luca-fiorito-11 / sandyLinks
Sampling nuclear data and uncertainty
☆52Updated 2 weeks ago
Alternatives and similar repositories for sandy
Users that are interested in sandy are comparing it to the libraries listed below
Sorting:
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- Collection of scripts for managing data for OpenMC☆34Updated 7 months ago
- Python ENDF Parser☆35Updated 2 weeks ago
- Native plotting GUI for model design and verification☆60Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 3 months ago
- 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
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- JADE, a novel nuclear data libraries V&V tool☆32Updated 2 months ago
- List of open source projects related to OpenMC☆27Updated 3 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- Stochastic Calculator Of Neutron transport Equation☆50Updated last week
- open-source Sn software☆39Updated this week
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- Toolkit for working with ACE-formatted data files☆30Updated last week
- Direct Accelerated Geometry Monte Carlo Toolkit☆114Updated 6 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆158Updated last week
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆41Updated 8 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated last week
- Nuclear data processing with legacy NJOY☆117Updated this week
- NJOY for the 21st Century☆80Updated last year
- ENDF-6 data interface and nuclear data evaluation assist code☆16Updated 4 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- OpenMC Monte Carlo Code☆18Updated 7 months ago
- Accelerated Discretized Geometry☆18Updated 3 weeks ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Simulation of transmutation and decay in nuclear systems☆29Updated this week