luca-fiorito-11 / sandyLinks
Sampling nuclear data and uncertainty
☆52Updated last week
Alternatives and similar repositories for sandy
Users that are interested in sandy are comparing it to the libraries listed below
Sorting:
- Python ENDF Parser☆36Updated last month
- Native plotting GUI for model design and verification☆60Updated last month
- Collection of scripts for managing data for OpenMC☆35Updated 8 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆46Updated this week
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated this week
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 2 months ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 4 years ago
- Stochastic Calculator Of Neutron transport Equation☆51Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Direct Accelerated Geometry Monte Carlo Toolkit☆116Updated 7 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 5 months ago
- JADE, a novel nuclear data libraries V&V tool☆32Updated last week
- open-source Sn software☆42Updated this week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated this week
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 2 months ago
- NJOY for the 21st Century☆80Updated last year
- Accelerated Discretized Geometry☆18Updated this week
- Nuclear data processing with legacy NJOY☆117Updated 3 weeks ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated 2 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆159Updated last month
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆41Updated 9 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 2 weeks ago
- ☆32Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆77Updated 2 months ago