sandialabs / MatMCNPLinks
A utility code for generating material cards for MCNP
☆22Updated 4 years ago
Alternatives and similar repositories for MatMCNP
Users that are interested in MatMCNP are comparing it to the libraries listed below
Sorting:
- Python Interface and Utility Functions for MCNP6☆21Updated 8 years ago
- Some Monte Carlo tools☆52Updated last month
- A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)☆14Updated 13 years ago
- MCNP(X) project builder using C++☆16Updated this week
- OpenMC Monte Carlo Code☆23Updated 10 months ago
- ☆87Updated last year
- Sampling nuclear data and uncertainty☆54Updated 2 months ago
- a companion for writing MCNP input decks☆12Updated 4 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- ☆16Updated last year
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Updated 8 years ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated last month
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆12Updated last year
- Native plotting GUI for model design and verification☆64Updated 3 weeks ago
- Simulation of transmutation and decay in nuclear systems☆33Updated this week
- Collection of scripts for managing data for OpenMC☆38Updated 2 weeks ago
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Monte Carlo Particle Lists☆35Updated 3 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Convert MCNP input files to a general CAD format☆38Updated 5 months ago
- Tools for usage with MCNP☆10Updated 12 years ago
- List of open source projects related to OpenMC☆30Updated 6 months ago
- Python ENDF Parser☆39Updated last month
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆171Updated last week
- Tool to rename cells, surfaces, materials and universes in MCNP input files.☆12Updated 3 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 10 months ago
- Nuclear data processing with legacy NJOY☆122Updated this week
- API for parsing and post-processing many MC simulations related files☆17Updated this week