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The development of new high magnetic field facilities in the Chinese High Magnet Field Laboratory (CHMFL) will soon be completed according to the present situation. For the construction of the 40 T hybrid magnet, which will be the highest magnetic field facility in China, great progress has been achieved so far, for example, the engineering design of the resistive insert composed of six Florida-Bitter-type coils has been completed and part of the Bitter disks has been punched in Shanghai, and significant R & D progress on the design and manufacture of the superconducting outsert has been made, and the other main components of the superconducting outsert, such as?cryostat, 80 K thermal shield, vacuum pumping units, busbars, a pair of 16 kA HTS leads, overpressure protection device and so on, have been manufactured. The recent development of the CHMFL 40 T hybrid magnet is introduced in detail.

The EAST is an Experimental Advanced Superconducting Tokamak. The mission of the EAST Project is to bring out scientific issues on the continuous nonburning plasma scenario of steady-state operation and engineering issues on establishing the basis of technology for superconducting tokamak. Superconducting magnets were chosen for all poloidal field (PF) and toroidal field (TF) systems since the engineering mission is to establish the technology basis of full superconducting Tokamak for future fusion reactors. The superconducting magnets of EAST consist of sixteen TF coils and fourteen PF coils (seven coil-pairs). To obtain the good performance of the superconducting magnets, all TF magnets and most PF magnets have been tested before assembly. The assembly of the main device was completed in the end of 2005 and at the beginning of 2006, we made successfully the first engineering commissioning of the EAST system. Up to now the EAST device has been used in 4 operation campaigns and has achieved good experimental results.

EAST (HT-7U) is a large fusion experimental device being built at IPP, Hefei, China. Its superconducting magnet system consists of sixteen Toroidal Field (TF) coils and fourteen Poloidal Field (PF) coils. The TF coil includes the winding pack with a square cable-in-conduit (CIC) type superconductor in NbTi cooled by a force flow of supercritical helium, the welded case structure, the gravity support which is composed of pedestals with flexible plates, the coil joint with low resistance at high current and other components. At present, the production of all TF coils has been finished and all of the TF coils have been installed in the machine. This paper describes mainly the special fabrication processes of the TF coil

HT-7U is a large fusion experimental device. It will be built at the Institute of Plasma Physics of Chinese Academy of Sciences. The mission of HT-7U is to develop the scientific basis for a continuously operating tokamak fusion reactor. This paper describes only the toroidal field (TF) superconducting magnet system of HT-7U. In this paper, design criteria of conductor and stability analysis, coil winding and support structure design of magnet system, mechanical calculation, stress analysis and heat load evaluation are given.

On-site winding of magnet coils of HT-7U started in September 1998, using a numerically controlled winding machine. Magnet coils are all forced-flow superconducting coils, consisting of superconducting Toroidal Field (TF) coils and superconducting Poloidal Field (PF) coils. All of TF and PF coils will use NbTi Cable-in-Conduit Conductor (CICC) cooled with supercritical helium. This paper reports on the set up of a new winding facility with unique capabilities for continuous winding of long length CICC. An analytical method used to predict conduit springback before winding is presented and the results are compared to the ones obtained during winding. Research and development of winding of the TF Dummy Coil (TFDC) has been carried out and a winding method has been developed by winding trials. Windings of the TFDC and CS Model Coil (CSMC) have been successfully completed by using the developed technique. In R&D, long dummy conductor and short sample jackets have been used to demonstrate a plastic deformation characteristic of CICC during the winding process. The developed winding method can be applied to fabricate all TF and PF coils.