Faculty Profile
 
  HUANG Qunying
     
Department: Insititute of Nuclear Energy Safety technology, Chinese Academy of Sciences
Mailing Address:
350 Shushanhu Road Hefei 230031, Anhui, P. R. China
Postal Code:
230031
Phone:
0551-65593328
Fax:
86-551-5593681
Homepage:
http://www.fds.org.cn/membercont.asp?did=297
 
       

Research Profile

unying HUANG, Professor, working at the Institute of Plasma Physics, Chinese Academy of Sciences. She gained the B.E., M.E. and Ph.D from Xi'an Jiaotong University and Institute of Plasma Physics, Chinese Academy of Sciences, respectively, majoring in nuclear reactor engineering and safety. She ever worked in the University of Tokyo as a guest professor and at Culham Science Center in England as a senior scientist. And she ever worked in the National Institute of Fusion Science (NIFS) and Hokkaido University in Japan as a visiting scholar. She was awarded the title of “Excellent Woman” by Anhui Province and “Excellent Researcher” by the Institute of Plasma Physics.She is one of the members for ITER Test Blanket Working Group, for the 13rd International Fusion Reactor Materials Program Committee, and for Monte Carlo Method Committee of China Calculation Physics Association. She is in experts list of “863” Hi-Tech Research and Development Program of China, one of the professors in the University of Science and Technology (USTC), and the special reviewer for Journals of Chinese Physics Letters and Computational Physics.Her main interests are in the fields of fusion reactor blanket design, optimization and related R&D, development and research on advanced calculation methods for reactor physics and shield etc..She won the 3rd Prize of Progress of Science and Technology awarded by the Nation, the 1st Prizes of Progress of Science and Technology awarded by the State Education Commission of China, the 1st Prizes of Progress of Natural Science awarded by the Science and Technology Department of Anhui Province etc.. She is the most important person who is responsible for the invention and R&D on China Low Activation Martensitic steel (CLAM). One software designed and developed by her is widely used in the physical design and analysis of LWRs such as used in the Daya Bay Power Station, the Qinshan Power Station and the 1st Nuclear Power Institute etc..She is responsible for some projects supported by National Natural Scientific Foundation and the Knowledge Innovation Program of Chinese Academy of Sciences etc..About 100 papers have been published, several patents have been submitted and approved.
 
     
Selected Publications
1) 中国低活化马氏体钢CLAM研究进展 , 核科学与工程 , 2007 , 第27卷第1期
2) 中国低活化马氏体钢CLAM在液态锂铅中腐蚀的初步实验研究 , 核科学与工程 , 2007 , 第27卷第1期
3) 中国低活化马氏体钢(CLAM)热等静压扩散焊接初步研究 , 核科学与工程 , 2007 , 第27卷第1期
4) Neutronics Analysis for A Compact Reversed Shear Tokamak CREST , Fusion Engineering and Design , 2006 , 81(2006)
5) Corrosion Experiment in the First Liquid Metal LiPb Loop of China , the 24th Symposium on Fusion Technology , 2006 , Sept.11-15
6) Preliminary Experimental study on Hot Isostatic Pressing Diffusion Bonding for CLAM-CLAM , the 24th Symposium on Fusion Technology , 2006 , sept.11-15
7) Effects of Addition of Yttrium on Properties and Microstructure for China Low Activation Martensitic Steel , the 24th Symposium on Fusion Technology , 2006 , Sept.11-15
8) CLAM钢冲击和拉伸性能测试与研究 , 原子核物理评论 , 2006 , 第23卷第2
9) Preliminary Tritium Analysis on China Liquid LiPb Test Blanket Module for ITER , the Mini-Workshop on ITER Related Tritium Technolo , 2006 , August 9-11
10) ITER中国液态锂铅实验包层模块氚渗透分析 , 核科学与工程 , 2006 , 第26卷第2期
11) ITER中国液态锂铅实验包层模块活化特性分析与废料处理 , 核科学与工程 , 2006 , 第26卷第2期
12) 蒙特卡罗方法在放疗计划中的应用 , 核技术 , 2006 , 第29卷第1期
13) ITER TBM 包层材料相关问题 , 聚变安全及包层材料研讨会,合肥 , 2006 , 2006.4
 
Recruitment information
Master Admissions 
a Nuclear Science and Engineering 
b Nuclear Fuel Cycle and Materials
Doctor Admissions
a Nuclear Science and Engineering 
b Nuclear Fuel Cycle and Materials
       
       
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TEL: +86-551-63600279, E-mail: tianlin@ustc.edu.cn