",
    # plane_origin=[0, 0, 0],
    plane_normal=[0, 0, 1],
    rotate_mesh=0,
    rotate_geometry=0,
    required_units=None,
    source_strength=None,
)

my_plot.show()

<filename>examples/plot_regular_mesh_tally_with_geometry.py
import regular_mesh_plotter as rmp
import openmc

# loads in the statepoint file containing tallies
statepoint = openmc.StatePoint(filepath="statepoint.2.h5")

# gets one tally from the available tallies
my_tally = statepoint.get_tally(name="neutron_effective_dose_on_2D_mesh_xy")

# creates a plot of the mesh
my_plot = rmp.plot_regular_mesh_tally_with_geometry(
    tally=my_tally,
    dagmc_file_or_trimesh_object="dagmc.h5m",
    std_dev_or_tally_value="tally_value",
    filename="plot_regular_mesh_tally_with_geometry.png",
    scale=None,  # LogNorm(),
    vmin=None,
    label="",
    x_label="X [cm]",
    y_label="Y [cm]",
    # plane_origin=[0, 0, 0],
    plane_normal=[0, 0, 1],
    rotate_mesh=0,
    rotate_geometry=0,
    required_units=None,
    source_strength=None,
)

my_plot.show()

# loads in the statepoint file containing tallies # gets one tally from the available tallies # creates a plot of the mesh # LogNorm(), # plane_origin=[0, 0, 0],