IAEA-NDS / endf-parserpyLinks
Python package for reading, writing, verifying and translating ENDF-6 formatted files
☆20Updated last month
Alternatives and similar repositories for endf-parserpy
Users that are interested in endf-parserpy are comparing it to the libraries listed below
Sorting:
- Python ENDF Parser☆35Updated 3 weeks ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆31Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆44Updated 3 months ago
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- List of open source projects related to OpenMC☆27Updated 3 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆74Updated 2 months ago
- NJOY for the 21st Century☆80Updated last year
- JADE, a novel nuclear data libraries V&V tool☆32Updated 2 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- Stochastic Calculator Of Neutron transport Equation☆50Updated last week
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- Accelerated Discretized Geometry☆18Updated 3 weeks ago
- Nuclear data processing with legacy NJOY☆117Updated last week
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Convert OpenMC Geometry Components to CAD☆18Updated 9 months ago
- Sampling nuclear data and uncertainty☆52Updated this week
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10Updated 3 years ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆158Updated last week
- ☆84Updated last year
- ENDF-6 data interface and nuclear data evaluation assist code☆16Updated 4 months ago
- open-source Sn software☆40Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 11 months ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.☆102Updated 6 months ago
- Native plotting GUI for model design and verification☆60Updated 2 weeks ago