kbat / mc-toolsLinks
Some Monte Carlo tools
☆50Updated last week
Alternatives and similar repositories for mc-tools
Users that are interested in mc-tools are comparing it to the libraries listed below
Sorting:
- ☆85Updated last year
- Native plotting GUI for model design and verification☆60Updated last month
- OpenMC Monte Carlo Code☆18Updated 7 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 7 months ago
- Sampling nuclear data and uncertainty☆52Updated this week
- A utility code for generating material cards for MCNP☆21Updated 4 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆45Updated last week
- Python Interface and Utility Functions for MCNP6☆21Updated 8 years ago
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- Collection of scripts for managing data for OpenMC☆34Updated 8 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated this week
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- NJOY for the 21st Century☆80Updated last year
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Nuclear data processing with legacy NJOY☆117Updated 3 weeks ago
- Simulation of transmutation and decay in nuclear systems☆29Updated last week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆76Updated 2 months ago
- Python ENDF Parser☆36Updated last month
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated last month
- a companion for writing MCNP input decks☆12Updated 4 years ago
- Monte Carlo Particle Lists☆34Updated last week
- MCNP(X) project builder using C++☆15Updated this week
- Convert MCNP input files to a general CAD format☆38Updated 2 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 4 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆159Updated 3 weeks ago
- A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.☆103Updated 7 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 2 months ago