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.
Start learningNRDP
Nuclear Reference Data Portal
Periodic table, cross-section libraries, material cards, and engineering calculators.
GROVES
Desktop MC Editor · v1.0.1
Air-gap-friendly desktop editor for MCNP, OpenMC, Serpent, and SCONE. Lattice builder, 3D preview, templates.
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.