Learn the fundamentals of neutron transport simulation using the open-source Monte Carlo code OpenMC. Students will learn the basics of how a Monte Carlo solver can be used to solve for neutron flux, reaction rates, and multiplication factor using a Pressurized Water Reactor (PWR) pincell.

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• A computer to run a pre-installed version of OpenMC through a web browser (Jupyter Notebook).
• Basic knowledge of neutron transport.
• Basic knowledge of programming with Python.

By the end of the workshop, participants will:

• Understand the basics of the Monte Carlo method for neutron transport.
• Be able to build reactor simulations using OpenMC.
• Create tallies and visualisations to gain intuition about nuclear systems.

• 60 min: Introduction to the Monte Carlo method and OpenMC.
• 30 min: Materials and geometry for a PWR pincell.
• 15 min: Break.
• 30 min: Running a PWR pincell.
• 60 min: Tallies and visualisation.