Concept design of the CFETR central solenoid

Zheng, Jinxing; Song, Yuntao; Liu, Xufeng; Li, Jiangang; Wan, Yuanxi; Wan, Baonian; Ye, Minyou; Wu, Huan

doi:10.1016/j.fusengdes.2014.12.018

Cited by 18 publications

(4 citation statements)

References 12 publications

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“…The CFETR concept design has been carried out for nearly four years. The previous approach focused on Phase I which is based on a smaller machine with major/minor radius R = 5.7 m/a = 1.6 m and B T = 4-5 T. Physics design on operating scenarios, some key concept engineering designs and R&D including full size vacuum vessel (VV) manufacture as well as key tritium technology development, first wall (FW) and divertor materials have been carried out [8][9][10][11][12][13]. However, to fulfill the goals of Phase II, CFETR must be upgraded to a larger size device.…”

Section: Nuclear Fusionmentioning

confidence: 99%

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Overview of the present progress and activities on the CFETR

et al. 2017

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The China Fusion Engineering Test Reactor (CFETR) is the next device in the roadmap for the realization of fusion energy in China, which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). CFETR will be operated in two phases. Steady-state operation and self-sufficiency will be the two key issues for Phase I with a modest fusion power of up to 200 MW. Phase II aims for DEMO validation with a fusion power over 1 GW. Advanced H-mode physics, high magnetic fields up to 7 T, high frequency electron cyclotron resonance heating and lower hybrid current drive together with off-axis negative-ion neutral beam injection will be developed for achieving steady-state advanced operation. The recent detailed design, research and development (R&D) activities including integrated modeling of operation scenarios, high field magnet, material, tritium plant, remote handling and future plans are introduced in this paper.

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Section: Nuclear Fusionmentioning

confidence: 99%

“…The CFETR includes CS coils, TF coils, PF coils, and CC [11,13]. To obtain a higher magnetic field and higher fusion power, high performance superconducting magnet with advanced Jc Nb 3 Sn RRP superconducting strands and high temperature superconductors of Bi2212 material are used for the CFETR reactor [24].…”

Section: The Magnet Systemmentioning

confidence: 99%

Overview of the present progress and activities on the CFETR

et al. 2017

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“…The OH coils provide, by changing the current rapidly in the coils, the electric field needed to break down the plasma. This driven current provides OH of plasma due to the plasma resistance [20]. The OH coils consist of two main components including a central solenoid and its outer turns.…”

Section: Oh System Of the Taban Tokamakmentioning

confidence: 99%

Design, simulation and construction of the Taban tokamak

Mirzaei¹,

Amrollahi²

2018

Plasma Sci. Technol.

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“…For the CFETR in phase I, the central solenoid (CS) must provide most of the volt-seconds needed to induce and sustain a 10 MA plasma [3,4]. It consists of six vertically stacked Nb 3 Sn modules, which are designed to produce a peak field of 12 T.…”

Section: Introductionmentioning

confidence: 99%

Mechanical performance evaluation of the CFETR central solenoid model coil design

et al. 2017

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The Chinese Fusion Engineering Test Reactor (CFETR) Central Solenoid Model Coil is being fabricated by the Institute of Plasma Physics Chinese Academy of Sciences. The Model Coil is comprised of Nb3Sn and NbTi modules held together by a preload structure. It will operate at 4.5 K to produce a peak field of 12 T at 48 kA. In order to investigate the feasibility and integrity of the Model Coil design before its manufacturing, the mechanical performance has been evaluated for the room temperature preload, 4.5 K stand-by and 48 kA operating conditions. A 1/15 3D detailed model that consists of jackets, insulations, bladders, buffers and preload structure, is constructed and simulated using the coupled structural-thermal-electromagnetic solver of ANSYS. In contrary to a smeared winding pack model, our analysis with the detailed model can directly and precisely simulate the differential thermal contraction effect of the preload structure, jacket and insulations, as well as the electromagnetic load acting on the jacket. The detailed deformation and stress behaviors of the Model Coil are illustrated and discussed. The results indicate that the final design of the CFETR Central Solenoid Model Coil is reasonably conservative and satisfy the design criteria.

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Concept design of the CFETR central solenoid

Cited by 18 publications

References 12 publications

Overview of the present progress and activities on the CFETR

Overview of the present progress and activities on the CFETR

Design, simulation and construction of the Taban tokamak

Mechanical performance evaluation of the CFETR central solenoid model coil design

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