rachelslaybaugh / NE250
Nuclear Reactor Theory
☆19Updated 7 years ago
Alternatives and similar repositories for NE250
Users that are interested in NE250 are comparing it to the libraries listed below
Sorting:
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆57Updated last month
- 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☆31Updated 4 months ago
- List of open source projects related to OpenMC☆24Updated 8 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- Native plotting GUI for model design and verification☆57Updated 3 months ago
- Stochastic Calculator Of Neutron transport Equation☆43Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆41Updated 3 months ago
- Sampling nuclear data and uncertainty☆51Updated last week
- Tools to translate between different CSG geometry types☆37Updated last year
- Direct Accelerated Geometry Monte Carlo Toolkit☆112Updated 3 months ago
- curated documents pertaining to early molten salt reactor research.☆22Updated last year
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- Python ENDF Parser☆33Updated 9 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- Nuclear data processing with legacy NJOY☆107Updated last month
- Collection of models for reactor physics benchmarks☆52Updated 7 months ago
- NJOY for the 21st Century☆78Updated last year
- A Python package for parsing FISPACT-II output☆28Updated 3 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆30Updated last week
- open-source Sn software☆33Updated this week
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆53Updated this week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆43Updated this week
- ☆30Updated 3 months ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆68Updated last week
- Computational inputs, reference outputs and experimental data for V&V systems☆12Updated last month
- MC/DC: Monte Carlo Dynamic Code☆41Updated 3 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆69Updated last week
- Catalogs a plethora of reactor inputs for OpenMC☆23Updated 2 months ago