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Updated ICF docs #109

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Nov 27, 2024
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2 changes: 1 addition & 1 deletion pyproject.toml
Original file line number Diff line number Diff line change
Expand Up @@ -8,7 +8,7 @@ build-backend = "setuptools.build_meta"
[project]
name = "openmc_plasma_source"
dynamic = ["version"]
description = "Creates tokamak and ICF plasma sources for OpenMC"
description = "Creates tokamak and fusion point sources for OpenMC"
readme = "README.md"
classifiers = [
"Programming Language :: Python :: 3",
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7 changes: 4 additions & 3 deletions src/openmc_plasma_source/point_source.py
Original file line number Diff line number Diff line change
Expand Up @@ -13,10 +13,11 @@ def fusion_point_source(
temperature: float = 20000.0,
fuel: Dict[str, float] = {"D": 0.5, "T": 0.5},
) -> List[IndependentSource]:
"""Creates a list of openmc.IndependentSource objects representing an ICF source.
"""
Creates a list of openmc.IndependentSource objects representing a point source.
Example uses: sealed-tube neutron generator, inertial confinement fusion source...
Resulting ICF (Inertial Confinement Fusion) source will have an energy
distribution according to the fuel composition.
Resulting source will have an energy distribution according to the fuel composition.
Args:
coordinate: Location of the point source.
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