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Effect of 3-D fields on divertor detachment and associated pedestal profiles in NSTX H-mode plasmas

机译:3-D场对NSTX H模式等离子体中的倾斜器分离和相关基座谱的影响

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The effect of externally applied 3-D magnetic perturbations on the divertor heat and particle flux profiles has been actively studied in various tokamaks, for example in DIII-D [1] and NSTX [2,3]. These phenomena are directly related with the 'strike point (SP) splitting' caused by the 3-D magnetic field perturbations to the plasma edge [4]. As ITER is considering the use of 3-D magnetic fields for the control of ELM transient heat loads, a detailed understanding of the physical mechanism leading to the ELM suppression as well as the changes to the edge transport associated with the application of 3-D fields is necessary. Partial detachment is the divertor operation regime selected for ITER high fusion performance operation, as it allows control of heat fluxes to the divertor and erosion at the material surface during the stationary phase to values acceptable for the PEC operation lifetime. It is essential that the two schemes be compatible with each other. Thus we have investigated the effect of applied 3-D fields on the divertor detachment and its relation to the pedestal profiles in National Spherical Torus Experiment (NSTX).
机译:在各种Tokamak中,在各种Tokamak中研究了外部施加的3-D磁性扰动对转子热量和颗粒磁通型的影响,例如DIII-D [1]和NSTX [2,3]。这些现象与由3-D磁场扰动引起的等离子体边缘的“击球点(SP)分裂”直接相关[4]。由于镜头在考虑使用3-D磁场来控制ELM瞬态热负荷,详细了解导致ELM抑制的物理机制以及与3-D应用相关的边缘传输的变化字段是必要的。部分拆卸是选择用于浸泡的高熔融性能操作的转向器操作制度,因为它允许在固定相期间控制在材料表面上的倒档器和腐蚀的热量,以对PEC操作寿命可接受的值。这两种方案必须彼此兼容。因此,我们研究了应用的三维场对倾斜器分离的影响及其与国家球形圆环实验(NSTX)中的基座谱的关系。

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