FICHA · AUR

openmc-git

The OpenMC project aims to provide a fully-featured Monte Carlo particle transport code based on modern methods.

  • particle-transport-simulation-tool
  • CLI
  • SCIENCE
  • NUCLEAR
  • Launchable
  • Runs in terminal
official+codex · reviewed · Jun 3, 2026 description in en

Description

Monte Carlo particle transport simulations can be built with a modern fully featured codebase. This helps researchers model neutron, photon, or radiation transport problems.

Particle-transport results depend on nuclear data, geometry, tallies, and statistical convergence. Validate models before using results for safety or engineering decisions.

How to run

openmc

Commands: openmc

Permissions

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