ZHOU Xiangwen
Senior Research Scientist of Nuclear Science and Engineering
Division of New Materials
xiangwen@tsinghua.edu.cn
(+86 10) 8979-6607
Education background
PhD, Tsinghua University, Material Science and Engineering, 2007
B.S., Tsinghua University, Mechanical Engineering and Automation, 2001
Experience
12/2010-present, Associate Professor, Division of New Materials, INET
03/2015-03/2016, Visiting Scholar, Oak Ridge National Laboratory, TN, USA
12/2008-12/2010, Assistant Professor, Division of New Materials, INET
01/2007-12/2008, Post-Doctor, Division of Reactor Structure, INET
Social service
Teaching
Nuclear Reactor Materials
Journal Reviewer
New Carbon Materials
Nuclear Engineering and Design
Journal of Nuclear Materials
Service to Professional Associations
Member of Carbon Materials Branch of Chinese Society of Metals;
Member of the First Artificial Graphite Sub-Technical Committee of the National Non-metallic Mineral Products and Products Standardization Technical Committee;
Member of the First Natural Flake Graphite Sub-Technical Committee of the National Non-metallic Mineral Products and Products Standardization Technical Committee
Areas of Research Interests/ Research Projects
Dr. Zhou’s research interests are in the areas of mass production of pebble fuel elements for HTR, property evaluation and microstructure characterization of nuclear graphite materials, and novel matrix materials for advanced nuclear fuel.
Research Status
Research on Key Process and Technology Optimization of Fuel Element Production for HTGR
As the group leader for the research team of fuel elements, Dr. Zhou is in charge of the process optimization for the mass production of spherical fuel elements for future commercial HTR, including the preparation stability improvement of nuclear graphite powders and matrix graphite powder, production capacity increment of overcoated fuel particles, isostatic molding of pebble fuel elements, and corresponding consecutive heat treatment of carbonization and high-temperature purification. Relevant raw materials’ performance measurement and evaluation and microstructure characterization and analysis are in progress as well. The technologies and equipment obtained from this project will be transferred to the design and construction of future commercial fuel elements production lines, whose production capacity is approximately 3,000,000 fuel elements per year.
Research on Key Equipment and Process of Spherical Fuel Element Production
As the main technical staff of the project, Dr. Zhou have made important breakthroughs in the equipment and technology of large-scale manufacturing of spherical fuel elements for HTR-PM. Dr. Zhou presided over the formulation and revision of a large number of process specifications and quality assurance documents, formed an optimized equipment process system and a complete quality assurance system, which guaranteed the successful development of spherical fuel elements that met the technical requirements of HTR-PM. The sample of spherical fuel elements performed well in the radiation test conducted by the European Union, laying a solid foundation for the fuel charging and obtaining the operation permit of HTR-PM.
Honors And Awards
First Prize of Science and Technology Award, China Nuclear Energy Association
Academic Achievement
Publications
Xiangwen Zhou, Yang Yang, Jingtao Ma, et al. Effects of purification on the properties and microstructures of natural flake and artificial graphite powders. Nuclear Engineering and Design, 2020, 360: article 110527.
Zhou Xiang-wen, Yang Yang, Song Jing, et al. Carbon materials in a high temperature gas-cooled reactor pebble-bed module. New Carbon Materials, 2018, 33(2): 97-108.
Xiangwen Zhou, Zhenming Lu, Jie Zhang, et al., “Study on the Comprehensive Properties and Microstructures of A3-3 Matrix Graphite Related to the High Temperature Purification Treatment,” Science and Technology of Nuclear Installations, vol. 2018, Article ID 6084747, 10 pages, 2018.
Xiangwen Zhou, Cristian I. Contescu, Xi Zhao, et al., “Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength,” Science and Technology of Nuclear Installations, vol. 2017, Article ID 4275375.
ZHOU Xiang-wen, TANG Ya-ping, Lu Zhen-ming, Zhang Jie, Liu Bing. Nuclear graphite for high temperature gas-cooled reactors. New Carbon Materials, 2017, 32(3): 193-204.
Zhou Xiang-wen, Lu Zhen-ming, Li Xin-nan, Zhang Jie, Liu Bing, Tang Ya-ping. The oxidation behavior of A3-3 matrix graphite. New Carbon Materials, 2016, 31(2): 182-187.
Patents
Lu Zhenming, Zhang Jie, Liu Bing, Wang Lei, Zhou Xiangwen, et al. Device and method for pressing green spherical fuel element. CN108638564B, 2019.
Lu Zhenming, Zhang Jie, Zhou Xiangwen, et al. Soft molding die for powder spherical molding. CN206509514U, 2017.
Liu Bing, Zhang Jie, Lu Zhenming, Zhou Xiangwen, et al. Equipment for forming spherical fuel element. CN105679387A, 2016.
Zhao Xingyu, Zhou Xiangwen, Liu Malin, et al. A particle vibration optimization device. CN203737601U, 2014.
Zhou Xiangwen, Zhao Xingyu, Ma Jingtao, et al. Method for preparing quasi-uranium dioxide ceramic fuel microspheres. CN102229441A, 2013.
Last Updated：2020-10-06
