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Scaling of the scrape-off layer width in MAST L-mode plasmas as measured by infrared thermography

机译:红外热成像测量的桅杆L模式等离子体中的刮削层宽度缩放

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Introduction The power exhausted from a tokamak plasma is directed, via the scrape-off layer (SOL), towards plasma facing divertor targets that are designed to handle high heat fluxes. The width of the SOL is important for future device design since it plays a role in setting the magnitude of the parallel heat flux arriving at these surfaces and the distance that can be tolerated between the plasma edge and first wall materials. The well-established Eich equation [1,2] can be used to characterise the divertor heat flux profile as an exponential decay for the SOL width,λq, and a Gaussian spreading factor, S, due to diffusion around the last closed flux surface (LCFS) into the private flux region. The profile shape is given by: {formula}
机译:引言从托卡马克等离子体排出的功率通过刮削层(溶胶)朝向等离子体面向偏移器靶标,该靶向用于处理高热量通量。溶胶的宽度对于未来的设备设计是重要的,因为它在设定到达到达这些表面的平行热通量的大小以及可以在等离子体边缘和第一壁材料之间容忍的距离来发挥作用。良好的EICH方程[1,2]可用于表征转移器热通量轮廓作为溶胶宽度,λq和高斯扩散因子,S的指数衰减,由于最后闭合通量表面( LCFS)进入私人助焊区。轮廓形状由:{公式}给出

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