Design of the magnetic diagnostic for ITER

Journal Article · Fri Jan 01 00:00:00 EST 1999 · Review of Scientific Instruments

DOI:https://doi.org/10.1063/1.1149390· OSTI ID:342704

de Kock, L; Walker, C ^[1]; Coccorese, E ^[2]; Costley, A E ^[3]; Dremin, M ^[4]; Gernhardt, J ^[5]; Kasai, S; Senda, I; Shoji, T ^[6]; Leuer, J; Snider, R ^[7]; McCarthy, P ^[8]; Portone, A ^[9]; Stott, P ^[10]; Young, K ^[11]

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1. ITER Joint Work Site, JW, Garching (Germany)
2. CREATE, Naples (Italy)
3. ITER JWS, San Diego, California (United States)
4. Kurchatov Institute, Moscow (Russia)
5. Institut fuer Plasmaphysik (IPP), Garching (Germany)
6. Japan Atomic Energy Research Institute, Naka, Ibaraki (Japan)
7. General Atomics, San Diego, California (United States)
8. University of Cork, Cork (Ireland)
9. ITER JWS, Naka, Ibaraki (Japan)
10. Joint European Torus (JET), Abingdon (United Kingdom)
11. Princeton Plasma Physics Laboratory, Princeton, New Jersey (United States)

The detailed design of the magnetic diagnostic for ITER is presented. The system consists of groups of pickup coils and flux loops on the vessel wall, the back plate, and the divertor. These sensors provide the measurements for the equilibrium reconstruction and the fluctuation analysis. The system is supplemented by Rogowski coils for halo current measurements and by a diamagnetic loop. The complete system meets the measurement requirements, matching those of contemporary large divertor tokamaks. The maximum radiation exposure is such that the sensors will survive for the lifetime of the ITER. {copyright} {ital 1999 American Institute of Physics.}

• OSTI ID: 342704
• Report Number(s): CONF-980605-; ISSN 0034-6748; TRN: 99:004956
• Journal Information: Review of Scientific Instruments, Vol. 70, Issue 1; Conference: 12. topical conference on high-temperature plasma diagnostics, Princeton, NJ (United States), 7-11 Jun 1998; Other Information: PBD: Jan 1999
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION
TOKAMAK DEVICES
ITER TOKAMAK
DESIGN
PLASMA DIAGNOSTICS
DIVERTORS
MAGNETIC FIELDS
MAGNETIC FLUX
LIFETIME
PLASMA SIMULATION
ERRORS