paulromano / endf-pythonLinks
Python ENDF Parser
☆34Updated 11 months ago
Alternatives and similar repositories for endf-python
Users that are interested in endf-python are comparing it to the libraries listed below
Sorting:
- List of open source projects related to OpenMC☆26Updated last month
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆43Updated last month
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Accelerated Discretized Geometry☆17Updated last week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- JADE, a novel nuclear data libraries V&V tool☆31Updated last month
- Native plotting GUI for model design and verification☆59Updated 5 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆71Updated 3 weeks ago
- Convert OpenMC Geometry Components to CAD☆18Updated 7 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…☆40Updated 7 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated this week
- ENDF/B pre-processing codes (PREPRO)☆19Updated last year
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆11Updated 2 months ago
- open-source Sn software☆36Updated this week
- Stochastic Calculator Of Neutron transport Equation☆45Updated this week
- Sampling nuclear data and uncertainty☆52Updated 3 weeks ago
- Tools to translate between different CSG geometry types☆39Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 3 weeks ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated 2 weeks ago
- OpenMC wrapped as a Moose App☆16Updated 2 years ago
- Computational inputs, reference outputs and experimental data for V&V systems☆13Updated 3 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆59Updated 3 months ago
- NJOY for the 21st Century☆79Updated last year
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- A Python package for parsing FISPACT-II output☆29Updated last month
- Nuclear data processing with legacy NJOY☆111Updated last month