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美国俄亥俄州立大学张金锁教授讲座通知
澳门新永利官网:2015-05-21 18:26:43 点击量:

应核科学与技术学院曹良志教授邀请,美国俄亥俄州立大学张金锁教授将于2015年5月26日~5月28日来我校访问交流,并做学术报告。欢迎大家参加。

讲座题目:Structural Materials Degradation in Liquid Metal

报告人:Prof. Jinsuo Zhang The Ohio State University, USA

讲座时间:5月27日(周三)上午10:10

讲座地点:化工学院104会议室(教学二区西北角的红色小楼)

报告内容简介:

Abstract:

When a steel is exposed to liquid metal, some of its constituents can dissolve into the liquid and may or may not react with the impurities in the liquid metal, and also the liquid metal can penetrate into the steel along the grain boundaries or other defects, which changes the microstructure, composition and morphology at the steel surfaces. Therefore, the properties of the material to some depth into the material can be changed by the liquid metal. Such changes, known as liquid metal degradation, can become significant with time, and may eventually lead to material failure. The present study discuss structural material degradation issues in a liquid metal-cooled nuclear power system. First, the materials degradation mechanisms by liquid metal will be identified. Then based on the current understanding, the approach for developing a system model to predict the liquid metal degradation such as corrosion will be discussed. The paper presents mathematical analysis of liquid metal corrosion, including species transport in solid steels, in flowing liquid metals, and mass exchange at liquid/solid interface, as well as the liquid metal penetration. Both light liquid metal/alloy (sodium and sodium-potassium) and heavy liquid metal/alloy (liquid lead and lead-bismuth) are considered. Impurity effects, such as oxygen effects, on liquid metal degradation are also discussed.

Biographies

Prof. Jinsuo Zhang has been an associate professor of the nuclear engineering program at The Ohio State University since September, 2012. Dr. Zhang received his doctoral degree in 2001 at Zhejiang University, China. In the same year, he joined the Center for Non-linear Studies at the Los Alamos National Laboratory as a postdoctoral research associate, and was a staff scientist of the Nuclear Engineering & System Group at the same national laboratory through 2004 to 2012. Dr. Zhang was an adjunct research professor from 2004 to 2007 and then a visiting professor in 2007 at the University of Nevada at Las Vegas. In addition, Dr. Zhang was an adjunct faculty member of the Ohio University through 2009-2013. Dr. Zhang’s research activities focus on materials corrosion, electro-chemical separation, advanced nuclear fuel materials and nuclear coolant technology.

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