Development of a concept and basis for the DEMO diagnostic and control system

Biel, W.; Ariola, M.; Bolshakova, І.; Brunner, K. J.; Cecconello, M.; Ďuran, I.; Franke, T.; Giacomelli, L.; Giannone, L.; Janky, F.; Krimmer, A.; Luís, R.; Malaquias, A.; Marchiori, G.; Marchuk, O.; Mazon, D.; Pironti, A.; Quercia, A.; Rispoli, N.; Shawish, S. El; Siccinio, M.; Silva, A.; Sozzi, C.; Tartaglione, Gaetano; Todd, T.N.; Treutterer, W.; Zohm, H.

doi:10.1016/j.fusengdes.2022.113122

Cited by 28 publications

(23 citation statements)

References 111 publications

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“…The limited space available and remote maintenance considerably reduce the design freedom for the layout of the control system and its main components. For this reason, the implementation of the diagnostic components in the blanket have to be observed and studied in depth [ 108 , 109 ].…”

Section: Diagnostic Materialsmentioning

confidence: 99%

“…At the same time, the need to retract components into protected locations can only be compensated by integrating a large number of individual channels and sightlines, which in turn represents a huge design effort and will occupy significant space in the tokamak [ 109 ].…”

Section: Diagnostic Materialsmentioning

confidence: 99%

“…Finally, it is important to note that not all key features of the DEMO plasma scenario and technology have yet been well-defined and simultaneously demonstrated in large-scale experiments under relevant conditions. Therefore, at the current stage of DEMO research, the development of diagnostic and control systems should generally proceed according to the significant uncertainties associated with the plasma scenario and the machine properties [ 108 , 109 ].…”

Section: Diagnostic Materialsmentioning

confidence: 99%

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Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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Section: Diagnostic Materialsmentioning

confidence: 99%

Section: Diagnostic Materialsmentioning

confidence: 99%

Section: Diagnostic Materialsmentioning

confidence: 99%

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Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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“…Magnetic diagnostics are essential components for the operation and understanding of fusion machines [1][2][3][4][5]. In particular, inductive magnetic discrete probes, or pick-up coils [6], are widely used to measure the local magnetic flux density B and are typically installed as arrays on the inner and on the outer skin of the vacuum vessel, forming poloidal and toroidal belts.…”

Section: Introductionmentioning

confidence: 99%

“…For currently operated machines, such as JET, the drift is essentially due to an offset signal originating in the electronic integrator of the data acquisition system [7,8]. For the case of burning plasma experiments (BPXs) [9,10], such as ITER, and for future demonstration power plants (DEMO), such as the European DEMO [4,5], the drift problem is particularly challenging, for two reasons:…”

Section: Introductionmentioning

confidence: 99%

Long term operation of the radiation-hard Hall probes system and the path toward a high performance hybrid magnetic field sensor

Quercia

Pironti²,

Bolshakova³

et al. 2022

Nucl. Fusion

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The paper reports a systematic assessment of the Radiation-hard Hall Probes (RHP) magnetic diagnostic system of the JET tokamak, which is based on InSb semiconductor thin ﬁlms, and describes the path that lead to the proposal of an innovative magnetic probe concept. A relevant account of RHP operation during the recent Deuterium-Tritium experimental campaign (DTE2) is also provided, showing correct operation under ITER-like intense neutron ﬂux. The period considered for the systematic assessment of the RHP system ranges from October 2009 to March 2021, during which the machine produced more than 19000 pulses. The RHP system consists of six three-dimensional Hall probes, which have built-in recalibration capability, thanks to the presence of microsolenoids that produce a local known ﬁeld during a tailored automatic pre-pulse calibration sequence, that can also be initiated manually. During pulses, the microsolenoids can also be used as inductive sensors as their signals are recorded as well. Moreover, the system provides temperature measurements at the location of the probes, which are continuously recorded too. The assessment demonstrates accurate long-term operation of the RHP system. All the diagnostic channels reliably provide pre-pulse calibration data and pulse signals and the original sensitivities of the Hall sensors are preserved. Integration considerations and a data fusion analysis lead to the proposal of a high performance, compact, broadband, hybrid ﬁeld probe, consisting of the combination of an inductive coil and a Hall sensor, to be manufactured by means of the coil technology developed for ITER or an alternative concept with improved radiation-hardness. The hybrid probe is expected to deliver the advantages of both inductive and Hall sensing technologies, essentially in the same package size of a single ITER magnetic discrete probe. In particular, it would solve the problem of the drift of the integrator for long lasting burning plasma discharges. The signals produced by the coil and the Hall sensor, processed by means of a Luenberger-Kalman observer, provide a magnetic ﬁeld measurement which is non-drifting and low-noise. For these reasons, the hybrid probe has been proposed as the potential primary magnetic diagnostic sensor for future burning plasma experiments and demonstration fusion power plants.

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