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.
NRDP
Nuclear Reference Data Portal
Periodic table, cross-section libraries, material cards, and engineering calculators.
OWEN
Desktop MC Editor · v1.0.0
Text editor and 3D viewer for MCNP, OpenMC, Serpent, and SCONE. Lattice builder, templates, dark theme.
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.