luca-fiorito-11 / sandyLinks
Sampling nuclear data and uncertainty
☆53Updated 2 months ago
Alternatives and similar repositories for sandy
Users that are interested in sandy are comparing it to the libraries listed below
Sorting:
- Collection of scripts for managing data for OpenMC☆38Updated last week
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated 3 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- Python ENDF Parser☆39Updated last month
- Native plotting GUI for model design and verification☆64Updated 2 weeks ago
- List of open source projects related to OpenMC☆30Updated 6 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- Stochastic Calculator Of Neutron transport Equation☆53Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Updated last month
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 2 months ago
- JADE, a novel nuclear data libraries V&V tool☆34Updated last week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Open-source Sn software☆52Updated last week
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- NJOY for the 21st Century☆84Updated last year
- OpenMC Monte Carlo Code☆23Updated 10 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last month
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated this week
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆171Updated this week
- Catalogs a plethora of reactor inputs for OpenMC☆34Updated 9 months ago
- Nuclear data processing with legacy NJOY☆122Updated 3 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆81Updated last week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated 2 months ago
- Toolkit for working with ACE-formatted data files☆30Updated 3 months ago
- Some Monte Carlo tools☆52Updated 3 weeks ago