清華大學材料科學與工程研究院《材料科學論壇》

學術報告

報告題目：Irradiation degradation of reactor components at microscopic scale and proactive ageing management

報告人：Dongyue CHEN（Department of Nuclear Engineering and Management, School of Engineering, the University of Tokyo）

報告時間：2018年12月4日（星期二）上午10:00

報告地點：清華大學逸夫技術科學樓A205學術報告廳

聯系人：李正操老師（62772233）

歡迎廣大師生踴躍參加！

報告摘要：

Material degradation is the most important issue when considering the safety of nuclear reactors. As an example, stainless steel endures high temperature and high irradiation dose during its service as the structural material in reactor core, and may crack after long service time. In this talk, cutting-edge techniques, such as in situ transmission electron microscopy (in-situ TEM) and atom probe tomography (APT), are utilized to analyze the ageing process of stainless steel under irradiation at microscopic scale. The connection between microscopic defects and macroscopic degradation is discussed to allow a more proactive way of reactor ageing management.

報告人簡介：

Dr. Dongyue CHEN is an assistant professor in the Department of Nuclear Engineering and Management, School of Engineering, the University of Tokyo. In 2012, he got his master degree in the Department of Material Science and Engineering, Tsinghua University. In 2015, he got his PhD degree in The University of Tokyo.
His research focuses on irradiation mechanisms and ageing prediction. His interests cover stainless steel components and reactor pressure vessels in light water reactors, and graphites in high temperature gas cooled reactors. He utilizes cutting-edge tools to analyze the degradation process at microscopic scale, and compares them with modeling.