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MCNP

The Monte Carlo N-Particle (MCNP) radiation transport code is a Monte Carlo transport code developed by Las Alamos National Laboratory (LANL).

It supports over 37 different types of particles, and is widely used by nuclear engineers,

and nuclear physicists.

Here are 59 public repositories matching this topic...

lanl / mcnptools

mcnp mcnp6

Updated May 30, 2024
C++

MontePy

idaholab / MontePy

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

api monte-carlo mcnp radiation-transport neutronics mcnp6

Updated Sep 12, 2026
Python

inr-kit / McCAD-Library

a CAD to MC geometry conversion tool

cmake opencascade mcnp cpluplus boostcpp

Updated Apr 4, 2024
C++

openmc-dev / openmc_mcnp_adapter

Tool for converting MCNP input files to OpenMC classes/XML

monte-carlo-simulation nuclear-engineering mcnp openmc

Updated Sep 14, 2026
Python

kbat / mc-tools

Some Monte Carlo tools

monte-carlo povray root-cern mcnp fluka phits mcnpx radiation-transport

Updated Sep 15, 2026
Python

watts-dev / watts

Workflow and Template Toolkit for Simulation (WATTS)

python simulation templates workflow-automation mcnp nuclear-energy openmc

Updated Jul 24, 2026
Python

fusion-energy / neutronics_material_maker

A tool for making reproducible materials and standardizing use across several neutronics codes

library database material serpent mcnp neutrons fispact openmc

Updated Aug 27, 2026
Python

FSIBT / PyMCNP

Python tools for MCNP

python mcnp mcnp6

Updated Jun 12, 2026
Python

ukaea / neutronics_material_maker

A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak

library material serpent mcnp fispact openmc

Updated Sep 13, 2021
Python

repositony / vscode_mcnp

MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks as a placeholder for the full LSP is implemented.

syntax-highlighting snippets vscode-extension mcnp radiation-transport mcnp6

Updated Jul 7, 2024

alexhagen / wig

a companion for writing MCNP input decks

python simulation monte-carlo python-2 python-2-7 mcnp

Updated Apr 2, 2021
Python

IAEA-NDS / ACEMAKER

A code package to produce ACE-formatted files for MCNP calculations.

ace nuclear-data mcnp

Updated Apr 17, 2026
Fortran

MC-kit / mckit

Tools to work with MCNP models and results

tally nuclear-engineering mcnp radiation-physics meshtally

Updated Sep 21, 2026
Python

arekfu / t4_geom_convert

Tool to convert MCNP geometries into TRIPOLI-4 geometries.

converter geometry mcnp mcnpx tripoli-4

Updated Mar 6, 2025
Python

ENEA-Fusion-Neutronics / MCNP-Input-Reader

The package for reading mcnp input in a pythonic way

radiation nuclear-engineering mcnp neutronics

Updated Jul 25, 2022
Python

Fusion-Power-Plant-Framework / tokamak-neutron-source

Create an arbitrary parametric tokamak neutron source

plasma source mcnp nuclear-fusion neutronics openmc

Updated May 13, 2026
Python

egor1abs / openmc_sdef_parser

MCNP SDEF to OpenMC conversion tool

fusion plasma-physics mcnp neutronics openmc

Updated Jun 10, 2026
Python

caalh / OWEN

OWEN — Open Workflow for Engineered Neutronics: a VS Code/Cursor extension for MCNP, OpenMC, Serpent & SCONE (syntax highlighting, lattice builder, 3D preview, validation, workflow automation). A BelvoirDynamics product.

monte-carlo vscode-extension nuclear serpent mcnp scone neutronics openmc

Updated Sep 20, 2026
TypeScript

travleev / numjuggler

Tool to rename cells, surfaces, materials and universes in MCNP input files.

python iter mcnp renumbering

Updated Sep 11, 2025
Python

ojschumann / mcnp_bash_completion

Bash completion script for MCNP

terminal bash-completion mcnp

Updated Dec 5, 2024
Shell

Created by Los Alamos National Laboratory

Followers: 10 followers
Website: github.com/topics/mcnp
Wikipedia: Wikipedia