fusion-energy / openmc_source_plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
☆10Updated 9 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
- ☆13Updated 10 months ago
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 9 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆32Updated 2 months ago
- List of open source projects related to OpenMC☆24Updated 5 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated last week
- ☆18Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Collection of scripts for managing data for OpenMC☆29Updated last month
- Toolkit for reading and interacting with ENDF-6 formatted files☆36Updated last week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated this week
- A tool for making reproducible materials and standardizing use across several neutronics codes☆23Updated 4 months ago
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆12Updated 5 years ago
- Python ENDF Parser☆27Updated 6 months ago
- Native plotting GUI for model design and verification☆55Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 5 months ago
- Combines open source packages to produce an automated fusion specific neutronics workflow☆14Updated 2 years ago
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- OpenMC wrapped as a Moose App☆16Updated last year
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- Sampling nuclear data and uncertainty☆50Updated last month
- Example Jupyter notebooks for OpenMC☆35Updated 3 months ago
- a companion for writing MCNP input decks☆11Updated 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☆12Updated last year
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆28Updated last month
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆28Updated this week
- A Python package for downloading h5 cross section files for use in OpenMC.☆12Updated last month
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated 2 weeks ago
- Convert OpenMC Geometry Components to CAD☆16Updated 3 months ago