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

Author

Ziying, Liao

Author_Institution

Inst. of Plasma Phys., Acad. Sinica, Hefei, China

Volume

2

fYear

1997

fDate

6-10 Oct 1997

Firstpage

653

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

Keywords

Tokamak devices; electromagnetic shielding; fusion reactor design; nitrogen; superconducting magnets; 2 tesla; 220 kA; HT-7 superconducting tokamak; N₂; electromagnetic shield; external vacuum chamber; heat load; internal vacuum chamber; nitrogen screen system; over cooled liquid nitrogen; thermal radiation; toroidal field; toroidal shields; Coils; Cooling; Insulation; Magnetic circuits; Nitrogen; Physics; Plasma devices; Plasma displays; Superconducting magnets; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1997. 17th IEEE/NPSS Symposium

Conference_Location

San Diego, CA

Print_ISBN

0-7803-4226-7

Type

conf

DOI

10.1109/FUSION.1997.687711

Filename

687711