OpenMC Monte Carlo Code
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Updated
Jun 27, 2024 - Python
OpenMC Monte Carlo Code
Native plotting GUI for model design and verification
Create DAGMC geometry from CAD
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.
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
List of open source projects related to OpenMC
Workflow and Template Toolkit for Simulation (WATTS)
openmc msr depletion capabilities example
Tool for converting MCNP input files to OpenMC classes/XML
Package Manager for Nuclear Engineering Development
Radiation transport simulations with a human phantoms in OpenMC. Meshes are created in Cubit Coreform. The phantom used in this project is obtained from: https://www.icrp.org/publication.asp?id=ICRP%20Publication%20145
This repository contains a beginner-friendly tutorial for OpenMC, a Monte Carlo particle transport simulation code widely used in nuclear engineering.
Openmc-FEnicsx for muLtiphysics tutorIAl
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