MCNP, OPENMC, SERPENT and SCONE. Free tutorials
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GROVES desktop v1.0.1 + OWEN VS Code extension v0.1.0 — explore both ReactorMC Educate · Reference · Create
Learn MCNP, OpenMC, SERPENT & SCONE — free Monte Carlo tutorials for nuclear engineering, reactor physics, and radiation transport.
TUTORIALS Monte Carlo Education Hub
90+ pages of structured lessons from first input to full reactor models.
MCNP 27 pages OpenMC 22 pages SERPENT 21 pages SCONE 22 pages Fundamentals 9 pages Rosetta Stone interactive Start learning NRDP Nuclear Reference Data Portal Periodic table, cross-section libraries, material cards, and engineering calculators.
118 elements with isotope data Materials library ZAID & MT reference Fraction & density calculators Community Library Now open Explore NRDP GROVES Desktop MC Editor · v1.0.1
Air-gap-friendly desktop editor for MCNP, OpenMC, Serpent, and SCONE. Lattice builder, 3D preview, templates.
MCNP, OpenMC, Serpent & SCONE 3D viewport for geometry Lattice builder & templates Companion: OWEN VS Code extension Download v1.0.1 Jump into an example Working code from simple pin cells to full assemblies.
MCNP PWR Pin Cell Fuel, gap, cladding, moderator — geometry with k-eff tallies.
OpenMC Python Pin Cell Build a fuel pin in Python with automatic plotting.
SERPENT Pin Cell Basic pin geometry with detectors and output analysis.
MCNP 17×17 Assembly Lattice structures, guide tubes, and enrichment.
OpenMC Assembly Model 17×17 assembly with lattices and visualization.
SERPENT Assembly + Burnup Full assembly with depletion for reactor physics.
SCONE Fuel Pin Block-style pin with pinUniverse and ACE nuclear data.
SCONE Reactor Core BEAVRS-derived 17×17 lattice with tallies.
Compare codes → ReactorMC Independent tutorials for MCNP, OpenMC, SERPENT, and SCONE—geometry, sources, tallies, cross sections, and worked examples—plus the NRDP isotope and material reference. Free to use; always verify against official code documentation for safety-critical work.
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