Title :
Plasma heating and current drive systems for ITER and future fusion devices
Author_Institution :
JET Joint Undertaking, Abingdon, UK
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;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687064
