Dongjun Park received a doctorate in materials science & engineering in 2008 from the Korea Advanced Institute of Science and Technology. After a year of post-doctoral position at the Max Planck Institute in Germany (2008-2009), he joined the Korea Atomic Energy Research Institute and has been working on nuclear fuel cladding related research to date. He is currently a Visiting Scholar at the Center for Nuclear Materials and Fuel Cycle Research, Virginia Tech.
His research focuses on development of advanced Zr-based alloy fuel claddings for light water reactors and loss-of-coolant accident simulating tests. In addition, he conducted a high temperature oxidation test of various materials for the nuclear industry and studied their oxidation behaviors. His most recent research focuses on the surface modification process for nuclear fuel cladding using 3D laser coating technique.