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Due to the critical impact on the plasma control, the reliability of the magnetic diagnostic system in a tokamak should be continuously supervised. A new procedure based on a robust estimation of the expected field in the probe region and its comparison with the actual measurement has been recently proposed and assessed on several devices. The application of the procedure in the case of the Divertor Tokamak Test facility is here discussed.
In a world increasingly facing new challenges at the forefront of plasma scientific research and technological innovation, CNR and ISTP pledge progress and achieve an impact in the integration of research into societal practices and policy
