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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 is 1 public repository matching this topic...

mgaldon17 / BEMP_Thesis

This repository automates the execution of MCNP simulations for a specific problem related to the sensitivity of a radiation detector

automation nuclear mcnp

Updated Jun 1, 2024
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Created by Los Alamos National Laboratory

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