This python-based package offers a collection of pre-built OpenMC neutron sources for fusion applications.
OpenMC is required to use this package.
To install openmc_plasma_source, simply run:
pip install openmc_plasma_source
Create a source with a spatial and temperature distribution of a tokamak plasma. The OpenMC sources are ring sources which reduces the computational cost and the settings.xml file size. Each source has its own strength (or probability that a neutron spawns in this location).
The equations implemented here are taken from this paper.
from openmc_plasma_source import tokamak_source
my_sources = tokamak_source(
elongation=1.557,
ion_density_centre=1.09e20,
ion_density_pedestal=1.09e20,
ion_density_peaking_factor=1,
ion_density_separatrix=3e19,
ion_temperature_centre=45.9e3,
ion_temperature_pedestal=6.09e3,
ion_temperature_separatrix=0.1e3,
ion_temperature_peaking_factor=8.06,
ion_temperature_beta=6,
major_radius=906,
minor_radius=292.258,
pedestal_radius=0.8 * 292.258,
mode="H",
shafranov_factor=0.44789,
triangularity=0.270,
fuel={"D": 0.5, "T": 0.5},
)For a more complete example check out the example script.
Create a ring source with temperature distribution of a 2000 eV plasma.
from openmc_plasma_source import fusion_ring_source
my_source = fusion_ring_source(
radius=700,
angles=(0.0, 2 * math.pi), # 360deg source
temperature=20000.0,
fuel={"D": 0.5, "T": 0.5},
)Create a point source with temperature distribution of a 2000 eV plasma.
from openmc_plasma_source import fusion_point_source
my_source = fusion_point_source(
coordinate=(0, 0, 0),
temperature=20000.0,
fuel={"D": 0.09, "T": 0.91}, # note this is mainly tritium fuel so that TT reactions are more likely
)To run the tests, simply run
pytest tests