曾於2008-2011年任日本原子力研究機構(JAEA)ResearchFellow 。在那珂核融合研究所從事聚變堆設計工作,主要從事產氚包層中子學、熱流體分析研究,在包層產氚、流體傳熱及數值仿真技術領域發現一系列有重要參考價值的理論與工程結果;於2012、2015年在美國麻省理工學院(MIT)等離子科學與聚變中心(PSFC)VisitingScientist,從事聚變工程研究;曾多次參加國際學術會議。 2012年3月被聘為中國科學院合肥研究院副研究員,2013年12月被聘為碩士生導師。已在工程力學、流體力學、核技術領域取得一定的研究成果。在NuclearFusion, IEEETransactionson PlasmaScience,Fusion Engineering and Design,Science in China等相關期刊發表研究論文30餘篇。Nuclear Science and Engineering,Fusion Engineering and Design 等雜誌審稿人。
[1]Changle Liu, Damao Yao, Xiang Gao, Zhaoliang Wang, Chao Liang, Zibo Zhou, Lei Cao, Tiejun Xu. Investigation on the possibility of tritium self-sufficiency for CFETR using a PWR water-cooled blanket. IEEE Transactions on Plasma Science, 2014, 42(6): 1759-1763
[2] Liu ChangLe,Yao DaMao, Doody, Jeffrey, Lipschultz, Bruce, Zhou LiHua, Liang Chao, Zhou ZiBo, Cao Lei, Xu TieJun. An approach to explore the eddy currents of the new type divertor for EAST device using ANSYS code.Science in China - Series E: Technological Sciences, 2014, 57(1): 9-13
[3] Liu change, Yao Damao, Fan Xinjiang, Li Lei, Wang Zhaoliang, Zhou Zibo, Cao Lei, Gao Xiang. The Design and Analysis of the Cooling System of NBI Thermal Shielding for EAST A# Equatorial Port. Journal of Fusion Energy. 2014, 33(4):422–427
[4] Changle Liu, Jie Zhang, Hao Yang, Lei Li, Zhaoliang Wang, Chao Liang, Zibo Zhou, Lei Cao, Damao Yao, Xiang Gao. The Temperature Control Mechanism of a Breeding Blanket Module for Fusion Reactor. Journal of Fusion Energy (2014) 33(4):382–385
[5] Changle. Liu, Damao. Yao , Xiang. Gao , Zhaoliang. Wang, Songlin. Liu. A multi-layer breeding blanket concept for CFETR based on PWR condition. 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), San Francisco, CA, USA, 2013
[6]Changle Liu, Jianzhong Zhang, Yinfeng Zhu, Songlin Liu, Xuebin Ma, Peiming Chen. Numerical simulation of a blanket cooling system for fusion reactor based on PWR conditions. Fusion Engineering and Design. 2013, 88 (3): 156-159.
[7] C. Liu, K. Tobita, Y. Someya, et al. TBR comparison of water-cooled blanket
based on PWR and SCWR conditions. Fusion Engineering and Design. 2012, 87
(9): 1667-1669.
[8] C. Liu, K. Tobita, H. Utoh, Y. Someya, H. Takase, N. Asakura. Nuclear analysis of DEMO water-cooled blanket based on sub-critical water condition. Fusion Engineering and Design. 2011,86(12):2839-2842.
[9] C. Liu, K. Tobita. Numerical Simulation Analysis for the Divertor Plate of DEMO Reactor.Journal of Plasma Fusion Research. SERIES, 2010,9:197-201.
[10 ] C. Liu, K. Tobita.Hydraulic analysis of the water-cooled blanket based on the sub-critical water condition. Fusion Engineering and Design. 2009,85 (7-9) :979-982.
[11] K. Tobita, H. Utoh, C. Liu, H. Tanigawa, D. Tsuru, M. Enoeda, T. Yoshida, N. Asakura. Search for reality of solid breeder blanket for DEMO, Fusion Engineering and Design. 2010,85(7-9)1342-1347
[12] K. Tobita, S. Nishio, M. Enoeda, ……, C. Liu, ……T. Yamanishi and T. Yoshida.Compact DEMO, SlimCS: design progress and issues.Nuclear. Fusion, 49(7), 2009/7