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8.15】Dr. Lingfeng He
题目:Radiation Effects in Ceramic Oxide and LWR Fuels
 
2014-08-13 | 文章来源:高性能陶瓷材料研究部        【 】【打印】【关闭

题 目:Radiation Effects in Ceramic Oxide and LWR Fuels

报告人:Dr. Lingfeng He(何灵峰)

         University of Wisconsin-Madison, Madison, WI, USA.

 间:815日(周五)上午9:30-11:00

 点:李薰楼468房间

欢迎参加!

摘要:

Uranium dioxide (UO2) is the standard material used for commercial light water reactor (LWR) fuels. The cumulative radiation damage at high temperatures causes severe degradation in the thermophysical properties of UO2 fuels, limiting their lifetime and strongly affecting operation cost. Investigating the defect evolution and fission gas transport under irradiation is of great importance in understanding the degradation of thermophysical properties of nuclear fuel.

This presentation will cover ion-beam-induced radiation effects in UO2 and its surrogate CeO2. The results of ion dose and temperature dependence of defect microstructure (dislocation loops, dislocations and gas bubbles) investigated by in situ and ex situ TEM will be presented. Particular attention will be paid to the examination of surface and grain boundary sinks, dislocation loop nature, gas bubble distribution, and stoichiometry change within the materials. A general approach to develop simple microstructure in UO2 for thermal transport measurement and phase field modeling will also be discussed.

简历:

Lingfeng He is now an Assistant Scientist at University of Wisconsin-Madison, Wisconsin, USA. Dr. He received a B.Eng. degree in Metallurgical Engineering at Central South University in China in 2003 and a Ph.D. degree in materials science at Institute of Metal Research, Chinese Academy of Sciences in 2009. His Ph.D. work was focused on the synthesis, microstructure and properties of advanced ceramic materials. He then worked as a postdoctoral research associate in the Extreme Energy-Density Research Institute of Nagaoka University of Technology, Japan, where he studied structural and functional ceramic nanocomposites. In 2011, He joined the nuclear fuel and material research group at the University of Wisconsin-Madison, where he has been studying irradiation behavior of nuclear fuels and corrosion behavior of steels and Ni-based alloys for high-temperature nuclear application. He has authored/co-authored 50 peer-reviewed papers and holds 4 Chinese patents.

 

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