openmc-dev / openmc-notebooks
Example Jupyter notebooks for OpenMC
☆35Updated 2 months ago
Alternatives and similar repositories for openmc-notebooks:
Users that are interested in openmc-notebooks are comparing it to the libraries listed below
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆135Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- List of open source projects related to OpenMC☆23Updated 5 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 3 weeks ago
- Native plotting GUI for model design and verification☆55Updated 3 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated this week
- Direct Accelerated Geometry Monte Carlo Toolkit☆108Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated last week
- Python ENDF Parser☆27Updated 6 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated 2 weeks ago
- Collection of scripts for managing data for OpenMC☆29Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 5 months ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 9 months ago
- NCrystal : a library for thermal neutron transport in crystals and other materials☆44Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated last month
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆40Updated 7 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆23Updated 4 months ago
- Stochastic Calculator Of Neutron transport Equation☆39Updated 3 weeks ago
- Sampling nuclear data and uncertainty☆50Updated last month
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- ☆75Updated 8 months ago
- Tools to translate between different CSG geometry types☆36Updated last year
- ☆18Updated 2 weeks ago
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆28Updated this week
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆32Updated 2 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…☆39Updated 2 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆36Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆55Updated last week
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year