CORE-GATECH-GROUP / serpent-tools
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
☆55Updated last week
Alternatives and similar repositories for serpent-tools:
Users that are interested in serpent-tools are comparing it to the libraries listed below
- Tools to translate between different CSG geometry types☆36Updated last year
- Python ENDF Parser☆27Updated 6 months ago
- Stochastic Calculator Of Neutron transport Equation☆39Updated 3 weeks ago
- NJOY for the 21st Century☆78Updated last year
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated last week
- ☆75Updated 8 months ago
- Native plotting GUI for model design and verification☆55Updated 3 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- List of open source projects related to OpenMC☆24Updated 5 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆34Updated last month
- JADE, a novel nuclear data libraries V&V tool☆25Updated this week
- ☆29Updated this week
- curated documents pertaining to early molten salt reactor research.☆21Updated 11 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆36Updated last week
- Sampling nuclear data and uncertainty☆50Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 5 months ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated 2 weeks ago
- Nuclear data processing with legacy NJOY☆102Updated 2 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆64Updated last year
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆35Updated this week
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆136Updated this week
- ☆18Updated this week
- Direct Accelerated Geometry Monte Carlo Toolkit☆109Updated this week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆28Updated last month
- A Python package for parsing FISPACT-II output☆26Updated 11 months ago
- Convert OpenMC Geometry Components to CAD☆16Updated 2 months ago
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year