DocumentCode :
1599740
Title :
Status of the ITER EC system
Author :
Darbos, C.
Author_Institution :
ITER EC Int. Design Team ITER Organ., St. Paul-lez-Durance, France
fYear :
2013
Firstpage :
1
Lastpage :
1
Abstract :
Summary form only given. A 24 MW Electron Cyclotron Heating and Current Drive (EC H&CD) system is under development for plasma startup, central H&CD and control of MHD activity on the ITER Tokamak. Physics applications will be achieved by a combination of two types of launchers, one located in the equatorial port and four in the upper. For the first plasma on ITER, one third of the EC power is required and whole EC system will be available for the second phase. The EC system design is progressing towards the final stage according to the 2020 first plasma date, as nearly all subsystems have completed their preliminary designs. R&D is going on to confirm good performances already demonstrated on gyrotron prototypes by both Japanese and Russian Domestics Agencies (DA). European DA is focusing on achieving a more conventional 1MW prototype, despite good results obtained on the 2MW tube, but limited to short pulses. All DAs involved in gyrotrons procurement already installed (Japan, Europe) or will soon build a dedicated test facility (India, Russia) mimicking ITER environment including control system aspects. Half of EC procurement arrangements (PA) has been signed in 2012 and a large effort has been put on achieving a reasonably good preliminary design of the EC system. The remaining PAs for gyrotrons are planned to be signed this year along with the construction design of the RF building housing both IC and EC systems, including services. A review of the present design and integration status of the EC system will be presented, as well as possible future modifications which include: increase High Voltage Power Supplies specifications to accommodate possible future EC power upgrade up to 1.2 MW per gyrotron, removal of Be from the first wall for Equatorial and Upper Launchers and introduce a 10 cm recession from the neighbouring wall mounted blankets, modification in the Equatorial Launcher beam scan direction from toroidal to poloidal plane in order to - ouble the driven current capability especially at mid radius.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; gyrotrons; plasma magnetohydrodynamics; plasma radiofrequency heating; plasma toroidal confinement; EC power; EC system design; European DA; ITER EC system; ITER tokamak; Japanese domestics agencies; MHD activity; Russian domestics agencies; electron cyclotron heating; equatorial launcher beam scan; gyrotron prototypes; high voltage power supplies; power 1 MW; power 24 MW; wall mounted blankets; Cyclotrons; Europe; Gyrotrons; Organizations; Plasmas; Procurement; Prototypes;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Plasma Science (ICOPS), 2013 Abstracts IEEE International Conference on
Conference_Location :
San Francisco, CA
ISSN :
0730-9244
Type :
conf
DOI :
10.1109/PLASMA.2013.6635124
Filename :
6635124
Link To Document :
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