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Title: Conceptual design of DTT magnetic diagnostics
Authors: Baruzzo, M.
Pironti, A.
Albanese, R.
Ambrosino, R.
Artaserse, G.
Castaldo, A.
Cavazzana, R.
Cianfarani, C.
Crisanti, F.
Marchiori, G.
Marconato, N.
Marrelli, L.
Martin, P.
Mele, Adriano 
Peruzzo, S.
Ramogida, G.
Terranova, D.
Testa, D.
Zanca, P.
Zuin, M.
Issue Date: 2019
The Divertor Tokamak Test (DTT) is a new tokamak device whose main mission is to explore
innovative divertor concepts for DEMO and test them in heat loads conditions on plasma
facing components relevant to a fusion reactor. The device is presently going through a
detailed design process, and the tendering process has started for some of the components.
Magnetic diagnostics for plasma current and shape control, and vertical position stabilization
are essential diagnostics for tokamak operation, and are the first diagnostic components that
will need to be ready for installation and commissioning when DTT vacuum vessel and
magnets are assembled. The DTT operational conditions for in-vessel and ex-vessel magnetic
diagnostics resemble those that will be encountered in ITER (high heat flux, long pulses, large
Electromagnetic stresses), except for the 14MeV neutron effects. Furthermore the compact
machine assembly implies a very tight space for High Field Side sensors, both in-vessel and
ex-vessel, therefore a dedicated thin sensors design is mandatory.
In this work the conceptual design of DTT magnetic diagnostics will be presented, including
Mirnov Coils, LTCC coils, saddle loops, flux loops and diamagnetic loops, Hall probes and
optic fibre plasma current measurements. The constraints that have been taken into account in
choosing the sensors technology will be outlined, motivating the different design choices.
Sensors number and sensitivity have been determined with a model-based optimization
procedure: the error in the reconstruction of plasma current and current centroid position has
been iteratively estimated by varying the placement of a current filament on a grid spanning
the vacuum vessel volume. The maximum reconstruction error has been evaluated for
different sensors number, position and effective area (NA). The optimal sensors setup will be
discussed, in order to keep the error in plasma current less than 1%, and the error on the
current centroid position less than 1cm. Finally the difficult task of integrating the sensors
design with the machine first wall and vacuum vessel design will be discussed.
Rights: Attribution-NonCommercial-NoDerivatives 4.0 International
Appears in Collections:D3. Poster

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