openmc
There are 41 repositories under openmc topic.
openmc-dev/openmc
OpenMC Monte Carlo Code
fusion-energy/neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
fusion-energy/paramak
Create parametric 3D fusion reactor CAD and neutronics models
enrico-dev/enrico
ENRICO: Exascale Nuclear Reactor Investigative COde
openmc-dev/plotter
Native plotting GUI for model design and verification
stellarmesh/stellarmesh
Meshing library for nuclear workflows
openmc-dev/openmc_mcnp_adapter
Tool for converting MCNP input files to OpenMC classes/XML
fusion-energy/openmc-plasma-source
Creates a plasma source as an openmc.source object from input parameters that describe the plasma
fusion-energy/cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
watts-dev/watts
Workflow and Template Toolkit for Simulation (WATTS)
fusion-energy/neutronics_material_maker
A tool for making reproducible materials and standardizing use across several neutronics codes
openmc-dev/openmc-ecosystem
List of open source projects related to OpenMC
ukaea/neutronics_material_maker
A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
fusion-energy/fusion_neutronics_workflow
Combines open source packages to produce an automated fusion specific neutronics workflow
openmc-data-storage/openmc_data_downloader
A Python package for downloading h5 cross section files for use in OpenMC.
ERMETE-Lab/MP-OFELIA
Openmc-FEnicsx for muLtiphysics tutorIAl
fusion-energy/openmc_source_plotter
A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
nukehub-dev/nukebox
Package Manager for Nuclear Engineering Development
openmc-dev/fes-project-ii
Project repository for "An Open Source Nuclear Modeling Ecosystem to Support Fusion Pilot Plant Design" collaboration between MIT and ANL
fusion-energy/openmc-dagmc-wrapper
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
fusion-energy/inertial_fusion_openmc_dagmc_paramak_example
A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
fusion-energy/openmc_tally_unit_converter
A Python package that finds and converts OpenMC tally units.
openmsr/pincell_msr
openmc msr depletion capabilities example
fusion-energy/stl_to_h5m
Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.
eealanoca/openmc_first_tutorial
This repository contains a beginner-friendly tutorial for OpenMC, a Monte Carlo particle transport simulation code widely used in nuclear engineering.
egor1abs/openmc_sdef_parser
MCNP SDEF to OpenMC conversion tool
Fuad-HH/BWR_SqauredArraySubChannel-OpenMC
The jupyter notebook contains python code which creates a BWR square assembly with a 3-by-3 fuel-less center.
fusion-energy/openmc_cell_segmenter
Segments cells into smaller cells. Useful for redefining geometry for cell based shutdown dose rate simulations.
AI-Pranto/ESFR_Model
European SFR core sub-assembly model
AI-Pranto/OpenMC-termux
Run OpenMC on Android phone
CJD-1113/Neutron-Imaging-Simulation
Code to simulate the flux through cylinders with the MUTR Neutron Imager
Toshi-23/HYPR-Capstone-2023
USNA Engineering Design Capstone. OpenMC simulations for the High Flux Production Reactor (HYPR) design concepts.
Toshi-23/Proliferation_Research
Student research repository for independent research of the material attractiveness of prospective fuel to be used in microreactors
morten-nygaard/msfr
OpenMC model of the EVOL reference MSFR. Includes code used to simulate and plot results in DTU student project "Impact of temperature feedback on reactivity parameters in the Molten Salt Fast Reactor" by Morten Nygaard (ongoing per June 2024). See "README.md" for detailed description of code and project.
etare8/neutronic-openmc-stuff
Neutronics using OpenMC Monte Carlo Code