Hi all,
I am running simulations with transfer rates where I use a cell not present in the geometry to store nuclides removed from fuel salt. However, I noticed that when I set a cell’s region to None and used the plot run mode, all of the white space where no geometry is defined became colored the same as the material I gave to the cell with a None region. I’ve included an example below showing what I mean.
import openmc
x_min = openmc.XPlane(-1, boundary_type='vacuum')
x_max = openmc.XPlane(1, boundary_type='vacuum')
y_min = openmc.YPlane(-1, boundary_type='vacuum')
y_max = openmc.YPlane(1, boundary_type='vacuum')
z_min = openmc.ZPlane(-1, boundary_type='vacuum')
z_max = openmc.ZPlane(1, boundary_type='vacuum')
block_inside = (+x_min & -x_max &
+y_min & -y_max &
+z_min & -z_max)
fuel = openmc.Material()
fuel.set_density('g/cc', 10)
fuel.add_element('U', 1)
test = openmc.Material()
test.set_density('g/cc', 100)
test.add_element('U', 1)
mats = openmc.Materials(
(fuel,
test)
)
mats.export_to_xml()
fuel_cube = openmc.Cell()
fuel_cube.fill = fuel
fuel_cube.region = block_inside
empty_cell = openmc.Cell()
empty_cell.fill = test
root = openmc.Universe(
cells=[fuel_cube,
empty_cell]
)
geom = openmc.Geometry(root)
geom.export_to_xml()
sets = openmc.Settings()
sets.run_mode = 'plot'
sets.export_to_xml()
colors = {
fuel_cube : 'blue',
empty_cell : 'green'
}
plot = openmc.Plot()
plot.color_by = 'cell'
plot.colors = colors
plots = openmc.Plots([plot])
plots.export_to_xml()
openmc.run()