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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 is 1 public repository matching this topic...

lanl / sinbad-dt-source

MCNP6 source subroutine for simulating D-T neutrons in Ti-T Target

mcnp6

Updated Dec 16, 2025
Fortran

Created by Los Alamos National Laboratory

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