Published September 2006 | Version v1
Journal article

Status and prospects for mm-wave reflectometry in ITER

  • 1. ITER International Team, Naka Joint Work Site, 801-1 Mukouyama, Naka, Ibaraki 311-0193 (Japan)
  • 2. ITER IT, Garching JWS, c/o Max-Planck-Institut f. Plasmaphysik, Boltzmannstr. 2, D 85748 Garching bei Muenchen (Germany)
  • 3. Association EURATOM/CEA sur la fusion, CEA Cadarache, 13108 St Paul Lez Durance (France)
  • 4. Association EURATOM/CIEMAT, 28040 Madrid (Spain)
  • 5. Institute of Applied Physics of Russian Academy of Science, Nijnii Novgorod (Russian Federation)
  • 6. Associacao EURATOM/IST, Centro de Fusao Nuclear/Instituto Superior Tecnico, 1096 Lisboa Codex (Portugal)
  • 7. KIAE, Ploshchad'Akademika Kurchatova 1, Moscow 123182 (Russian Federation)
  • 8. LPMIA, Universite Henri Poincare Nancy I, Vandoeuvre (France)

Description

Reflectometry with wavelengths in the centimetre to millimetre-wave range will be used in ITER to measure the density profile in the main plasma and divertor regions and to measure the plasma position and shape in order to provide a reference for the magnetic diagnostics in long pulses. In addition, it is expected to provide key information for the measurement of density fluctuations. A set of reflectometers to meet the relevant ITER measurement requirements has been included in its present outline as part of the ITER design since 2001 and is being adapted to the present ITER baseline and to accommodate progress with reflectometry techniques and measurement capabilities. It comprises low and high field side (HFS and LFS, respectively) ordinary (O-) mode systems for the measurement of the density profile in the gradient regions, a LFS extraordinary (X-) mode system for the detailed study of the edge profile, an HFS X-mode system operating in the left hand cutoff to measure the core profile, a dedicated O-mode system for plasma-wall gap measurement and a multi-band, multiple line of sight O-mode system to measure divertor density profiles. This paper describes the evolution of the design, in particular some recent improvements in the engineering implementation and improvements aimed at enhancing the measurement capability. It concludes with a brief assessment of the likely measurement performance against the ITER measurement requirements for the parameters of interest and the overall confidence that the technique will be implanted on ITER

Availability note (English)

Available online at http://stacks.iop.org/0029-5515/46/S836/nf6_9_S20.pdf or at the Web site for the journal Nuclear Fusion (ISSN 1741-4326 ) http://www.iop.org/

Additional details

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
46
Journal Issue
9
Journal Page Range
p. S836-S845
ISSN
0029-5515
CODEN
NUFUAU

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37121343
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
DESIGN; DIVERTORS; FLUCTUATIONS; HYPERFINE STRUCTURE; ITER TOKAMAK; PERFORMANCE; PLASMA; PLASMA DENSITY; PLASMA DIAGNOSTICS; PULSES; WAVELENGTHS
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; VARIATIONS