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OPENMC

OpenMC

Open source computational physics program

OpenMC is an open source Monte Carlo neutron and photon simulation transport code. Initially developed by the Computational Reactor Physics Group at MIT

OpenMC

List of free and open-source software packages

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

Computational physics

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

Computational_physics

Neutron transport

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

Neutron_transport

List of computational physics software

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

Monte Carlo N-Particle Transport Code

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

List of software for nuclear engineering

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

Faddeeva function

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

Faddeeva_function

Nuclear criticality safety

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

Nuclear_criticality_safety