openmc-dev / openmc_mcnp_adapterLinks
Tool for converting MCNP input files to OpenMC classes/XML
☆44Updated 3 months ago
Alternatives and similar repositories for openmc_mcnp_adapter
Users that are interested in openmc_mcnp_adapter are comparing it to the libraries listed below
Sorting:
- List of open source projects related to OpenMC☆27Updated 2 months ago
- Python ENDF Parser☆35Updated 2 weeks ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- API for parsing and post-processing many MC simulations related files☆17Updated 3 weeks ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆16Updated this week
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated last month
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆74Updated 2 months 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
- Computational inputs, reference outputs and experimental data for V&V systems☆13Updated 4 months ago
- Accelerated Discretized Geometry☆18Updated 3 weeks ago
- Native plotting GUI for model design and verification☆60Updated last week
- ENDF/B pre-processing codes (PREPRO)☆21Updated 2 years ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆40Updated last week
- ☆84Updated last year
- JADE, a novel nuclear data libraries V&V tool☆32Updated 2 months ago
- Convert OpenMC Geometry Components to CAD☆18Updated 9 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 2 years ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆39Updated 3 weeks ago
- Tools to translate between different CSG geometry types☆39Updated 3 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated 4 months ago
- Nuclear data processing with legacy NJOY☆115Updated 2 weeks ago
- OpenMC Monte Carlo Code☆18Updated 6 months ago
- open-source Sn software☆39Updated this week
- NJOY for the 21st Century☆80Updated last year
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆30Updated last month
- Stochastic Calculator Of Neutron transport Equation☆48Updated last week
- Workflow and Template Toolkit for Simulation (WATTS)☆32Updated 2 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆114Updated 6 months ago
- ☆32Updated last month