Keynote Speaker I


Prof. Hartmut Hinz
Frankfurt University of Applied Sciences, Germany

Project leader for the development of high voltage electrical systems for concept fuel cell

Program director of the study program electrical engineering


H. Hinz received the diploma degree in electrical engineering from the University of Applied Sciences, Aachen and the Ruhr University, Bochum in Germany in the years 1990 and 1994 respectively. He received the Ph.D. degree from the Technical University, Darmstadt in Germany in 2000.
Between 1999 and 2009 he was with General Motors Fuel Cell Activities, most recently as project leader for the development of high voltage electrical systems for concept fuel cell. In 2009 he was appointed as a Professor for power electronics at the University of Applied Sciences, Frankfurt in Germany. Since 2011 he is the program director of the study program electrical engineering. Since 2010 he is a visiting Professor (flying faculty) at the Vietnamese-German University in Ho-Chi-Minh City, Vietnam. His research interests are in the areas power electronics, modeling and decentralized power generation.




Keynote Speaker II


Prof. Di Yun
Xi'an Jiaotong University, China

Outstanding scholar in the ‘Youth Talent Plan’

Director of ‘Key R&D Project Issues’ for the Ministry of Science and Technology


Dr. Di Yun is a professor in the Department of Nuclear Science and Technology of Xi'an Jiaotong University. He is an outstanding scholar in the ‘Youth Talent Plan’ and served as the director of ‘Key R&D Project Issues’ for the Ministry of Science and Technology. Professor Yun received his PhD in Nuclear Engineering from University of Illinois at Urbana-Champaign in 2010. He worked at Argonne National Laboratory as a nuclear engineer in the Nuclear Engineering Division from 2010 to 2015. He joined Xi'an Jiaotong University in 2015.

Professor Yun focuses on developing advanced nuclear fuel materials. On the theoretical front, he explored a novel approach, multi-atom nucleation, to describe gas bubble nucleation process in metallic nuclear fuel materials; he also investigated in fundamental aspects of nuclear fuel performance modeling and applied multi-scale simulation methods to address fuel performance issues. On the experimental front, he is developing nitride coatings for advanced nuclear fuel systems for light water reactors and has received technological awards in this area; he is currently pushing for development of such materials into real engineering application scenarios.


Speech Title "A Novel Metallic Fuel Conceptual Design for the Travelling Wave Reactor"

In order to improve the economics of fast reactors and their associated fuel cycles, achieving ultra-high fuel burn-up and ultra-long fuel life has been a topic of significant interests. One example of such reactor design concept is the Travelling Wave Reactor (TWR). However, the very high fast neutron irradiation dose on the fuel cladding materials has posed a major challenge to such reactor conceptual designs. The initial fuel cladding fast neutron irradiation dose design parameter for the TWR was set to be more than 600 dpa, which greatly exceeds the current limit on this design parameter obtained from past reactor operation experience (200 dpa). A lot of work have been conducted lately to attempt to improve the fast neutron irradiation dose limit on fast reactor fuel cladding materials. In this work, a new angle is taken to help achieve ultra-high fuel burn-up. That is, to rely on the low swelling property of the spinodal decomposed U-50Zr metallic fuel under irradiation environments for steady-state operation (below the phase change temperature of U-50Zr fuel to transit to the gamma phase) and then vent fission gas at certain fuel burn-up intervals, once fission gas has accumulated in the fuel matrix, by manually creating a transient scenario and raising fuel temperature for a relatively short time span. Such operation serves two purposes that will help to drive a complete release of fission gas, one is the high temperature and the other is the phase change of U-50Zr metallic fuel. Computer simulations have shown that once fuel temperature is over 750 degree Celsius, large amount of fission gas will be released in metallic U-Zr fuel, and phase transition is also helpful to drive fission gas to interfaces which will facilitate gas release in large amount. A fuel performance analysis has been conducted to support such fuel design concept to demonstrate that the fuel temperature can be well controlled such that a nearly 100% of fission gas release may be achieved while the cladding creep and swelling at this transient scenario will not significantly degrade its mechanical properties. This operation, when a nearly 100% venting of fission gas can be achieved periodically, will lower the Fuel Cladding Mechanical Interaction (FCMI) to the maximum extent. Consequently, the cladding materials will experience much less FCMI compared to that in the conventional U-10Zr/HT-9 sodium fast reactors, and thus building a low stress environment for the cladding materials so that a higher fast neutron irradiation dose may be achieved even on existing candidate fast reactor cladding materials. A detailed analysis is still necessary to assess the effect of lowering FCMI on extending the fast neutron irradiation dose limit of current or future fast reactor fuel cladding materials.



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