openmc
Here are 38 public repositories matching this topic...
A Python package that finds and converts OpenMC tally units.
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Mar 7, 2022 - Python
Combines open source packages to produce an automated fusion specific neutronics workflow
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May 31, 2022 - Python
The jupyter notebook contains python code which creates a BWR square assembly with a 3-by-3 fuel-less center.
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Jul 25, 2022 - Jupyter Notebook
A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
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Dec 9, 2022 - Python
Nuclear data processing with ACEMAKER, FRENDY and NJOY
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Apr 9, 2023 - Jupyter Notebook
Student research repository for independent research of the material attractiveness of prospective fuel to be used in microreactors
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May 7, 2023 - Jupyter Notebook
ENRICO: Exascale Nuclear Reactor Investigative COde
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Jul 21, 2023 - C++
Code to simulate the flux through cylinders with the MUTR Neutron Imager
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Aug 10, 2023 - Jupyter Notebook
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
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Aug 15, 2023 - Python
This repository contains a beginner-friendly tutorial for OpenMC, a Monte Carlo particle transport simulation code widely used in nuclear engineering.
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Jan 21, 2024 - Jupyter Notebook
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