mit-crpg / opendepleteLinks
A depletion framework for OpenMC
☆15Updated 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 6 months ago
- Collection of scripts for managing data for OpenMC☆33Updated 6 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Updated 8 years ago
- MCNP(X) project builder using C++☆15Updated 3 weeks ago
- Native plotting GUI for model design and verification☆60Updated 6 months ago
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆29Updated 6 years ago
- Plugins and command extensions for Coreform Cubit☆18Updated last month
- Some Monte Carlo tools☆50Updated 3 weeks ago
- Simulation of transmutation and decay in nuclear systems☆29Updated 6 months ago
- Sampling nuclear data and uncertainty☆52Updated last month
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- MC/DC: Monte Carlo Dynamic Code☆43Updated 3 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 5 months ago
- Collection of models for reactor physics benchmarks☆54Updated 10 months ago
- A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.☆100Updated 5 months ago
- Example Jupyter notebooks for OpenMC☆37Updated 5 months ago
- Convert MCNP input files to a general CAD format☆37Updated last month
- open-source Sn software☆37Updated this week
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- 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…☆41Updated 7 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated last month
- List of open source projects related to OpenMC☆26Updated 2 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 2 months ago
- Python ENDF Parser☆34Updated last year
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- Papillon Nuclear Data Library☆17Updated 3 weeks ago