Last week, John Billingsley from our Radiation Shielding team ran a full-day internal training session on OpenMC - a Monte Carlo particle transport code used for simulating neutron and photon transport. 

OpenMC is a community-developed, open-source code that has gained popularity for its flexibility, active development, and integration with Python. It is widely adopted in the fusion energy sector, where its ability to perform high-fidelity simulations makes it a valuable tool for design and analysis. Increasingly, OpenMC is also being adopted in other areas of the nuclear industry as interest in modern, open-source tools continues to grow. 

The training was well attended by members of both the shielding and criticality teams and was structured as a mix of short lectures and hands-on exercises. John introduced the main concepts of building models with OpenMC, including using its Python API to define geometries and materials, set up source terms, and run transport simulations. Attendees had the chance to follow along with practical examples and try building their own models themselves throughout the day. 

The informal workshop format encouraged plenty of discussion, and it was a great opportunity for colleagues to explore how OpenMC might be applied in future projects. It was also a valuable chance for Cerberus to build upon our existing experience and expand our capabilities in the use of modern Monte Carlo transport codes. 

Thanks to John for putting together such an informative and engaging session and for helping more of the team get familiar with OpenMC.