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Electric probe diagnostics for measuring SOL parameters, wall and divertor fluxes in KSTAR

机译:电探针诊断程序,用于测量KSTAR中的SOL参数,壁和偏滤器通量

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Some components in electric probe diagnostics (EPDs) are improved in order to investigate characteristics of edge plasmas in the upstream scrape-off-layer (SOL) region and to measure wall and divertor fluxes during L-mode and H-mode plasma discharges in the Korea Superconducting Tokamak Advanced Research (KSTAR). From the upgrades in the EPDs, the measured error of the elapsed distance for the evaluation of the SOL profiles can be reduced up to 1% and the ion saturation current of up to 1.0A near an outer strike point (OSP) can be measured at the divertor region. In the SOL profile measurements during L-mode and inner wall limited plasma (B-T = 2.0T, I-p =0.4 MA), the e-folding lengths in the main SOL region lambda(Te) and lambda(ne) are evaluated as 3.5 cm and 2.1 cm, respectively. From particle flux measurement at the far SOL region during a diverted ELMy H-mode discharge (B-T = 1.8 T, I-p = 0.65 MA), peaked heat flux toward to outboard wall during ELM bursts is estimated up to similar to 20 k Wm(-2), which may be less than 1% of the peaked divertor heat flux expected for the neutral beam (NB) heating power P-NB of similar to 2.66 MW and stored energy W-TOT of similar to 0.38 MJ. In addition, the movement of the OSP during a diverted H-mode plasma (B-T = 2.4T, I-p = 0.5 MA) can be detected from the divertor probe measurement and peaked heat flux near the OSP is estimated as few MW m(-2) for P-NB = 3.0 MW, W-TOT = similar to 0.25 MJ. In this work, the technical details of the EPDs including its upgrades and some experimental results from EPD measurements are presented. (C) 2016 Elsevier B.V. All rights reserved.
机译:改进了电探针诊断(EPD)中的某些组件,以研究上游刮除层(SOL)区域中边缘等离子体的特性,并测量L型和H型等离子体放电过程中壁和偏流通量。韩国超导托卡马克高级研究(KSTAR)。通过EPD的升级,可将用于评估SOL轮廓的经过距离的测量误差降低至1%,并且可以在以下位置测量接近外部冲击点(OSP)时高达1.0A的离子饱和电流转向器区域。在L模式和内壁受限等离子体(BT = 2.0T,Ip = 0.4 MA)期间的SOL轮廓测量中,主要SOL区域中的lambda(Te)和lambda(ne)的电子折叠长度评估为3.5 cm和2.1厘米。根据ELMy H模式放电(BT = 1.8 T,Ip = 0.65 MA)期间远SOL区域的粒子通量测量,估计在ELM爆发期间朝向外壁的峰值热通量高达20 k Wm(- 2),其可能小于中性束(NB)加热功率P-NB约为2.66 MW和存储能量W-TOT约为0.38 MJ的预期偏滤器峰值热通量的1%。另外,可以从分流器探针测量中检测出在转向的H模式等离子体(BT = 2.4T,Ip = 0.5 MA)期间OSP的运动,并且估计OSP附近的峰值热通量为MW m(-2 )对于P-NB = 3.0 MW,W-TOT =类似于0.25 MJ。在这项工作中,介绍了EPD的技术细节,包括其升级以及EPD测量的一些实验结果。 (C)2016 Elsevier B.V.保留所有权利。

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