openmc.SourceParticle¶
- class openmc.SourceParticle(r: Iterable[float] = (0.0, 0.0, 0.0), u: Iterable[float] = (0.0, 0.0, 1.0), E: float = 1000000.0, time: float = 0.0, wgt: float = 1.0, delayed_group: int = 0, surf_id: int = 0, particle: ParticleType = ParticleType.NEUTRON)[source]¶
Source particle
This class can be used to create source particles that can be written to a file and used by OpenMC
- Parameters
r (iterable of float) – Position of particle in Cartesian coordinates
u (iterable of float) – Directional cosines
E (float) – Energy of particle in [eV]
time (float) – Time of particle in [s]
wgt (float) – Weight of the particle
delayed_group (int) – Delayed group particle was created in (neutrons only)
surf_id (int) – Surface ID where particle is at, if any.
particle (ParticleType) – Type of the particle