Nuclear Technical Public Seminar
Recent developments in reactor thermal-hydraulics and safety
Speaker
Dr. Jiyun Zhao
Associate Professor, Department of Mechanical and Biomedical Engineering, City University of Hong Kong.
Programme Highlights
The research and development in reactor thermal-hydraulics and safety is crucial to ensure safe and economic operation of existing plants and develop next generation nuclear systems. In this seminar, the issues and R&D requirements facing the existing nuclear power reactors will be discussed, and the current methods on the reactor modeling and simulations used in the industry will be introduced together with the future trend. The design features of Gen-III reactors, i.e. AP1000 and ESBWR, will be introduced. Then, the advanced fluids applications (supercritical fluids and nanofluids) in developing advanced nuclear systems such as Gen-IV supercritical water cooled reactors (SCWR) will be discussed. Finally, the researches on severe accidents and radioactive materials dispersions will be talked.
Registration & Enquiries
The seminar is free of charge and on a first-come-first served basis. Online free registration is via, http://www.hkarms.org/Registration/EventRegister.php?Event=76. For enquiries, please contact Dr Louis Liu, info@hkns.hk.
Disclaimer
All information and views expressed by speakers and in their conference materials do not reflect the official opinion and position of HKIE. No responsibility is accepted by the HKIE or their publisher for such information and views including their accuracy, correctness and veracity.