首页 | 本学科首页   官方微博 | 高级检索  
     


Bridge joint fabrication and validation for SST-1 PF coil winding pack
Affiliation:1. Nuclear Engineering and Technology Programme, Indian Institute of Technology, Kanpur 208016, India;2. Institute for Plasma Research, Gandhinagar 382428, India;3. Innovative Systems Software, Idaho Falls, ID 83406, USA;1. Center for Plasma Material Interactions, University of Illinois, Urbana, Champaign, IL 61801, USA;2. Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA;1. Department of Mechanical Engineering, University of Thessaly, Volos 38334, Greece;2. Associação EURATOM/IST, Centro de Fusão Nuclear, Av. Rovisco Pais, 1049-001 Lisboa, Portugal;1. Metallurgy and Materials Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102, Tamil Nadu, India;2. Institute for Plasma Research, Bhat, Gandhinagar, Gujarat, India;1. SSC RF TRINITI Troitsk, Moscow 142 190, Russia;2. JSC “Red Star”, Elektrolitnyj pr. 1A, Moscow 113 230, Russia;3. NRNU MEPhI, Kashirskoye sh. 31, Moscow 115409, Russia
Abstract:A novel concept of bridge joint for Poloidal field (PF) magnet of SST-1 with damaged winding pack has been realized. This joint has been fabricated on 5th and 6th layers of PF#3T coil winding pack (WP) after validation at 10 kA at liquid helium temperature of 4.2 K in current lead test chamber. The joint resistance of bridge joint was measured ∼1.6 nΩ at flat top DC current of 10 kA. This type of joint could be economically useful for revival of a shorted and damaged WP superconducting PF magnets of Tokamaks. In this paper, details of bridge joint design, fabrication and validations are discussed.
Keywords:SST-1  Superconducting magnets  CICC  Terminations  Bridge type joint  Nano voltmeter
本文献已被 ScienceDirect 等数据库收录!
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号