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mcnp6

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 6 public repositories matching this topic...

MontePy

idaholab / MontePy

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

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Updated Dec 18, 2025
Python

FSIBT / PyMCNP

Python tools for MCNP

python mcnp mcnp6

Updated Dec 3, 2025
Python

mjeroutek / MCNP-Syntax-Highlighting

Tools used for MCNP input deck syntax highlighting

python syntax-highlighting syntax python-script notepad-plus-plus mcnp mcnp6

Updated May 24, 2024
Python

ikarino / mcnp_input_generator

an unofficial MCNP input file generator

python mcnp mcnp6

Updated Dec 22, 2021
Python

afriou / mcnpgo

A Python library to assemble and apply transformations to MCNP files.

mcnp mcnpx mcnp6 mcnp5

Updated Nov 8, 2025
Python

glhrmbg / MCTools

Monte Carlo tools for use with MCNP input or output for data processing.

tools monte-carlo-simulation mcnp mcnpx mcnp6 monte-carlo-tools

Updated Aug 3, 2025
Python

Created by Los Alamos National Laboratory

Followers: 8 followers
Website: github.com/topics/mcnp
Wikipedia: Wikipedia