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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...

lanl / mcnptools

Updated Sep 9, 2022
C++

MontePy

idaholab / MontePy

MontePy is a Python library (API) to read, edit, and write MCNP input files.

api monte-carlo mcnp radiation-transport neutronics mcnp6

Updated Apr 15, 2024
Python

haeginh / POLY2TET

POLY2TET: A Computer Program for Conversion of Computational Human Phantoms from Polygonal Mesh to Tetrahedral Mesh

geant4 phantom radiation montecarlo-simulation phits mesh-phantoms tetrahedral-mesh computational-human-phantoms mcnp6

Updated Apr 1, 2022
C++

repositony / vscode_mcnp

MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.

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

Updated Jan 5, 2024

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

Created by Los Alamos National Laboratory

Followers: 5 followers
Website: mcnp.lanl.gov
Wikipedia: Wikipedia