美国弗吉尼亚理工大学张金锁教授将于2017年06月12-14日来我校进行学术访问，并针对先进核反应堆结构材料高温腐蚀的最新研究进展进行学术报告，届时欢迎各位师生参与交流。

报告题目：Materials Corrosion in Nuclear Engineering

时间：2017年06月13日 16:00-17:30

地点：yl34511线路中心化工行政楼302会议室

报告内容简介：

All the nuclear coolants are corrosive, especially for the high temperature nuclear reactor systems. However, the corrosion mechanisms for different coolants can be very different, which depends on the coolant properties. For example, the major mechanism of liquid metal corrosion is physical dissolution, while the major mechanism of molten salt and high temperature water corrosion is an electrochemical process. Due to the different mechanisms, the mitigation/control methodologies for different coolant systems will be different. This seminar will focus on liquid metal and molten salt corrosion, including the corrosion phenomena, major corrosion types and mechanisms as well as the corrosion mitigation methods. The seminar will also address the stress corrosion cracking in high temperature water and discuss corrosion/precipitation in a nuclear coolant system which is a closed loop.