Preliminary engineering design of toroidal field magnet system for superconducting tokamak HT-7U

Author

Pan, Y.N. ; Weng, P.D. ; Chen, Z.M. ; Li, B.Z. ; Wu, S.T. ; Wu, W.Y. ; Gao, B.J. ; Yu, J. ; Wu, D. ; Wu, X.B. ; Chen, Q. ; Chen, W.G.

Author_Institution

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

Volume

10

Issue

1

fYear

2000

fDate

3/1/2000 12:00:00 AM

Firstpage

628

Lastpage

631

Abstract

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.

Keywords

Tokamak devices; finite element analysis; fusion reactor design; superconducting magnets; HT-7U; coil winding; continuously operating tokamak fusion reactor; heat load evaluation; mechanical calculation; preliminary engineering design; stability analysis; stress analysis; superconducting tokamak; support structure design; toroidal field magnet system; toroidal field superconducting magnet system; Design engineering; Fusion reactor design; Fusion reactors; Nuclear and plasma sciences; Physics; Plasma devices; Plasma stability; Superconducting magnets; Tokamaks; Toroidal magnetic fields;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/77.828312

Filename

828312