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Open source computational physics program
OpenMC is a Monte Carlo neutron and photon simulation transport code. Initially developed by the Computational Reactor Physics Group at Massachusetts Institute
OpenMC
Geant4 MPMC OpenMC PYTHIA ROOT Solarsoft Spinach Surface Evolver TARDIS UrQMD Astropy CMBFAST GADGET CP2K EGS MCSim McStas McXtrace MPMC OpenMC TARDIS FORM
List of free and open-source software packages
List_of_free_and_open-source_software_packages
Numerical simulations of physical problems via computers
MCNP Meep MFEM Momentum MOOSE MPMC MRAMS Nek5000 Nektar++ OpenFOAM OpenLB OpenMC Orbiter (simulator) PYTHIA RELAP5-3D ROOT Serpent Simcenter STAR-CCM+ SPEDAS
Computational_physics
Creating a complex 3D surface or object by combining primitive objects
Boolean operations on polygonal meshes. Clara.io Geant4 Magica CSG MCNP OpenMC - Monte Carlo Photon and Neutron Transport Code SketchUp Womp Foley, James
Constructive_solid_geometry
Study of motions and interactions of neutrons
of criticality risk in nuclear installations developed at IRSN, France OpenMC – An open source, community-developed open source Monte Carlo code RMC –
Neutron_transport
with polarizable models". github.com. Retrieved December 17, 2025. "OpenMC". openmc.org. Retrieved December 17, 2025. "GitHub - cp2k/cp2k: Quantum chemistry
List of computational physics software
List_of_computational_physics_software
Geant4 (CERN) McCARD (KAIST) MCNP (LANL) MCU (MCU) (Kurchatov Institute) OpenMC PHITS (JAEA) SCALE (KENO V and KENO VI) (ORNL) Serpent (VTT) TRIPOLI-4 (CEA)
List of software for nuclear engineering
List_of_software_for_nuclear_engineering
Software package for simulating nuclear processes
for electron transport Nuclear reactor Nuclear engineering Neutron FLUKA Geant4 MELCOR RELAP5-3D Serpent (software) MONK OpenMC MCNP official website
Monte Carlo N-Particle Transport Code
Monte_Carlo_N-Particle_Transport_Code
Complex complementary error function
1. Bibcode:1992JAP....71....1B. doi:10.1063/1.350737. ISSN 0021-8979. "OpenMC Windowed Multipole". 2020-06-01. Retrieved 2020-12-20. Avetisov, Slava (1995)
Faddeeva_function
Field of nuclear engineering
repeated units. Computer codes used for criticality safety analyses include OPENMC (MIT), COG (US), MONK (UK), SCALE/KENO (US), MCNP (US), and CRISTAL (France)
Nuclear_criticality_safety
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