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other

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OpenMC Monte Carlo Code

openmc neutronics nuclear-data nuclear-energy nuclear-fusion photon-transport neutron-transport particle-transport nuclear-engineering radiation-transport computational-physics monte-carlo-simulation high-performance-computing

Created 2011-07-21

15,522 commits to develop branch, last one 16 hours ago

310

614

other

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Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303

geometry shielding nuclear-data visualization hadron-physics medical-physics photon-transport neutron-transport particle-tracking particle-transport high-energy-physics radiation-transport scientific-computing computational-physics monte-carlo-simulation multiphysics-simulation high-performance-computing

Created 2016-06-21

79 commits to master branch, last one 4 months ago

146

242

agpl-3.0

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Toolkit for Monte Carlo simulation of ionizing radiation — Trousse d'outils logiciels pour la simulation Monte Carlo du rayonnement ionisant

egsnrc dosimetry metrology medical-physics radiation-therapy ionizing-radiation radiation-transport monte-carlo-simulation

Created 2012-11-28

1,175 commits to master branch, last one about a year ago

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other

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Stochastic Calculator Of Neutron transport Equation

scone neutronics monte-carlo radiation-transport

Created 2022-07-06

1,182 commits to main branch, last one about a month ago

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mit

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MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

api mcnp mcnp6 neutronics monte-carlo radiation-transport

Created 2024-01-09

3,546 commits to develop branch, last one 8 days ago