NDLI: Design and reconstruction of the nitrogen screen system for HT-7 superconducting tokamak

Content Provider	IEEE Xplore Digital Library
Author	Liao Ziying
Copyright Year	1998
Description	Author affiliation: Inst. of Plasma Phys., Acad. Sinica, Hefei, China (Liao Ziying)
Abstract	The HT-7 Tokamak that is built at the Institute of Plasma Physics (ASIPP) is the first superconducting tokamak in China. It is reconstructed from Russian Tokamak T-7. The device can be operated at toroidal field of 2 tesla steadily now. A plasma current of 220 kilo-ampere and a 2.97 seconds pulse was achieved in May 1997. The nitrogen screen of HT-7 tokamak consists of two toroidal shields that are located in the interspace between the internal and external vacuum chamber. They enclose the superconducting magnet system, providing both thermal radiation and electromagnetic shield. The experiment result shows that the heat load of the nitrogen screen is increased after the reconstruction. Using over cooled liquid nitrogen we got a good result.
Starting Page	653
Ending Page	656
File Size	400891
Page Count	4
File Format	PDF
ISBN	0780342267
DOI	10.1109/FUSION.1997.687711
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1997-10-06
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Nitrogen Tokamaks Coils Superconducting magnets Cooling Plasma devices Plasma displays Magnetic circuits Insulation Physics
Content Type	Text
Resource Type	Article

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Design and reconstruction of the nitrogen screen system for HT-7 superconducting tokamak