banner

中法核工程与技术学院第113期学术午餐会

Nuclear materials in Molten Salt Reactor

发布人:中法核工程与技术学院
主题
Nuclear materials in Molten Salt Reactor
活动时间
-
活动地址
F309 in the teaching building, Zhuhai Campus, SYSU
主讲人
Dr.Miu Liu(刘敏)

中法核工程与技术学院第113期学术午餐会

113th Academic Lunch Seminar of Sino-French Institute of Nuclear Engineering and Technology

 

Topic: Nuclear materials in Molten Salt Reactor

Speaker:Dr.Miu Liu(刘敏)

Time:12:40—13:30,Friday Oct 18,2019

Venue: F309 in the teaching building, Zhuhai Campus, SYSU

Organizer: Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University

Language: English / Chinese

 

 

Abstract:

Molten salt reactor (MSR) is a promising new type of high temperature nuclear reactor that was originally proposed by the Generation IV International Forum due to its high energy conversion efficiency, inherent safety feature, and application of the thorium fuel. However, major components for MSR are working in the extreme environments such as high temperature, molten fluoride salt and neutron irradiation, which is a great challenge for nuclear materials in MSR. This speaking will start from the introduction of candidate materials for MSR. The microstructure, irradiation damage and corrosion behavior of these materials will also be discussed.

 

About the speaker:

Dr. Liu obtained his Ph. D. from University of Chinese Academy of Sciences (Shanghai Institute of Applied Physics, Chinese Academy of Sciences), Shanghai, in 2013. Before joining the IFCEN, he worked for Shanghai Institute of Applied Physics, Chinese Academy of Sciences. His research interests include irradiation damage and corrosion behavior of nuclear materials.