Published June 2009 | Version v1
Journal article

Progress on the heating and current drive systems for ITER

  • 1. Cabinet of High Commissioner for Atomic Energy, CEA Gif-sur-Yvette, St Paul-lez-Durance (France)
  • 2. Fusion for Energy, c/Josep Pla, No. 2, Torres Diagonal Litoral, Edificio B3, 08019 Barcelona (Spain)
  • 3. ITER Cadarache JWS, F-13108 St Paul-lez-Durance (France)
  • 4. CEA, IRFM, F-13108 St Paul-lez-Durance (France)
  • 5. ITER India, A29, Sector 25, GIDC, Gandhinagar, Gujarat (India)
  • 6. Institute of Applied Physics, 60360 Nizhny Novgorod (Russian Federation)
  • 7. US ITER Project Office, Oak Ridge National Laboratory, P.O. Box 2008, 1055 CM, MS 6483, Oak Ridge, TN 37831-6483 (United States)
  • 8. JAEA, 801-1 Mukouyama, Naka-shi, Ibaraki-ken 311-0193 (Japan)

Description

The electron cyclotron (EC), ion cyclotron (IC), heating-neutral beam (H-NB) and, although not in the day 1 baseline, lower hybrid (LH) systems intended for ITER have been reviewed in 2007/2008 in light of progress of physics and technology in the field. Although the overall specifications are unchanged, notable changes have been approved. Firstly, it has been emphasized that the H and CD systems are vital for the ITER programme. Consequently, the full 73 MW should be commissioned and available on a routine basis before the D/T phase. Secondly, significant changes have been approved at system level, most notably: the possibility to operate the heating beams at full power during the hydrogen phase requiring new shine through protection; the possibility to operate IC with 2 antennas with increased robustness (no moving parts); the possible increase to 2 MW of key components of the EC transmission systems in order to provide an easier upgrading of the EC power as may be required by the project; the addition of a building dedicated to the RF power sources and to a testing facility for acceptance of diagnostics and heating port plugs. Thirdly, the need of a plan for developing, in time for the active phase, a CD system such as LH suitable for very long pulse operation of ITER was recognised. The review describes these changes and their rationale.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2009.01.100

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2009.01.100;
PII
S0920-3796(09)00033-7;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
84
Journal Issue
2-6
Journal Page Range
p. 125-130
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
25. symposium on fusion technology
Acronym
SOFT-25
Dates
15-19 Sep 2008
Place
Rostock (Germany)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41031098
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BEAM INJECTION HEATING; ECR HEATING; ICR HEATING; ITER TOKAMAK; LOWER HYBRID CURRENT DRIVE; LOWER HYBRID HEATING
Descriptors DEC
CLOSED PLASMA DEVICES; HEATING; HIGH-FREQUENCY HEATING; NON-INDUCTIVE CURRENT DRIVE; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.