openmc-data-storage / isotope-xs-plotter
XSPlot - Neutron cross section plotter for isotopes
☆14Updated last year
Alternatives and similar repositories for isotope-xs-plotter
Users that are interested in isotope-xs-plotter are comparing it to the libraries listed below
Sorting:
- ☆22Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- List of open source projects related to OpenMC☆24Updated 8 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- A Python package for downloading h5 cross section files for use in OpenMC.☆13Updated 4 months ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 8 months ago
- API for parsing and post-processing many MC simulations related files☆15Updated 3 weeks ago
- 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 last week
- Python ENDF Parser☆33Updated 9 months ago
- Sampling nuclear data and uncertainty☆51Updated last week
- Accelerated Discretized Geometry☆14Updated this week
- Convert OpenMC Geometry Components to CAD☆17Updated 5 months ago
- OpenMC Monte Carlo Code☆17Updated 3 months ago
- Computational inputs, reference outputs and experimental data for V&V systems☆12Updated last month
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆29Updated 3 weeks ago
- Stochastic Calculator Of Neutron transport Equation☆43Updated this week
- open-source Sn software☆33Updated this week
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- Plugins and command extensions for Coreform Cubit☆18Updated 11 months ago
- ☆15Updated last year
- Openmc-FEnicsx for muLtiphysics tutorIAl☆16Updated 9 months ago
- A Python package for parsing FISPACT-II output☆28Updated 3 weeks ago
- ☆30Updated 2 months ago
- Collection of scripts for managing data for OpenMC☆31Updated 3 months ago
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆14Updated 4 years ago
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- JADE, a novel nuclear data libraries V&V tool☆27Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆41Updated 3 months ago
- ENDF-6 data interface and nuclear data evaluation assist code☆16Updated 2 weeks ago