The Superconducting Magnets for EAST Tokamak

Wei, Jing; Chen, W G; Wu, Wenqiang; Pan, Yannian; Gao, Daming; Wu, Songtao; Wu, Yu

doi:10.1109/tasc.2010.2040030

Cited by 25 publications

(6 citation statements)

References 4 publications

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“…This technology has been used successfully in model coils and in smaller fusion experiments. In fact, all superconducting fusion systems in operation or under construction (EAST, KSTAR, SST-1, LHD PF coils, Wendelstein 7-X, ITER) [14][15][16][17][18] use the Cable-in-Conduit-Conductor technology invented and developed in the US in the 1970s [19]. Magnet design for fusion applications requires multidisciplinary engineering skills including applied superconductivity, mechanical engineering, electrical engineering, materials science, and engineering design.…”

Section: Background On Fusion Magnetsmentioning

confidence: 99%

Smaller & Sooner: Exploiting High Magnetic Fields from New Superconductors for a More Attractive Fusion Energy Development Path

et al. 2016

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The current fusion energy development path, based on large volume moderate magnetic B field devices is proving to be slow and expensive. A modest development effort in exploiting new superconductor magnet technology development, and accompanying plasma physics research at high-B, could open up a viable and attractive path for fusion energy development. This path would feature smaller volume, fusion capable devices that could be built more quickly than low-to-moderate field designs based on conventional superconductors. Fusion's worldwide development could be accelerated by using several small, flexible devices rather than relying solely on a single, very large device. These would be used to obtain the acknowledged science and technology knowledge necessary for fusion energy beyond achievement of high gain. Such a scenario would also permit the testing of multiple confinement configurations while distributing technical and scientific risk among smaller devices. Higher field and small size also allows operation away from wellknown operational limits for plasma pressure, density and current. The advantages of this path have been long recognized-earlier US plans for burning plasma experiments (compact ignition tokamak, burning plasma experiment, fusion ignition research experiment) featured compact high-field designs, but these were necessarily pulsed due to the use of copper coils. Underpinning this new approach is the recent industrial maturity of high-temperature, highfield superconductor tapes that would offer a truly ''game changing'' opportunity for magnetic fusion when developed into large-scale coils. The superconductor tape form and higher operating temperatures also open up the possibility of demountable superconducting magnets in a fusion system, providing a modularity that vastly improves simplicity in the construction, maintenance, and upgrade of the coils and the internal nuclear engineering components required for fusion's development. Our conclusion is that while tradeoffs exist in design choices, for example coil, cost and stress limits versus size, the potential physics and technology advantages of high-field superconductors are attractive and they should be vigorously pursued for magnetic fusion's development.

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Section: Background On Fusion Magnetsmentioning

confidence: 99%

Smaller & Sooner: Exploiting High Magnetic Fields from New Superconductors for a More Attractive Fusion Energy Development Path

et al. 2016

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“…For steady-state tokamak operation, the magnetic coils will have to be superconducting. Tokamaks such as ToreSupra (now WEST) in France and EAST in China operate with superconducting coils of niobium titanium [17,18], and ITER will use niobium titanium (poloidal field and error field correction) and niobium tin (toroidal field and central solenoid) for its superconducting magnets [19].…”

Section: (C) High-temperature Superconductorsmentioning

confidence: 99%

Smaller and quicker with spherical tokamaks and high-temperature superconductors

Windridge

2019

Phil. Trans. R. Soc. A.

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“…This can be considered as an ultimate back up solution not to be implemented at the beginning of the ITER TF commissioning. The final choice between solutions has to be made after further observations on EAST [7] and KSTAR [6]. It has to be adjusted during ITER commissioning.…”

Section: Summary For Quench Detection In Iter Tf Coil Systemmentioning

confidence: 99%

Investigations About Quench Detection in the ITER TF Coil System

Coatanea

Duchateau

Nicollet

et al. 2012

IEEE Trans. Appl. Supercond.

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22nd International Conference on Magnet Technology (MT), ITER Org, Marseille, FRANCE, SEP 12-16, 2011International audienceDue to the large stored energy (40 GJ) and the small allowed number of fast discharges (50), severe requirements have been put in the ITER project for the Toroidal Field (TF) coil system in comparison with the Poloidal Field (PF) and Central Solenoid (CS) systems, aiming at avoiding any fast discharge not related to a quench. A very important point, which has to be examined, is whether a quench detection based on a co-wound tape, recommended in the ITER project, and located inside the conductor insulation is compulsory to ensure the inductive voltage compensation. Another possible solution is the balance of the voltage of TF coils or TF coils subcomponents. The sensitivity of the quench detection systems is examined according to the different types of flux variations experienced in the machine. During plasma discharge, the sensitivity to poloidal flux variations and plasma paramagnetism is highlighted, the last effect being illustrated for Tore Supra. It is eventually recommended to select the quench detection by balancing coils or coils subcomponents. This solution has been adopted for Tore Supra, KSTAR and in JT-60SA project. The level of refinement should be adjusted during commissioning, as a function of the required voltage detection level (0.4 V) and to the required holding time (1 s)

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The Superconducting Magnets for EAST Tokamak

Cited by 25 publications

References 4 publications

Smaller & Sooner: Exploiting High Magnetic Fields from New Superconductors for a More Attractive Fusion Energy Development Path

Smaller & Sooner: Exploiting High Magnetic Fields from New Superconductors for a More Attractive Fusion Energy Development Path

Smaller and quicker with spherical tokamaks and high-temperature superconductors

Investigations About Quench Detection in the ITER TF Coil System

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