Error field and correction coils in DTT: A preliminary analysis

Albanese, Raffaele; Bolzonella, T.; Chiariello, Andrea G.; Cucchiaro, A.; Iaiunese, Antonio; Lampasi, Alessandro; Martone, R.; Piron, L.; Pizzuto, A.; Zumbolo, Pasquale

doi:10.1016/j.fusengdes.2023.113437

Cited by 6 publications

(2 citation statements)

References 10 publications

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“…Non-axisymmetric in-vessel coils are being designed for the purpose of ELM mitigation and suppression on DTT. The design of these coils is principally driven by the following requirements: (i) physical constrains for in-vessel mounting, (ii) integration with other in-vessel sub-systems, (iii) double purpose of ELM and Error Field (EF) control [14]. An advantage of ELM control with RMPs is that it can be used to reduce the frequency and severity of ELMs without affecting the overall performance of the tokamak plasma.…”

Section: Introductionmentioning

confidence: 99%

Numerical investigation of toroidal plasma response for ELM control via magnetic perturbations in the DTT Tokamak

Pigatto,

Bolzonella,

Bonotto

et al. 2023

Nucl. Fusion

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Linear plasma response modeling is exploited in this work to assess the effectof different coil configurations on Edge Localized Mode (ELM) stability in full poweroperational scenarios for the Divertor Tokamak Test (DTT) facility, presently underconstruction at the ENEA site of Frascati (Italy). The MARS-F code is used tocompute, in toroidal geometry and including flow, the resistive plasma response todifferent vacuum fields with toroidal mode numbers n=1,2,3. Peeling-like responsein particular, correlated with ELM control, is found to be significant for n=2,3perturbations while n=1 induces a large core response in the investigated scenarios.Two metrics are used to link plasma response to ELM control. Namely the local normalplasma displacement in the x-point region and the Chirikov parameter in PEST-likestraight-field-line coordinates. These criteria are used to predict optimal phasing ofthe active coil arrays and current thresholds based on empirical evidence. Dependingon the number of active coils and on the scenario, coil currents between 20 − 40 kAtare predicted to be effective for ELM mitigation in DTT.

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Section: Introductionmentioning

confidence: 99%

Numerical investigation of toroidal plasma response for ELM control via magnetic perturbations in the DTT Tokamak

Pigatto,

Bolzonella,

Bonotto

et al. 2023

Nucl. Fusion

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“…These errors are independent of each other at each assembly point for blanket modules and BSS. To systematically assess the EFs introduced by this assembly error in the blanket system [26,[33][34][35],…”

Section: The Efs Introduced By Assembly Errormentioning

confidence: 99%

The effect of blanket system and port plugs on the harmonic components of error field and optimizing approach investigation

Liu,

Lei,

et al. 2023

Nucl. Fusion

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The fusion plasma is sensitive to the penetration of the toroidal mode numbers n harmonic components of the error fields (EFs), and the toroidal mode components of the EFs are closely tied to the toroidal distribution of the magnetic field source. The primary source of EFs within the magnetic field sources is the current source, such as the magnet system, while the magnetic field produced by magnetized ferromagnetic materials may also generate EFs. The ferromagnetic field source, such the reduced-activation ferritic-martensitic steel, represent a smaller portion of the EFs source. However, the use of ferromagnetic materials is expected to increase significantly as tokamak research transitions from experimental devices to demonstration and commercial reactors, particularly for the structural materials of in-vessel components and port plugs. Predictably, the EFs induced by ferromagnetic materials will increase and may even surpass the design specifications. In this study, the EFs introduced by the water-cooling ceramic breeder blanket system and the vacuum vessel port plugs of China Fusion Engineering Test Reactor are comprehensively analyzed by an analytical approach and finite element numerical approach, which is based on the Fourier decomposition. The results reveal a clear linear relationship between the EFs formed by the saturated magnetization module and its rigid displacement deviating from periodic symmetry, as well as the same behavior in EFs and overall magnetization intensity. Compared to the assembly error of the blanket system, the EFs that may be introduced by the equatorial ports and plugs are substantial, including larger n ⩽ 3 toroidal mode harmonic components that can lead to lock mode and disruption. Moreover, using the correlation between harmonic components and symmetrical periods, specific toroidal mode components can be selectively shielded.

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