Plasma heating and current drive systems for ITER and future fusion devices

Author

Jacquinot, J.

Author_Institution

JET Joint Undertaking, Abingdon, UK

Volume

1

fYear

1997

fDate

6-10 Oct 1997

Firstpage

399

Abstract

The design effort and technological development of four candidate additional heating and current drive systems for ITER are outlined. These are (i) electron cyclotron resonance heating (170 GHz), (ii) ion cyclotron resonance heating (40-70 MHz), (iii) lower hybrid current drive (5 GHz) and (iv) negative-ion neutral beam injection (1 MeV). The ITER requirement of ~100 MW will be provided by a combination of a minimum of two different systems. The ITER R&D programme is focused on key technology for each method which is progressing in parallel. It involves significant developments in a range of items such as power sources (high power steady-state gyrotrons, 1 MeV negative ion accelerators), transmission systems, windows and plasma facing RF couplers for the above systems

Keywords

fusion reactor design; fusion reactor ignition; plasma beam injection heating; plasma hybrid waves; plasma radiofrequency heating; plasma toroidal confinement; 1 MeV; 170 GHz; 40 to 70 MHz; 5 GHz; ECRH; ICRH; ITER; NBI heating; design effort; electron cyclotron resonance heating; fusion devices; ion cyclotron resonance heating; lower hybrid current drive; negative-ion neutral beam injection; plasma facing RF couplers; plasma heating; technological development; Cyclotrons; Electron beams; Gyrotrons; Heating; Ion accelerators; Plasma accelerators; Plasma sources; Radio frequency; Resonance; Steady-state;

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.1997.687064

Filename

687064