ahmedkmadani / OpenMCProject
Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/
☆12Updated 5 years ago
Alternatives and similar repositories for OpenMCProject:
Users that are interested in OpenMCProject are comparing it to the libraries listed below
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- List of open source projects related to OpenMC☆24Updated 6 months ago
- Collection of scripts for managing data for OpenMC☆29Updated last month
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated 2 weeks ago
- ENDF/B pre-processing codes (PREPRO)☆17Updated last year
- a companion for writing MCNP input decks☆11Updated 3 years ago
- Native plotting GUI for model design and verification☆55Updated last month
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆60Updated last week
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆33Updated 2 months ago
- Python ENDF Parser☆28Updated 7 months ago
- Sampling nuclear data and uncertainty☆50Updated last month
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆13Updated 7 years ago
- Tools to translate between different CSG geometry types☆36Updated last year
- Convert OpenMC Geometry Components to CAD☆16Updated 3 months ago
- Toolkit for reading and interacting with ENDF-6 formatted files☆37Updated last week
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆39Updated 2 months ago
- A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles☆10Updated 9 months ago
- Catalogs a plethora of reactor inputs for OpenMC☆23Updated this week
- ☆76Updated 9 months ago
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Updated 3 years ago
- OpenMC wrapped as a Moose App☆16Updated last year
- Example Jupyter notebooks for OpenMC☆35Updated this week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆14Updated last month
- Nuclear data processing with legacy NJOY☆103Updated last month
- curated documents pertaining to early molten salt reactor research.☆22Updated 11 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 6 months ago
- Stochastic Calculator Of Neutron transport Equation☆40Updated last month
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- ☆18Updated last week