Tools to translate between different CSG geometry types
☆44May 28, 2025Updated last year
Alternatives and similar repositories for csg2csg
Users that are interested in csg2csg are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Sep 13, 2021Updated 4 years ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆36Aug 21, 2026Updated last week
- Native plotting GUI for model design and verification☆73Jul 9, 2026Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆132Aug 14, 2026Updated 2 weeks ago
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 3 years ago
- Managed Database hosting by DigitalOcean • AdPostgreSQL, MySQL, MongoDB, Kafka, Valkey, and OpenSearch available. Automatically scale up storage and focus on building your apps.
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆65Aug 23, 2026Updated last week
- Convert MCNP input files to a general CAD format☆40Jun 20, 2025Updated last year
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆21Sep 13, 2021Updated 4 years ago
- Collection of scripts for managing data for OpenMC☆41Aug 1, 2026Updated 3 weeks ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆46Dec 11, 2024Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆39Jul 24, 2026Updated last month
- JADE, a novel nuclear data libraries V&V tool☆41Jul 30, 2026Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆61May 1, 2026Updated 3 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆28Updated this week
- Wordpress hosting with auto-scaling - Free Trial Offer • AdFully Managed hosting for WordPress and WooCommerce businesses that need reliable, auto-scalable performance. Cloudways SafeUpdates now available.
- Automated V&V for fusion relevant CAD-based benchmarks☆25Apr 8, 2026Updated 4 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆66Aug 22, 2026Updated last week
- Sampling nuclear data and uncertainty☆61May 29, 2026Updated 3 months ago
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆15Mar 19, 2021Updated 5 years ago
- A utility code for generating material cards for MCNP☆24Feb 26, 2021Updated 5 years ago
- NJOY for the 21st Century☆91Jan 22, 2024Updated 2 years ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆34Jul 17, 2026Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆68Jul 21, 2023Updated 3 years ago
- Simulation of transmutation and decay in nuclear systems☆37Jul 27, 2026Updated last month
- GPUs on demand by Runpod - Special Offer Available • AdRun AI, ML, and HPC workloads on powerful cloud GPUs—without limits or wasted spend. Deploy GPUs in under a minute and pay by the second.
- Toolkit for reading and interacting with ENDF-6 formatted files☆42Aug 18, 2026Updated last week
- List of open source projects related to OpenMC☆42May 22, 2026Updated 3 months ago
- Script to help download, configure, install, and run the OpenMP offloading version of OpenMC☆11May 3, 2024Updated 2 years ago
- Python ENDF Parser☆45Jun 6, 2026Updated 2 months ago
- Format description for ACE nuclear data files☆23Apr 28, 2022Updated 4 years ago
- CGMF nuclear fission fragment de-excitation statistical code☆31Apr 4, 2026Updated 4 months ago
- Plugins and command extensions for Coreform Cubit☆18Jun 20, 2025Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 8 months ago
- OpenMC Monte Carlo Code☆28Jan 31, 2025Updated last year
- Simple, predictable pricing with DigitalOcean hosting • AdAlways know what you'll pay with monthly caps and flat pricing. Enterprise-grade infrastructure trusted by 600k+ customers.
- continuous energy monte carlo neutron transport in general geometries on GPUs☆52Jun 8, 2017Updated 9 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆100Jun 25, 2026Updated 2 months ago
- Collection of validation scripts, notebooks, results☆11Dec 23, 2025Updated 8 months ago
- A code package to produce ACE-formatted files for MCNP calculations.☆15Apr 17, 2026Updated 4 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆12May 18, 2022Updated 4 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆46Jun 25, 2024Updated 2 years ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆31May 19, 2021Updated 5 years ago