mit-crpg / opendepleteLinks
A depletion framework for OpenMC
☆14Updated 7 years ago
Alternatives and similar repositories for opendeplete
Users that are interested in opendeplete are comparing it to the libraries listed below
Sorting:
- Collection of validation scripts, notebooks, results☆11Updated last year
- OpenMC Monte Carlo Code☆18Updated 4 months ago
- Collection of scripts for managing data for OpenMC☆33Updated 4 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Updated 7 years ago
- Plugins and command extensions for Coreform Cubit☆18Updated 11 months ago
- Simulation of transmutation and decay in nuclear systems☆28Updated 4 months ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆29Updated 2 weeks ago
- Native plotting GUI for model design and verification☆58Updated 4 months ago
- Collection of models for reactor physics benchmarks☆52Updated 8 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last month
- Sampling nuclear data and uncertainty☆51Updated last month
- List of open source projects related to OpenMC☆26Updated last week
- Toolkit for reading and interacting with ENDF-6 formatted files☆41Updated last week
- NCrystal : a library for thermal neutron transport in crystals and other materials☆46Updated this week
- Format description for ACE nuclear data files☆21Updated 3 years ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)☆13Updated 12 years ago
- Nuclear data processing with legacy NJOY☆109Updated 2 weeks ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 3 months ago
- NJOY for the 21st Century☆79Updated last year
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆39Updated 5 months ago
- Convert MCNP input files to a general CAD format☆37Updated last year
- open-source Sn software☆34Updated this week