CORE-GATECH-GROUP / serpent-toolsLinks
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
☆61Updated 2 months ago
Alternatives and similar repositories for serpent-tools
Users that are interested in serpent-tools are comparing it to the libraries listed below
Sorting:
- NJOY for the 21st Century☆84Updated last year
- Stochastic Calculator Of Neutron transport Equation☆53Updated last week
- Python ENDF Parser☆39Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆52Updated last week
- Tools to translate between different CSG geometry types☆40Updated 6 months ago
- ☆32Updated 4 months ago
- Nuclear data processing with legacy NJOY☆121Updated 3 months ago
- Native plotting GUI for model design and verification☆64Updated last week
- List of open source projects related to OpenMC☆30Updated 6 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆40Updated 2 months ago
- API for parsing and post-processing many MC simulations related files☆17Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- JADE, a novel nuclear data libraries V&V tool☆34Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Accelerated Discretized Geometry☆19Updated last week
- 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☆53Updated 2 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 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…☆42Updated 11 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 5 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated last month
- open-source Sn software☆50Updated last week
- Convert OpenMC Geometry Components to CAD☆20Updated last year
- Format description for ACE nuclear data files☆22Updated 3 years ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆21Updated 5 months ago
- Computational inputs, reference outputs and experimental data for V&V systems☆15Updated 2 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆171Updated 3 weeks ago
- curated documents pertaining to early molten salt reactor research.☆24Updated last year