A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
☆13Feb 10, 2026Updated 6 months ago
Alternatives and similar repositories for openmc_source_plotter
Users that are interested in openmc_source_plotter are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆15Nov 29, 2019Updated 6 years ago
- Native plotting GUI for model design and verification☆73Jul 9, 2026Updated last month
- ☆20Mar 26, 2024Updated 2 years ago
- List of open source projects related to OpenMC☆42May 22, 2026Updated 3 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆41Jul 3, 2025Updated last year
- Managed hosting for WordPress and PHP on Cloudways • AdManaged hosting for WordPress, Magento, Laravel, or PHP apps, on multiple cloud providers. Deploy in minutes on Cloudways by DigitalOcean.
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆46Jun 24, 2026Updated 2 months ago
- Example Jupyter notebooks for OpenMC☆50Feb 28, 2025Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆61May 1, 2026Updated 3 months ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆12May 18, 2022Updated 4 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆16May 6, 2025Updated last year
- The ERSN-OpenMC-Py is a graphical user interface specifically designed to streamline the use of the OpenMC code. It provides a user-frie…☆11Feb 24, 2024Updated 2 years ago
- ENDF/B pre-processing codes (PREPRO)☆23Aug 14, 2023Updated 3 years ago
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆12Oct 11, 2023Updated 2 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆200Aug 12, 2026Updated 2 weeks ago
- Managed Kubernetes at scale on DigitalOcean • AdDigitalOcean Kubernetes includes the control plane, bandwidth allowance, container registry, automatic updates, and more for free.
- OpenMC Workshop for Canadian Nuclear Laboratories☆12Mar 17, 2017Updated 9 years ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆12Oct 20, 2022Updated 3 years ago
- a companion for writing MCNP input decks☆14Apr 2, 2021Updated 5 years ago
- Python package for processing nuclear data distribution in ACE and ENDF format into HDF5 format for use in OpenMC. Adapted from the openm…☆19Aug 19, 2026Updated last week
- Materials for the PHYSOR 2016 OpenMC workshop.☆10May 9, 2016Updated 10 years ago
- Contains slides and example problems for OpenMC workshops and presentations☆26Jun 13, 2022Updated 4 years ago
- Monte Carlo neutron source terms for SHINE's neutron generators☆15Apr 20, 2026Updated 4 months ago
- curated documents pertaining to early molten salt reactor research.☆31Mar 7, 2024Updated 2 years ago
- 3D visualizations for DAGMC & OpenMC☆16May 27, 2026Updated 3 months ago
- 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.
- Convert OpenMC Geometry Components to CAD☆21Nov 22, 2024Updated last year
- Determine plasma flux functions for various plasma parameters and plasma configurations.☆18Jun 23, 2026Updated 2 months ago
- Collection of scripts for managing data for OpenMC☆41Aug 1, 2026Updated 3 weeks ago
- Create parametric 3D fusion reactor CAD and neutronics models☆104Jul 3, 2026Updated last month
- A C++ Monte Carlo Neutron Transport Code☆19Dec 10, 2025Updated 8 months ago
- A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)☆13Oct 24, 2012Updated 13 years 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
- Combines open source packages to produce an automated fusion specific neutronics workflow☆16May 31, 2022Updated 4 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆100Jun 25, 2026Updated 2 months ago
- AI Agents on DigitalOcean Gradient AI Platform • AdBuild production-ready AI agents using customizable tools or access multiple LLMs through a single endpoint. Create custom knowledge bases or connect external data.
- 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
- Parametric 3-D modeling toolset for stellarator fusion devices☆48Apr 23, 2026Updated 4 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆31Jun 4, 2024Updated 2 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Sep 13, 2021Updated 4 years ago
- A utility code for generating material cards for MCNP☆24Feb 26, 2021Updated 5 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆39Jul 24, 2026Updated last month