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• W3045533878 startingPage "102001" @default.
• W3045533878 abstract "Abstract Extensive experiments of advanced scenario development, which contribute to the ITER hybrid operational scenario have been carried out on experimental advanced superconducting tokamak (EAST) tokamak recently with the ITER-like tungsten divertor. The <?CDATA ${beta _N}$?> <mml:math xmlns:mml=http://www.w3.org/1998/Math/MathML overflow=scroll> <mml:mrow> <mml:msub> <mml:mi>β</mml:mi> <mml:mi>N</mml:mi> </mml:msub> </mml:mrow> </mml:math> in this operational scenario is intermediate up to 2.1 (EAST#78987, <?CDATA ${beta _N}$?> <mml:math xmlns:mml=http://www.w3.org/1998/Math/MathML overflow=scroll> <mml:mrow> <mml:msub> <mml:mi>β</mml:mi> <mml:mi>N</mml:mi> </mml:msub> </mml:mrow> </mml:math> ∼ 2.1, I p ∼ 0.45 MA, q 95 = 3.7, <?CDATA ${B_T}$?> <mml:math xmlns:mml=http://www.w3.org/1998/Math/MathML overflow=scroll> <mml:mrow> <mml:msub> <mml:mi>B</mml:mi> <mml:mi>T</mml:mi> </mml:msub> </mml:mrow> </mml:math> ∼ 1.5 T, 3 MW neutron beam injection and 1 MW 4.6 GHz lower hybrid wave). In these hybrid H-mode plasmas, the internal transport barrier (ITB) has been frequently observed with central flat q profile and it is found that the fishbone mode ( m / n = 1/1) can be beneficial to sustain the central flat ( q (0) ∼ 1) q profile, thus a stable ITB can be obtained. In this case, better plasma performance is achieved. The formation of the ITB of the electron density is related to the fishbone activities. Energy transport analysis shows that the fishbone instabilities have a suppression on electron turbulent energy transport, while the ITB of ion temperature is due to the suppression of high-k modes (electron temperature gradient). The mechanism of turbulence suppression from fishbone instabilities in the EAST tokamak is not clear and needs more investigation. It is also observed that the power threshold for ITB formation is <?CDATA $ geq $?> <mml:math xmlns:mml=http://www.w3.org/1998/Math/MathML overflow=scroll> <mml:mo>≥</mml:mo> </mml:math> 3.5 MW, which is consistent with the scaling law for other tokamaks. The dimensionless parameter <?CDATA $G{text{ }}$?> <mml:math xmlns:mml=http://www.w3.org/1998/Math/MathML overflow=scroll> <mml:mi>G</mml:mi> <mml:mrow> <mml:mtext> </mml:mtext> </mml:mrow> </mml:math> ( <?CDATA $ = {text{ }}{H_{89}}{beta _N}/q_{95}^2$?> <mml:math xmlns:mml=http://www.w3.org/1998/Math/MathML overflow=scroll> <mml:mo>=</mml:mo> <mml:mrow> <mml:mtext> </mml:mtext> </mml:mrow> <mml:mrow> <mml:msub> <mml:mi>H</mml:mi> <mml:mrow> <mml:mn>89</mml:mn> </mml:mrow> </mml:msub> </mml:mrow> <mml:mrow> <mml:msub> <mml:mi>β</mml:mi> <mml:mi>N</mml:mi> </mml:msub> </mml:mrow> <mml:mrow> <mml:mo>/</mml:mo> </mml:mrow> <mml:msubsup> <mml:mi>q</mml:mi> <mml:mrow> <mml:mn>95</mml:mn> </mml:mrow> <mml:mn>2</mml:mn> </mml:msubsup> </mml:math> ) obtained in the EAST reaches 0.3, but is still lower than the ITER hybrid scenario design ( G ≥ 0.4) and needs more extension. Further investigation of extending the operational regimes, such as expanding the ITB foot outwards, would be important for the development of the hybrid and steady-state scenarios for next-step fusion devices like ITER and CFETR." @default.
• W3045533878 created "2020-08-03" @default.
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• W3045533878 date "2020-09-02" @default.
• W3045533878 modified "2023-10-12" @default.
• W3045533878 title "Experimental progress of hybrid operational scenario on EAST tokamak" @default.
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• W3045533878 doi "https://doi.org/10.1088/1741-4326/abaa91" @default.
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