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This paper presents the multiple set of requirements for the ITER magnetic diagnostic systems and the current status of the various R&D activities performed by the EU partners. [ABSTRACT FROM AUTHOR]

Examines the design of tokamak configuration variable to create plasma shapes. Requirement of plasma flexibility; Description of the magnetic sensor geometry, fabrication, calibration, associated electronics and diagnostic operation in sensor position and monitoring; Method for deriving corrections in sensor position and calibration.

An accurate and reliable measurement of poloidal β is essential to assess the performances of Joint European Torus (JET). The diamagnetic loop can measure β values as low as 0.1 in JET discharges with a plasma current larger than 2 × 10[sup 6] A. The instrumentation used includes a flux loop rigidly fitted on a toroidal field (TF) coil, a large Rogowski coil measuring the TF busbar current, and a displacement gauge measuring the TF coil expansion. The fluxes to be compensated originate, in order of importance, from the TF current, the eddy current in the vessel, the TF coil expansion, and the stray coupling with the poloidal fields. The TF and eddy currents must be particularly well compensated on JET since the plasma current starts before the toroidal field has reached its plateau value. Comparison between the diamagnetic and other evaluations of β shows a good agreement. [ABSTRACT FROM AUTHOR]