厘米教育
中山大学 创办时间:1924年 主管部门:教育部 所属地区:中国-广州-珠海-深圳 类别:公立大学 学校类型:综合类 官网: 学校代码:10558 邮编:510275 招生电话:020-84112828 地址:广州市新港西路135号 查看地图

点评 123

关注 3251

浏览 

中法核工程与技术学院第 40 期学术午餐会

Research on heat transfer and melting of the reactor core and lower head in SA

作者:厘米教育 来源:中山大学| 2017-02-27 17:06:27

 

 
中法核工程与技术学院第 40 期学术午餐会
40
th
Academic Lunch Seminar of Sino-French Institute of Nuclear Engineering
and Technology
 
 
Topic:
Research on heat transfer and melting of the reactor core and lower head in SA
Speaker: Prof. Xiaoying Zhang
Time: 12:40 14:00, Friday 3 March
Venue: F309 in the teaching building, Zhuhai Campus, SYSU
Organizer: Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University
Language:English
 
Abstract:
IVR-ERVC is one important safety design in advanced PWR for keep the
integrity of reactor pressure vessel(RPV) and to prevent release of radiosity material
into the environment in case of severe accident. This speech talk about a research on
coupling study the radiative heat transfer in melting process of the overall structure in
RPV of PWR, and to develop analysis code. Heat transfer in the reactor core will be
modeled with a 2D transient conduction of fuel rods, where the radiative heat transfer
in the core will be computed with the net radiation analysis model inside a grey wall
enclosure, and radiative properties of the steam and melt particles will be computed
with wide band model and Mie theory, respectively. A 2D axisymmetric heat
conduction model with moving boundary will be used for the lower head wall to
analyze the coupling heat transfer from the dual melt pool to the wall, and the outer
coolant eventually. A detailed temperature increasing and the melting processes of the
core and lower head during a long time after severe accident will be shown.
 
 
About the speaker:
Zhang Xiaoying, Professor. She got a PHD in Thermal Energy and
Power Engineering Department from Beihang University. Now she’s the responsible
professor of Reactor Thermal Hydraulic Lab in IFCEN. Her research major is reactor
thermal hydraulic and safety study.