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 39 public repositories matching this topic...
A high-fidelity, free user input cylinder meshing tool for MCNP.
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Jun 6, 2021 - C
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May 26, 2023 - Assembly
notepad++ plugin for MCNP deck development. shows informative popups for selected cell/surface/physics cards. Inbuilt error checking.
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Oct 2, 2024 - Python
A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.
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Oct 1, 2024 - Rust
This repository automates the execution of MCNP simulations for a specific problem related to the sensitivity of a radiation detector
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Jun 1, 2024 - TeX
MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.
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Jul 7, 2024
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.
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Sep 11, 2024 - Rust
Command line tool to generate mesh-based weight windows. Supports all MCNPv6.2 legacy meshtal output formats for rectangular and cylindrical meshes.
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Sep 11, 2024 - Rust
Tools to work with MCNP models and results
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Oct 2, 2024 - Jupyter Notebook
Command line tool to decode binary UKAEA CuV posvol files and convert the data to UTF-8 or JSON formats.
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Sep 11, 2024 - Rust
Command line tool to split meshtal results into individual files. This is extremely simple but nice to have when needed.
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Sep 11, 2024 - Rust
Created by Los Alamos National Laboratory
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- Wikipedia
- Wikipedia