James Allen Anderson Seminar Series: Constantly Innovation of Safety Technology in Nuclear Reactors

Since the accident at Fukushima, one major goal of reactor safety research has been the development of more accident tolerant technologies, coupled with other thermal hydraulic methods that can mitigate or delay fuel degradation during a Beyond Design Basis Accident. One major effort has been focused on the development of claddings and coatings for light water reactor fuel cladding. FeCrAl cladding, Chromium-coated Zircaloy clad are of the leading options. In this work, the MELCOR systems code (version 1.8.6 UDGC) is used to evaluate the performance of FeCrAl cladding and Cr-coated Zircaloy clad as compared to Zircaloy clad for a Pressurized Water Reactor, PWR (i.e., Surry) for a Station Blackout (SBO) accident scenario. Passive cooling and FLEX engineered the system, such as core recovery cooling injection and auxiliary feedwater injection, are also considered during the ATF performance analysis for extra copying time. Our future work is focused on the uncertainty analysis of the oxidation rate data, coating failure criteria, and severe accident modeling limitations in order to better quantify ATF (Accident Tolerant Fuels) clad benefits.

Dr. Jun Wang is a research scientist in the Department of Engineering Physics at the University of Wisconsin-Madison. He is working on several research projects funded by Department of Energy (DOE) about nuclear power plant safety technologies, especially the development of accident tolerant fuels technology. Dr. Wang has over 50 publications of book, government report, peer-reviewed journal and conference articles at the areas of nuclear safety, accident tolerant fuels, Gen IV designs, and two-phase flow experiments. Dr. Wang’s work gets over 190 citations, with h-index 8. Dr. Wang services as an editor for Elsevier Nuclear Energy Book Program; associate editor for the journal Frontiers in Energy Research Nuclear Energy; editor on board for the journals Open Engineering, Experimental and Computational Multiphase Flow, and World Journal of Nuclear Science and Technology.

This seminar series is named after Dr. James Allen Anderson, who contributed significantly in the establishment of the first undergraduate Nuclear Engineering Program in a Historically Black College/University (HBCU).

Jun Wang

Department of Engineering Physics

University of Wisconsin Madison

ECSC Rm 336, Thursday,  5/30/2019, 11:00am-12 pm, Free Pizza and Drink