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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 are 5 public repositories matching this topic...

repositony / mesh2vtk

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.

mesh vtk mcnp neutronics meshtally

Updated Mar 14, 2025
Rust

repositony / fisdef

Command line tool to convert FISPACT-II JSON results to simulation decay sources using decay data from the IAEA chart of nuclides.

mcnp iaea fispact-ii decay-data

Updated Mar 5, 2025
Rust

repositony / mesh2ww

Command line tool to generate mesh-based weight windows. Supports all MCNPv6.2 legacy meshtal output formats for rectangular and cylindrical meshes.

mesh variance-reduction mcnp weight-window

Updated Mar 12, 2025
Rust

repositony / splitmesh

Command line tool to split meshtal results into individual files. This is extremely simple but nice to have when needed.

command-line mcnp meshtally

Updated Mar 5, 2025
Rust

repositony / posvol

Command line tool to decode binary UKAEA CuV posvol files and convert the data to UTF-8 or JSON formats.

mcnp posvol cell-under-voxel

Updated Mar 5, 2025
Rust

Created by Los Alamos National Laboratory

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