Concept design of CFETR Tokamak machine

Song, Yuntao; Wu, Songtao; Li, J. G.; Wan, Baonian; Wan, Yuanxi; Fu, Peng; Ye, M. Y.; Liu, S. M.; Gao, Xiang

doi:10.1109/sofe.2013.6635362

Cited by 41 publications

(30 citation statements)

References 10 publications

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“…From the VV inner shell to the boundary of the plasma, a radial dimension of at least 1,000 mm is reserved to for the blanket, divertor, inner coils with their supports and the cooling system etc. The maximum size inside the VV is about 6,220 mm in horizontal direction, and 10,270 mm in vertical direction [5].…”

Section: Design Description Of Vacuum Vesselmentioning

confidence: 96%

“…The inner, outer shells and stiffening ribs between them are joined by welding. To reduce the difficulty of manufacturing, the cross-section of the VV (Dshape) is made up of five arcs and one straight line, which are tangential to each other [5]. According to the design experience in EAST and ITER [6,7], the two VV shells are both 50 mm in thickness.…”

Section: Design Description Of Vacuum Vesselmentioning

confidence: 99%

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Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption

et al. 2014

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China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5°sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV.

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Section: Design Description Of Vacuum Vesselmentioning

confidence: 96%

Section: Design Description Of Vacuum Vesselmentioning

confidence: 99%

Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption

et al. 2014

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“…Thus, each CS coil has 11 turns in radial direction. (2) The height of central solenoid is smaller than 13.2 m according to the dimension of the device. Hence, each CS coil is 36 turns in vertical direction that can meet the requirement of 2.14 m of the height of each CS coil.…”

Section: The Design Work Of Cs Coilsmentioning

confidence: 99%

“…CFETR acronym as "China Fusion Engineering Test Reactor" is a superconducting tokamak device which is in a stage of concept design [1,2]. The major design parameters of CFETR compared to ITER are given in Table 1 [3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Concept design of the CFETR central solenoid

Zheng

Song

Liu

et al. 2015

Fusion Engineering and Design

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“…In order to narrow the R&D gap between ITER and fusion power plant, the Chinese Fusion Engineering Test Reactor (CFETR) [1][2][3] was proposed with primary objectives to demonstrate 50-200 MW fusion power, to achieve 30-50% duty cycle and an overall blanket tritium breeding ratio (TBR) no less than 1.2. The TBR requirement is recognized to be the most challenging for blanket design due to the restrictions of the available blanket material properties, and the limited space for blanket provided in CFETR.…”

Section: Introductionmentioning

confidence: 99%