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ReactorMC

Educate · Reference · Create

TUTORIALS

Monte Carlo Education Hub

90+ pages of structured lessons from first input to full reactor models.

MCNP27 pages
OpenMC22 pages
SERPENT21 pages
SCONE22 pages
Fundamentals9 pages
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
Explore NRDP

OWEN

Desktop MC Editor · v1.0.0

Text editor and 3D viewer for MCNP, OpenMC, Serpent, and SCONE. Lattice builder, templates, dark theme.

MCNP, OpenMC, Serpent & SCONE
3D viewport for geometry
Lattice builder & templates
Syntax highlighting, dark theme
Download v1.0.0

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 →Cross-code reference →