Example Jupyter notebooks for OpenMC
☆53Feb 28, 2025Updated last year
Alternatives and similar repositories for openmc-notebooks
Users that are interested in openmc-notebooks are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- List of open source projects related to OpenMC☆43May 22, 2026Updated 5 months ago
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆14Oct 9, 2026Updated 3 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆64Sep 14, 2026Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Sep 13, 2021Updated 5 years ago
- Contains slides and example problems for OpenMC workshops and presentations☆28Jun 13, 2022Updated 4 years ago
- Deploy on Railway without the complexity - Free Credits Offer • AdConnect your repo and Railway handles the rest with instant previews. Quickly provision container image services, databases, and storage volumes.
- Convert OpenMC Geometry Components to CAD☆21Nov 22, 2024Updated last year
- Tool for converting Serpent input files to OpenMC classes/XML☆12Sep 4, 2026Updated last month
- Catalogs a plethora of reactor inputs for OpenMC☆42Feb 28, 2025Updated last year
- Collection of validation scripts, notebooks, results☆12Dec 23, 2025Updated 10 months ago
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆15Nov 29, 2019Updated 6 years ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆12Oct 20, 2022Updated 4 years ago
- Native plotting GUI for model design and verification☆74Sep 3, 2026Updated last month
- Repository for running SINBAD benchmarks with OpenMC and UQ☆12May 18, 2022Updated 4 years ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆28Aug 27, 2026Updated 2 months ago
- Deploy on Railway without the complexity - Free Credits Offer • AdConnect your repo and Railway handles the rest with instant previews. Quickly provision container image services, databases, and storage volumes.
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆203Sep 28, 2026Updated last month
- ☆20Mar 26, 2024Updated 2 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 10 months ago
- OpenMC Monte Carlo Code☆1,131Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆41Jul 3, 2025Updated last year
- OpenMC Workshop for Canadian Nuclear Laboratories☆12Mar 17, 2017Updated 9 years ago
- OpenMC Monte Carlo Code☆28Jan 31, 2025Updated last year
- Monte Carlo Particle Lists☆38Updated this week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆67Oct 26, 2026Updated last week
- End-to-end encrypted cloud storage - Proton Drive • AdSpecial offer: 40% Off Yearly / 80% Off First Month. Protect your most important files, photos, and documents from prying eyes.
- Project repository for "An Open Source Nuclear Modeling Ecosystem to Support Fusion Pilot Plant Design" collaboration between MIT and ANL☆10Mar 5, 2026Updated 7 months ago
- Collection of scripts for managing data for OpenMC☆41Oct 22, 2026Updated last week
- Combines open source packages to produce an automated fusion specific neutronics workflow☆17May 31, 2022Updated 4 years ago
- A Python-based Monte Carlo radiation transport code☆61Updated this week
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆16May 6, 2025Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆39Jul 24, 2026Updated 3 months ago
- Monte Carlo neutron source terms for SHINE's neutron generators☆15Apr 20, 2026Updated 6 months 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
- Python ENDF Parser☆46Oct 13, 2026Updated 2 weeks ago
- 1-Click AI Models by DigitalOcean Gradient • AdDeploy popular AI models on DigitalOcean Gradient GPU virtual machines with just a single click. Zero configuration with optimized deployments.
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 3 years ago
- Stochastic Calculator Of Neutron transport Equation☆68Jul 28, 2026Updated 3 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆101Sep 12, 2026Updated last month
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆49Dec 24, 2025Updated 10 months ago
- Create parametric 3D fusion reactor CAD and neutronics models☆109Oct 7, 2026Updated 3 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆47Jun 25, 2024Updated 2 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆26Apr 8, 2026Updated 6 months ago