https://www.pistack.xyz/tags/monte-carlo/ Recent content in Monte-Carlo on Pi Stack Hugo en-us Wed, 10 Jun 2026 00:00:00 +0000 https://www.pistack.xyz/posts/2026-06-10-self-hosted-nuclear-engineering-openmc-openmoc-moltres/ Wed, 10 Jun 2026 00:00:00 +0000 https://www.pistack.xyz/posts/2026-06-10-self-hosted-nuclear-engineering-openmc-openmoc-moltres/ <h2 id="introduction">Introduction</h2> <p>Nuclear reactor design and safety analysis depend on neutron transport simulations that track billions of particle histories through complex three-dimensional geometries. Three open-source simulation codes serve distinct roles in the nuclear engineering toolkit: <strong>OpenMC</strong> (Monte Carlo neutron transport), <strong>OpenMOC</strong> (Method of Characteristics deterministic transport), and <strong>Moltres</strong> (multi-physics reactor simulation).</p>