A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.
-
Updated
Jul 1, 2024 - Rust
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.
A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.
Command line tool to convert MCNP mesh tallies to Visual ToolKit (VTK) formats. Supports all MCNPv6.2 legacy meshtal output formats, for both for rectangular and cylindrical meshes.
Command line tool to split meshtal results into individual files. This is extremely simple but nice to have when needed.
Created by Los Alamos National Laboratory