Conceptual design of ECH system for JT-60SU

Author

Ikeda, Y. ; Tsuneoka, M. ; Takahashi, K. ; Kasugai, A. ; Terakado, M. ; Haga, K. ; Ushigusa, K. ; Sakamoto, K. ; Imai, T. ; Yamamoto, T.

Author_Institution

Naka Fusion Res. Establ., JAERI, Ibaraki, Japan

Volume

1

fYear

1997

fDate

6-10 Oct 1997

Firstpage

437

Abstract

The ECH system is under consideration to heat plasma and drive plasma current locally for JT-60SU. On the first stage, the frequency of 110 GHz is proposed to inject the fundamental O-mode wave at the toroidal field of 4T. The system design is intended to operate at a pulse length of 10 second with output power of 4 MW, because the design priority is to use the existing RF facility of JT-60 such as the DC power supply within 10 second operation. On the second stage, the steady state operation will be done incorporating 170 GHz and 1 MW gyrotron at the full toroidal magnetic field of 6T by employing a steady state DC power supply. A high power up to 50 MW is generated by fifty gyrotrons. A large antenna which is composed of an array of fifty corrugated waveguides is designed to operate with a good radiation shield against the neutrons from plasmas

Keywords

Tokamak devices; antennas in plasma; fusion reactor design; gyrotrons; plasma radiofrequency heating; power supplies to apparatus; 1 MW; 110 GHz; 50 MW; 6 T; DC power supply; ECH system; JT-60SU; RF facility; corrugated waveguides; design priority; fundamental O-mode wave; gyrotrons; plasma current; radiation shield; steady state operation; toroidal field; Antenna arrays; Gyrotrons; Neutrons; Plasma waves; Power generation; Power supplies; Pulsed power supplies; Radio frequency; Steady-state; Toroidal magnetic fields;

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.1997.687073

Filename

687073