Current design and R&D progress of the Chinese helium cooled ceramic breeder test blanket system. (5th June 2019)

• Record Type: Journal Article
• Authors: Wang, X.Y.; Feng, K.M.; Chen, Y.J.; Zhang, L.; Feng, Y.J.; Wu, X.H.; Liao, H.B.; Ye, X.F.; Zhao, F.C.; Cao, Q.X.; Wang, F.; Gong, B.P.; Wang, Q.J.; Zhou, B.; Zhang, H.X.; Pan, C.H.; Xu, M.; Duan, X.R.; Wang, M.; Sheng, Q.; He, K.H.; Luo, D.L.; Yao, Y.
• Other Names: collab.
• Is Part Of: Nuclear fusion. Volume 59:Number 7(2019:Jul.)
• Publication Date: 2019-06-05
• Subjects: HCCB TBS -- design -- R&D -- ITER; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/ab0c32
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: As the testing mockup of tritium breeding blanket for DEMO, the Chinese helium cooled ceramic breeder test blanket system (HCCB TBS) is under development by China and will be tested in ITER to verify key tritium breeding blanket technologies. After the approval of the conceptual design of the HCCB TBS by the ITER Organization in 2015, the design optimization and more research and development activities for the HCCB TBS have begun for the preliminary design. This paper gives an overview of the recent progress of the HCCB TBS development in China, including the design optimizations, material development, mockup fabrication and test facility construction.