#

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 3 public repositories matching this topic...

patrickpark910 / critloadexp

Python-automated MCNP simulation of the critical loading experiment for a TRIGA Mk.I reactor

python fortran mcnp

Updated Feb 12, 2021
Assembly

hungbt1908 / MCNP6-HPGE_Detector_Simulation

monte-carlo-simulation mcnp hpge

Updated May 26, 2023
Assembly

patrickpark910 / rodcal-mcnp

Python-automated MCNP simulation of control rod calibration, with integral and differential worth curve calculations, for a TRIGA Mk.I reactor

python nuclear mcnp

Updated Feb 16, 2021
Assembly

Created by Los Alamos National Laboratory

Followers: 6 followers
Website: mcnp.lanl.gov
Wikipedia: Wikipedia