Price: $49

Organizer: Joffrey Dorville (ANL)

OpenMC is a general purpose Monte Carlo neutron and photon transport simulation code. It is capable of simulating 3D models based on constructive solid geometry with second-order surfaces as well as CAD-based geometries. It also has built-in capabilities for activation/depletion to track material evolution with time. This workshop will present a brief overview of the code and its growing list of features, and a walk-through on how to setup input files using the Python API using nuclear reactor examples. The workshop will also demonstrate how to leverage powerful Python packages for post-processing of results. Participants should bring their laptop to follow along and run OpenMC. A link will be provided to access the software on a cloud computing platform.

Attendees will indeed be running jobs interactively at the workshop. We find this to be a much more enjoyable experience than watching hours of powerpoint presentations!

OpenMC is open source so there are no licensing requirements. As the description above alludes to, participants will need to have a laptop with an internet connection and a web browser, but they don't need to have anything else preinstalled.