watts-dev / wattsLinks
Workflow and Template Toolkit for Simulation (WATTS)
☆33Updated 6 months ago
Alternatives and similar repositories for watts
Users that are interested in watts are comparing it to the libraries listed below
Sorting:
- List of open source projects related to OpenMC☆30Updated 7 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Native plotting GUI for model design and verification☆64Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last week
- Python ENDF Parser☆39Updated 2 months ago
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆35Updated 6 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 10 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆49Updated this week
- Tools to translate between different CSG geometry types☆40Updated 7 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Updated 3 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 3 months ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated 3 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 3 weeks ago
- Open-source Sn software☆53Updated last week
- Stochastic Calculator Of Neutron transport Equation☆53Updated 3 weeks ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆84Updated last month
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆172Updated 3 weeks ago
- Collection of scripts for managing data for OpenMC☆38Updated 2 weeks ago
- Accelerated Discretized Geometry☆22Updated 3 weeks ago
- ☆33Updated 5 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆25Updated last year
- NJOY for the 21st Century☆84Updated last year
- Sampling nuclear data and uncertainty☆54Updated 3 months ago
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- JADE, a novel nuclear data libraries V&V tool☆34Updated 3 weeks ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago