svalinn / pydagmc
A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
☆12Updated 5 months ago
Related projects ⓘ
Alternatives and complementary repositories for pydagmc
- List of open source projects related to OpenMC☆21Updated 2 months ago
- OpenMC Monte Carlo Code☆14Updated 2 months ago
- Python ENDF Parser☆26Updated 3 months ago
- ☆17Updated 3 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- A Python package for parsing FISPACT-II output☆25Updated 8 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆36Updated 3 weeks ago
- Native plotting GUI for model design and verification☆48Updated 3 weeks ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆57Updated last month
- open-source Sn software☆21Updated this week
- ☆29Updated last year
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 2 months ago
- Thermal Scattering Library created with NJOY+NCrystal☆9Updated 2 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆32Updated this week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆36Updated 4 months ago
- Stochastic Calculator Of Neutron transport Equation☆36Updated last month
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 2 months ago
- Sampling nuclear data and uncertainty☆48Updated last month
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆13Updated 3 years ago
- Tools to translate between different CSG geometry types☆35Updated last year
- Meshing library for nuclear workflows☆42Updated last month
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 5 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆34Updated 3 weeks ago
- JADE, a novel nuclear data libraries V&V tool☆23Updated this week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆32Updated 3 years ago
- curated documents pertaining to early molten salt reactor research.☆21Updated 8 months ago
- OpenMC wrapped as a Moose App☆16Updated last year
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆38Updated last year