Design of Test Platform of High-Payload Transporter Joint for a Tokamak

doi:10.1109/TPS.2020.2982429

	Design of Test Platform of High-Payload Transporter Joint for a Tokamak
	Wang, Yan 2,3,4; Zhou, Zibo 4; Bai, Xiaowei 3,4; Yao, Damao 4; Choi, Chang-Hwan 1
刊名	IEEE TRANSACTIONS ON PLASMA SCIENCE
	2020-06-01
卷号	48
关键词	Hydraulic systems Loading Shafts Torque Force Couplings Servomotors China fusion engineering test reactor (CFETR) International Thermonuclear Experimental Reactor (ITER) remote handling (RH) test platform
ISSN号	0093-3813
DOI	10.1109/TPS.2020.2982429
通讯作者	Zhou, Zibo(zhouzb@ipp.ac.cn)
英文摘要	A general purpose remote-handling system with high-payload handing capability is necessary for Tokamak fusion reactors. Such a system helps maintain in-vessel components that could be damaged by high-temperature plasma. A high-payload transporter has been designed and a key rotary joint has been selected by the ITER Organization. To verify the feasibility of the high-payload transporter in engineering applications, its rotary joints that will be exposed to severe dynamic loads needs to be designed, manufactured, and tested. This system includes a test platform, a control system, and measuring instruments. This article discusses the design, analyses, and principle of the load simulation for the test platform. The mechanical jigs of the test platform are designed, and they consist of the bracket, Oldham coupling, and load shafts. The strength and deformation analyses of the loading shafts are conducted. The equivalent stress of the loading shafts is approximately 285.42 MPa, and the total deflection of joint & x0023;4 and the shafts is approximately 10.81 mm. The results show that the mechanical structure of the test platform conforms to the Chinese national standard. Hydraulic cylinders are used to generate the shear force, bending moment, and torque as well as to simulate the payload. The loading principle and method of the hydraulic system are introduced to illustrate that the hydraulic loading scheme can meet the loading requirements. The design scheme satisfies the test requirements, and is confirmed and accepted by the ITER Organization.
资助项目	Ministry of Science and Technology, China[2017YFA0402500] ; Department of Education Anhui Province[KJ2018A0079]
WOS研究方向	Physics
语种	英语
出版者	IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC
WOS记录号	WOS:000542945800067
资助机构	Ministry of Science and Technology, China ; Department of Education Anhui Province
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/71471]
专题	中国科学院合肥物质科学研究院
通讯作者	Zhou, Zibo
作者单位	1.ITER Org, F-13067 St Paul Les Durance, France 2.Anhui Univ Sci & Technol, Huainan 232001, Peoples R China 3.Univ Sci & Technol China, Hefei 230026, Peoples R China 4.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
推荐引用方式 GB/T 7714	Wang, Yan,Zhou, Zibo,Bai, Xiaowei,et al. Design of Test Platform of High-Payload Transporter Joint for a Tokamak[J]. IEEE TRANSACTIONS ON PLASMA SCIENCE,2020,48.
APA	Wang, Yan,Zhou, Zibo,Bai, Xiaowei,Yao, Damao,&Choi, Chang-Hwan.(2020).Design of Test Platform of High-Payload Transporter Joint for a Tokamak.IEEE TRANSACTIONS ON PLASMA SCIENCE,48.
MLA	Wang, Yan,et al."Design of Test Platform of High-Payload Transporter Joint for a Tokamak".IEEE TRANSACTIONS ON PLASMA SCIENCE 48(2020).