watts-dev / wattsLinks
Workflow and Template Toolkit for Simulation (WATTS)
☆32Updated 2 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☆27Updated 2 months ago
- open-source Sn software☆39Updated this week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- Python ENDF Parser☆35Updated 2 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆33Updated last month
- Native plotting GUI for model design and verification☆60Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated 3 weeks ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Sampling nuclear data and uncertainty☆52Updated 2 weeks ago
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 3 months ago
- Stochastic Calculator Of Neutron transport Equation☆48Updated this week
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆22Updated 3 months ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆74Updated 2 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- Accelerated Discretized Geometry☆18Updated 3 weeks ago
- Collection of models for reactor physics benchmarks☆54Updated 10 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated 2 weeks ago
- Convert OpenMC Geometry Components to CAD☆18Updated 9 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 10 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆66Updated 2 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆20Updated last month
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆114Updated 6 months 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 8 months ago
- ☆32Updated last month