openmc-plasma-source 0.2

Creates tokamak plasma sources for OpenMC

openmc-plasma-source

This python-based package offers a way of creating a parametric OpenMC plasma source from plasma parameters. The OpenMC sources are ring sources which reduces the computational cost and the settings.xml file size.

The equations implemented here are taken from this paper.

Installation

To install openmc-plasma-source, simply run:

pip install openmc-plasma-source

Usage

Tokamak Source

Create a source with a spatial and temperature distribution of a tokamak plasma.

from openmc_plasma_source import TokamakSource

my_plasma = TokamakSource(
    elongation=1.557,
    ion_density_centre=1.09e20,
    ion_density_peaking_factor=1,
    ion_density_pedestal=1.09e20,
    ion_density_separatrix=3e19,
    ion_temperature_centre=45.9,
    ion_temperature_peaking_factor=8.06,
    ion_temperature_pedestal=6.09,
    ion_temperature_separatrix=0.1,
    major_radius=9.06,
    minor_radius=2.92258,
    pedestal_radius=0.8 * 2.92258,
    mode="H",
    shafranov_factor=0.44789,
    triangularity=0.270,
    ion_temperature_beta=6
  )

my_plasma.sample_sources()
my_sources = my_plasma.make_openmc_sources()

For a more complete example check out the example script.

Ring Source

Create a ring source with temperature distribution of a 2000eV plasma.

my_plasma = FusionRingSource(
    start_angle = 0.,
    stop_angle = 6.28318530718,  # input is in radians
    temperature = 20000.,
    fuel='DT'
)

Point Source

Create a point source with temperature distribution of a 2000eV plasma.

my_plasma = FusionPointSource(
    coordinate = (0, 0, 0),
    temperature = 20000.,
    fuel = 'DT'
)