姓名
周启来
性别
男
民族
汉
出生年月
1984年11月

职称
副教授
职务
教师
联系电话
**

单位名称
材料科学与工程学院
Email
zhou.qilai@whut.edu.cn

实验室网址
https://www.researchgate.net/profile/Qilai_Zhou

研究方向
长期从事聚变堆材料相关研究，主持国家自然科学基金1项、日本科学技术振兴机构（JST）樱花科技计划1项，获得日本学术振兴机构（JSPS）若手科学研究费。主要研究方向：
1、聚变堆材料制备与部件成形
2、氢同位素行为

教育背景
2012- 2015,华中科技大学,材料加工工程,工学博士
2008- 2011,华中科技大学, 材料加工工程,工学硕士
2004- 2008,武汉理工大学,材料成型及控制工程,工学学士

工作经历
2019至今,武汉理工大学材料科学与工程学院,副教授
2018 - 2019,日本核聚变科学研究所（NIFS）,COE研究员
2016- 2018,日本静冈大学理学部放射科学研究中心,博士后
2011- 2012, 武昌船舶重工集团有限公司,助理工程师

项目情况
1. 国家自然科学基金，复合陶瓷氚增殖材料微结构对氢同位素释放过程的影响及机制，2020.1 – 2022.12，No. **，主持
2. 日本JST樱花科技计划，放射线测定技术及其在材料分析中的应用，2020.12 – 2020.12，No. S2019F**, 中方负责人

代表性学术
成果
代表性论文：
[1]. Q. Zhou, M. Yajima, M. Tokitani, Y. Hamaji, S. Masuzaki, Tritium removal from the LHD first-wall by the hydrogen plasma discharge, Fusion Engineering and Design, 2020, Accept.
[2]. Q. Zhou, A. Togari, M. Nakata, M. Zhao, F. Sun, M. Yajima, M. Tokitani, N. Yoshida, M. Hara, Y. Hatano, Y. Oya, Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature, International Journal of Hydrogen Energy 45(2020)9959-9968.
[3]. Q. Zhou, A. Togari, M. Nakata, M. Zhao, F. Sun, Q. Xu, Y. Oya, Release kinetics of tritium generation in neutron irradiated biphasic Li2TiO3–Li4SiO4 ceramic breeder, Journal of Nuclear Materials 522(2019)286-293.
[4].大矢恭久, 周啓来, 小林真, 連載講座「核融合トリチウム研究最前線」―-原型炉実現に向けて-第7回トリチウム蓄積, 日本原子力学会誌（Atomos）61(2019)64-69).
[5]. Q. Zhou, K. Azuma, A. Togari, M. Yajima, M. Tokitani, S. Masuzaki, N. Yoshida, M. Hara, Y. Hatano, Y. Oya, Helium retention behavior in simultaneously He+-H2+ implanted tungsten, Journal of Nuclear Materials 502(2018)289-294.
[6]. Q. Zhou, K. Azuma, A. Togari, M. Yajima, M. Tokitani, S. Masuzaki, N. Yoshida, M. Hara, Y. Hatano, Y. Oya,　Deuterium retention behavior in simultaneously He+-D2+ implanted tungsten, Nuclear Energy and Materials 16(2018)76-81.
[7]. Q. Zhou, Y. Oya, T. Chikada, W. Zhang, L. Xue, Y. Yan, Preparation of Li2TiO3 by hydrothermal synthesis and its structure evolution under high energy Ar+ irradiation, Journal of the European Ceramic Society 37(2017)4955-4961.
[8]. Q. Zhou, L. Xue, Y. Wang, H. Li, T. Chikada, Y. Oya, Y. Yan, Preparation of Li2TiO3 ceramic with nano-sized pores by ultrasonic-assisted solution combustion, Journal of the European Ceramic Society 11(2017)3595-3602.
[9]. Q. Zhou, Y. Gao, K. Liu, L. Xue, Y. Yan, Fabrication of Li2TiO3 pebbles by a selective laser sintering process, Fusion Engineering and Design 100(2015)166-170.
[10]. Q. Zhou, Y. Mou, X. Ma, L. Xue, Y. Yan, Effect of fuel-to-oxidizer ratios on combustion mode and microstructure of Li2TiO3 nano-scale powders, Journal of the European Ceramic Society 34(2014)801-807.
[11]. Q. Zhou, L. Tao, Y. Gao, L. Xue, Y. Yan, Flash synthesis of Li2TiO3 powder by microwave-induced solution combustion, Journal of Nuclear Materials 455(2014) 101.

奖励：
[1]. 第15回日本原子力学会核融合工学部奖励赏, 日本原子力学会，2018年9月


Associate Prof. QilaiZHOU
Address:Room 109, Materials processing department, Mafangshaneast campus, Wuhan University of Technology, Luoshi Road 122, Wuhan 430070, P.R. China
Email：zhou.qilai@whut.edu.cn Tel: +86 **

EDUCATION
2012- 2015
Doctor course
Huazhong University of Science and Technology,
Research theme: Preparation of solid tritium breeding materials

2008- 2011
Master course
Huazhong University of Science and Technology,
Research theme: Preparation of tritium permeation barriers

2004-2008
Bachelor
Wuhan University of Technology
Major: Materials Processing

WORK EXPERIENCE
2019-now
Associate Professor
School of Materials Science and Technology, Wuhan University of Technology, China
Education work: Materials processing, and practice.
Research work: Fusion reactor materials; Hydrogen isotope behavior.

2018-2019
COE Researcher
Fusion system research division, National Institute for Fusion Science, Japan
Research topic: Tritium measurement and removal techniques for the Large Helical Device first-wall.

2016-2018
Post doctor
Faculty of Science, Shizuoka University, Japan
Research topic:Hydrogen/Helium behavior in plasma facing materials and ceramic tritium breeding materials.

2011-2012
Assistant Engineer
Wuchang Shipbuilding Industry Group Co., LTD
Work field: Welding materials and methods.

RESEARCH PROJET
My research topics are fusion reactor materials and hydrogen isotope behavior.I focuses on the fundamentalresearch in this field,especially in the tritium breeder and plasma-wall interaction. The following is my research projects, which are from the National Natural Science Foundation of China, and Japan Science and Technology Agency.
2020.1 – 2022.12
Effect of microstructure of the composite ceramic tritium breeding materials on the hydrogen isotope release process and its mechanism, National Natural Science Foundation of China (NSFC), No. **,Project Leader.

2020.12 – 2020.12
Measurement technology for the radioactive rays and its application in the materials analysis, Sakura Science Plan, Japan Science and Technology Agency (JST), No. S2019F**,Project Leader in China side.

SELECTED PUBLICATION
[1]. Q. Zhou, M. Yajima, M. Tokitani, Y. Hamaji, S. Masuzaki, Tritium removal from the LHD first-wall by the hydrogen plasma discharge, Fusion Engineering and Design, 2020, Accept.
[2]. Q. Zhou, A. Togari, M. Nakata, M. Zhao, F. Sun, M. Yajima, M. Tokitani, N. Yoshida, M. Hara, Y. Hatano, Y. Oya, Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature, International Journal of Hydrogen Energy 45(2020)9959-9968.
[3]. Q. Zhou, A. Togari, M. Nakata, M. Zhao, F. Sun, Q. Xu, Y. Oya, Release kinetics of tritium generation in neutron irradiated biphasic Li2TiO3–Li4SiO4 ceramic breeder, Journal of Nuclear Materials 522(2019)286-293.
[4]. Y. Oya, Q. Zhou, M. Kobayashi, Research frontier of tritium for fusion reactor. Toward the DEMO reactor (7). Tritium retention, Nippon Genshiryoku Gakkai-Shi (Atomos), 2019, 61(1): 64-69.
[5]. Q. Zhou, K. Azuma, A. Togari, M. Yajima, M. Tokitani, S. Masuzaki, N. Yoshida, M. Hara, Y. Hatano, Y. Oya, Helium retention behavior in simultaneously He+-H2+ implanted tungsten, Journal of Nuclear Materials 502(2018)289-294.
[6]. Q. Zhou, K. Azuma, A. Togari, M. Yajima, M. Tokitani, S. Masuzaki, N. Yoshida, M. Hara, Y. Hatano, Y. Oya,　Deuterium retention behavior in simultaneously He+-D2+ implanted tungsten, Nuclear Energy and Materials 16(2018)76-81.
[7]. Q. Zhou, Y. Oya, T. Chikada, W. Zhang, L. Xue, Y. Yan, Preparation of Li2TiO3 by hydrothermal synthesis and its structure evolution under high energy Ar+ irradiation, Journal of the European Ceramic Society 37(2017)4955-4961.
[8]. Q. Zhou, L. Xue, Y. Wang, H. Li, T. Chikada, Y. Oya, Y. Yan, Preparation of Li2TiO3 ceramic with nano-sized pores by ultrasonic-assisted solution combustion, Journal of the European Ceramic Society 11(2017)3595-3602.
[9]. Q. Zhou, Y. Gao, K. Liu, L. Xue, Y. Yan, Fabrication of Li2TiO3 pebbles by a selective laser sintering process, Fusion Engineering and Design 100(2015)166-170.
[10]. Q. Zhou, Y. Mou, X. Ma, L. Xue, Y. Yan, Effect of fuel-to-oxidizer ratios on combustion mode and microstructure of Li2TiO3 nano-scale powders, Journal of the European Ceramic Society 34(2014)801-807.
[11]. Q. Zhou, L. Tao, Y. Gao, L. Xue, Y. Yan, Flash synthesis of Li2TiO3 powder by microwave-induced solution combustion, Journal of Nuclear Materials 455(2014) 101.
PATENT
[1]. Youwei Yan, Lihong Xue, Heping Li, Qilai Zhou, A rapid fabrication method for Li2TiO3 tritium breeding pebbles, Chinese Patent No. ZL2.5.
INTERNATIONAL CONFERENCE
Invited presentation:
[1]. Release kinetics of tritium generated in biphasic Li2TiO3-Li4SiO4 by thermal neutron irradiation　
Japan-Korea Workshop on Physics of fine plasma particles, July 2018, Kamakura, Japan
Qilai Zhou, Akihiro Togari, Moeko Nakata, Mingzhong Zhao, Qiu Xu, Masanori Hara, Yasuhisa Oya
Ordinary presentations:
[1]. Helium and deuterium retention behavior in simultaneous He-H implanted tungsten　
the 18th International Conference on Fusion Reactor Materials, November 2017, Aomori, Japan
Qilai Zhou, Keisuke Azuma, Akihiro Togari, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Masanori Hara, Yuji Hatano (Oral)
[2]. Helium retention behavior in simultaneous implanted tungsten
Japan-Korea Tritium Workshop, July 2017, Toyama, Japan
Qilai Zhou, Keisuke Azuma, Akihiro Togari, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Takumi Chikada, Yasuhisa Oya (Oral)
[3]. Helium retention behavior in simultaneous implanted tungsten　
International Symposium toward the Future of Advanced Researches,February 2017, Qilai Zhou, Keisuke Azuma, Yuki Uemara, Shodai Sakurada, Hiroe Fujita, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Takumi Chikada, Yasuhisa Oya (Poster)
[4]. Single step fabrication of nano-sized Li4SiO4 breeder by microwave-induced solution combustion synthesis
23rd International Conference on Nuclear Engineering, May 2015, Chiba, Japan
Qilai Zhou, Yue Gao, Lihong Xue, Heping Li, Youwei Yan(Oral)
[5]. Rapid fabrication of Li2TiO3 pebbles via microwave-induced combustion process and 3D printing
22nd International Conference on Nuclear Engineering, July 2014, Prague, Czech Republic
Qilai Zhou, Yue Gao, Yang Mou, Lihong Xue, Heping Li, Youwei Yan (Oral)　　
[6]. Preparation of Li2TiO3 ceramic powder by the microwave-assisted solution combustion synthesis
the 16th International Conference on Fusion Reactor Materials, October 2013, Beijing
Qilai Zhou, Liyao Tao, Lihong Xue, and Youwei Yan (Poster)　



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