openmc-data-storage / openmc_data_downloader
A Python package for downloading h5 cross section files for use in OpenMC.
☆11Updated 3 weeks ago
Alternatives and similar repositories for openmc_data_downloader:
Users that are interested in openmc_data_downloader are comparing it to the libraries listed below
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 4 months ago
- ☆18Updated 5 months ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- Easily access hydrogen transport properties☆15Updated last month
- Tool to estimate H retention in tokamak divertors☆10Updated 3 years ago
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- ☆13Updated 10 months ago
- Python ENDF Parser☆27Updated 5 months ago
- ENDF/B pre-processing codes (PREPRO)☆16Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆13Updated 8 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated last month
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 8 months ago
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆27Updated this week
- List of open source projects related to OpenMC☆23Updated 5 months ago
- ☆17Updated 2 years ago
- Sampling nuclear data and uncertainty☆49Updated 3 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 5 months ago
- A Python package for parsing FISPACT-II output☆26Updated 11 months 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
- A tool for making reproducible materials and standardizing use across several neutronics codes☆22Updated 3 months ago
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆31Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆34Updated this week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆26Updated 3 weeks ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆36Updated 3 months ago
- ☆29Updated last year
- PROCESS is a systems code at UKAEA that calculates in a self-consistent manner the parameters of a fusion power plant with a specified pe…☆39Updated this week
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆10Updated 8 months ago