OpenMC is a community-developed Monte Carlo neutron and photon transport code. It is capable of performing fixed source, k-eigenvalue, and subcritical multiplication calculations on models …

The OpenMC project aims to provide a fully-featured Monte Carlo particle transport code based on modern methods. It is a constructive solid geometry, continuous-energy transport code that …

OpenMC is an open source Monte Carlo neutron and photon simulation transport code.

OpenMC is a modern, open-source Monte Carlo code with a Python-first workflow. It pairs a high-performance transport engine with the flexibility of the Python ecosystem, making it a favorite …

Dec 17, 2025 · This document provides a high-level introduction to OpenMC, a community-developed Monte Carlo neutron and photon transport simulation code. It covers the overall …

OpenMC is a Monte Carlo particle transport simulation code focused on neutron criticality calculations. It is capable of simulating 3D models based on constructive solid geometry with …

OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code. It is capable of performing fixed source, k-eigenvalue, and subcritical multiplication calculations …

What is OpenMC? Community developed, open source Monte Carlo neutron–photon transport code, primarily target at applications in nuclear science and engineering

What does OpenMC do? In a nutshell, OpenMC simulates neutral particles (presently neutrons and photons) moving stochastically through an arbitrarily defined model that represents an real …

Python 11 7 1 0 Updated 2 weeks ago openmc_mcnp_adapter Public Tool for converting MCNP input files to OpenMC classes/XML