Conceptual Design and Engineering Analysis for CFETR Upper RMP Coils

Zhang, Jianwu; Zhang, Shanwen; Xiang, Ji

doi:10.1007/s10894-015-9911-x

Cited by 3 publications

(2 citation statements)

References 2 publications

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“…To achieve a long duration of steady state operation maintaining a fixed β N , efficient schemes for ELM control are necessary. Originally, three sets of RMP coils have been conceptually and physically designed to match upper, middle and lower windows for CFETR [29], which could be used for the correction of error field, active feedback control of RMW, and control of ELM. These studies will inform whether additional ELM suppression or control strategies, such as RMP fields, will be required.…”

Section: Summary and Discussionmentioning

confidence: 99%

Dominant two-fluid magnetohydrodynamic instabilities in CFETR upgrade phase-I scenario in presence of perfect conducting wall

Cheng

Zhu

Banerjee

et al. 2019

Plasma Phys. Control. Fusion

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The dominant two-fluid magnetohydrodynamic (MHD) stabilities of China Fusion Engineering Test Reactor upgrade phase-I baseline equilibria in presence of perfect conducting wall have been evaluated using the initial value code NIMROD. Our MHD simulations show that for equilibrium with q axis < 1, high-n edge localized modes are slightly stabilized by toroidal shear flow, and n=1 mode is found to be unstable in the core region with the characteristic of sawtooth instability. For q axis >2 equilibrium, all modes are found to be unstable but edge localized both in single-fluid and two-fluid MHD models. Specifically for n 13 modes, the two-fluid MHD model gives a slightly higher growth rate than the single-fluid MHD model, while for n>13 modes, this trend becomes the opposite, which means the two-fluid MHD model is needed for high-n mode analysis. In addition, n=1-10 modes are found to be more unstable with increasing wall position and eventually their growth rates approach values in the no-wall limit.

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Section: Summary and Discussionmentioning

confidence: 99%

Dominant two-fluid magnetohydrodynamic instabilities in CFETR upgrade phase-I scenario in presence of perfect conducting wall

Cheng

Zhu

Banerjee

et al. 2019

Plasma Phys. Control. Fusion

View full text Add to dashboard Cite

show abstract

“…edge localized modes (ELMs) in JT-60SA [7]. But, the use of internal control coil currents in a fusion reactor is challenged by heat removal and the dynamic stress on the control coils from time-varying currents [8]. Internal ELM-control coils will be installed in ITER [9], but their use for RWM control is still under evaluation [10].…”

mentioning

confidence: 99%

Suppression of MHD modes with active phase-control of probe-injected currents

et al. 2021

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Active phase-control of probe-injected current is shown to both suppress and amplify long-wavelength rotating magnetohydrodynamic instabilities in the HBT-EP tokamak. Four probes are connected in quadrature and energized to drive non-axisymmetric currents through the edge of the tokamak, creating magnetic perturbations comparable to previously-studied saturated kink modes or resonant magnetic perturbations that are generated by an external control coil array. Measurements of the magnetic perturbations from the probe-injected currents determine a set of current-carrying helical filaments used to model active feedback control of resistive wall modes. These experiments suggest current-injection feedback may be an effective alternative to external control coils for control of RWMs and other long-wavelength kink-like modes at the edge of tokamaks.

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Heat transfer analysis of tokamak in-vessel coil water-cooling channel joint

Jiang

Huang

et al. 2021

Fusion Engineering and Design

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Conceptual Design and Engineering Analysis for CFETR Upper RMP Coils

Cited by 3 publications

References 2 publications

Dominant two-fluid magnetohydrodynamic instabilities in CFETR upgrade phase-I scenario in presence of perfect conducting wall

Dominant two-fluid magnetohydrodynamic instabilities in CFETR upgrade phase-I scenario in presence of perfect conducting wall

Suppression of MHD modes with active phase-control of probe-injected currents

Heat transfer analysis of tokamak in-vessel coil water-cooling channel joint

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