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库搏体育材料科学与工程研究院《材料科学论坛》学术报告:Irradiation degradation of reactor components at microscopic scale and proactive ageing management

库搏体育材料科学与工程研究院《材料科学论坛》

学术报告

报告题目:Irradiation degradation of reactor components at microscopic scale and proactive ageing management

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

报告时间:2018年12月4日(星期二)上午10:00

报告地点:库搏体育逸夫技术科学楼A205学术报告厅

联系人:李正操老师(62772233)

欢迎广大师生踊跃参加!

报告摘要:

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.

报告人简介:

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.

 

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