allows initial_source filename to be specified and also allows multiple energy plots to be added to the same graph using the
example usage of these two features together
import openmc_source_plotter as osp
import openmc_plasma_source as ops
import numpy as np
source_files = []
for temp in [500, 1000]:
# sets the energy distribution to a Muir distribution neutrons for DT fusion neutrons
my_source = ops.FusionPointSource(
temperature=temp,
fuel="DD", # can be changed from DD to DT to get neutrons of different energy
)
source_filename = f"{temp}.h5"
# makes an initial_source.h5 file with details of the particles
osp.create_initial_particles(
source=my_source,
number_of_particles=100000,
output_source_filename=source_filename,
openmc_exec="/home/jshim/miniconda3/envs/openmc_0_11_0/bin/openmc",
)
source_files.append(source_filename)
# plots the particle energy distribution
plot = osp.plot_energy_from_initial_sources(
energy_bins=np.linspace(0, 15e6, 10000),
input_filenames=source_files
)
plot.show()
allows initial_source filename to be specified and also allows multiple energy plots to be added to the same graph using the
example usage of these two features together