基本情况

出生年月：1984.11

职称：副教授

最高学位：博士

主要研究方向：核材料、氢同位素、材料腐蚀

导师类别：学术型硕导

工作单位：tyc1286太阳成集团

Email: zhou.qilai@whut.edu.cn

网站：https://www.researchgate.net/profile/Qilai-Zhou

教育及工作经历

2019至今   tyc1286太阳成集团, 副教授

2022-2023  日本静冈大学理学部放射科学教育研究推进中心, 外国人研究员（CSC访问学者）

2018-2019  日本国立核聚变科学研究所（NIFS）, COE研究员

2016-2018  日本静冈大学理学部放射科学教育研究推进中心, 博士后

2011-2012  武昌船舶重工集团有限公司, 助理工程师

2012-2015  华中科技大学tyc1286太阳成集团, 材料加工工程, 博士

2008-2011  华中科技大学tyc1286太阳成集团, 材料加工工程, 硕士

2004-2008  tyc1286太阳成集团, 材料成型及控制工程, 学士

奖励情况

教学奖励

2022.06, 太阳成集团的官方网站第十一届青年教师教学竞赛二等奖

学术奖励

2019.10，日本原子力学会会赏

近期主持科研项目

1.2020-2022, 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, 国家自然科学基金

2.2023, 聚变堆研发中的氚科学与工程, 日本科学技术振兴会樱花科技计划

近期代表性学术成果

学术论文： 

1. Q. Zhou*, S. Li, S. Hirata, A. Sanfukuji, G. Tan, Akira Taguchi, Yasuhisa Oya*, Tritium and deuterium release behavior of Li₂TiO₃-0.5Li₄SiO₄–Pb ceramic. Ceramics International, 2023, 49(16): 26778-26785.

2. Y. Oya*, N. Inozume, Y. Hoshino, N. Yoshida, T. Hinoki, K. Yabuuchi, Y. Hatano, Q. Zhou, F. Sun, R. Kolasinski, C.N. Taylor, M. Shimada, Thermal annealing effect on D retention for damaged W-10% Re alloy, Fusion Engineering and Design, 2023, 196: 113981.

3. Q. Zhou*, F. Sun, S. Hirata, S. Li, Y. Li, Y. Oya*, Effect of neutron dose on the tritium release behavior of Li₂TiO₃-0.5Li₄SiO₄ biphasic ceramic. International Journal of Hydrogen Energy, 2023, 48(11): 4363-4370.

4. Q. Wang, Q. Zhou*, Q. Xiong, J. Zhou, S. Li, S. Hirata, Y. Oya*, Preparation of Li₂TiO₃-Li₄SiO₄-Pb tritium breeding ceramic and its mechanical properties. Ceramics International, 2022, 48(18): 26742-26749.

5. J. Zhou, Q. Wang, S. Li, H. Li, Q. Zhou*, Phase composition control of biphasic tritium breeding ceramics and correlation behavior of lithium and tritium. Journal of Nuclear Materials, 2021, 557: 153294.

6. Q. Zhou, J. Zhou, W. Feng*, L. Xue*, H. Li, L. Guo, Y. Yan, Solution combustion synthesis of lithium orthosilicate as the tritium breeder: effects of microwave power and fuel-to-oxidizer ratio on phase, microstructure and sintering. Ceramics International, 2021, 47(15): 22006-22015.

7. 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, 159: 111879.

8. 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 2020, 45: 9959-9968.

9. 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).

10. 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, 2018, 502: 289-294.

11. 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, 2018, 16: 76-81.

12. 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, 2017, 37: 4955-4961.

13. 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, 2017, 11: 3595-3602.

14. Q. Zhou, Y. Gao, K. Liu, L. Xue*, Y. Yan, Fabrication of Li₂TiO₃ pebbles by a selective laser sintering process, Fusion Engineering and Design, 2015, 100: 166-170.

发明专利：

一种快速制备Li₂TiO₃氚增殖小球的方法, ZL 2014 1 0369142.5