Tools used for MCNP input deck syntax highlighting
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Updated
May 24, 2024 - Python
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.
Tools used for MCNP input deck syntax highlighting
This repository automates the execution of MCNP simulations for a specific problem related to the sensitivity of a radiation detector
A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.
Workflow and Template Toolkit for Simulation (WATTS)
MontePy is a Python library (API) to read, edit, and write MCNP input files.
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.
a CAD to MC geometry conversion tool
Command line tool to split meshtal results into individual files. This is extremely simple but nice to have when needed.
Tool for converting MCNP input files to OpenMC classes/XML
Tools to work with MCNP models and results
MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.
Tool to rename cells, surfaces, materials and universes in MCNP input files.
Created by Los Alamos National Laboratory