This event is presented by the IAEA.

Hosted by MIT and Argonne National Laboratory

A central problem in nuclear engineering is the simulation of the transit of neutron and photon radiation through devices. Several programs have been written over the past few decades to solve this problem in a generalized fashion via the Monte Carlo method, but only one is not centralized and allows anyone to hack the code and distribute it to others: OpenMC.

For this reason, OpenMC is excellent for students. We'll give an overview of getting OpenMC running on your computer, creating input to the program, and analyzing the results. Particularly, we'll look at a reactor criticality problem and a photon shielding problem, and how OpenMC's python interface enables streamlined analysis compared to older Monte Carlo codes.

Location: Hiwassee

Cost: $0

Attendees: 40