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
100+ pages of structured lessons from first input to full reactor models.
Start learningNRDP
Nuclear Reference Data Portal
Periodic table, cross-section libraries, material cards, and engineering calculators.
Software division of ReactorMC
Three tools for MCNP, OpenMC, Serpent & SCONE input decks — on the desktop, in VS Code, and in Sublime Text or Notepad++.
Latest additions
Recently shipped across the software, tutorial, and data sides of ReactorMC.
NICHOLS v1.0.0
Sublime Text & Notepad++ packages for MCNP, OpenMC, Serpent & SCONE — syntaxes, completions, and 4 color schemes.
NRDPALLEN Doppler Studio
Multi-temperature resonance broadening with self-shielding factors and resonance integrals, on top of the σ(E) explorer.
SoftwareResults Viewer & Sweep Dashboard
Parse k-eff, spectra, tallies & mesh from all four codes and chart parametric sweeps — in OWEN and GROVES.
Jump into an example
Working code from simple pin cells to full assemblies.
PWR Pin Cell
Fuel, gap, cladding, moderator — geometry with k-eff tallies.
OpenMCPython Pin Cell
Build a fuel pin in Python with automatic plotting.
SERPENTPin Cell
Basic pin geometry with detectors and output analysis.
MCNP17×17 Assembly
Lattice structures, guide tubes, and enrichment.
OpenMCAssembly Model
17×17 assembly with lattices and visualization.
SERPENTAssembly + Burnup
Full assembly with depletion for reactor physics.
SCONEFuel Pin
Block-style pin with pinUniverse and ACE nuclear data.
SCONEReactor Core
BEAVRS-derived 17×17 lattice with tallies.