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Power balance investigation in long-pulse high-performance discharges with ITER-like tungsten divertor on EAST
Nuclear Fusion ( IF 3.5 ) Pub Date : 2020-08-09 , DOI: 10.1088/1741-4326/aba0c6
Y. K. Liu 1, 2 , X. Gao 2, 3 , K. Hanada 4 , Y. W. Yu 3 , H. Q. Liu 3 , L. Yang 3 , T. Zhang 3 , Y. X. Jie 2, 3 , J. P. Qian 3 , L. Zeng 3 , T. F. Ming 3 , X. J. Liu 3 , S. C. Liu 3 , T. J. Xu 3 , Y. Chen 3 , Q. Zhuang 3, 5 , Y. L. Li 3, 5 , K. F. Gan 3, 6 , B. Zhang 3 , M. W. Chen 3 , P. F. Zi 3 , Y. M. Wang 3 , G. S. Li 3 , K. Z. Zhu 3 , T. Zhou 3 , L. Li 3 , L. Cao 3 , X. Z. Gong 3 , D. M. Yao 3 , K. Wang 1 , L. Wang 3 , J.G. Li 2, 3 , the EAST Team 3
Affiliation  

The Experimental Advanced Superconducting Tokamak (EAST) research program concentrates on demonstrating steady-state high-performance H-mode operations with ITER-like tungsten divertor. Calorimetry was applied to actively water-cool the plasma facing components (PFCs) by increasing the water temperature for power balance investigation. Considering the energy balance of EAST long-pulse high-performance discharges with upper single null (USN) configuration, thus far, approximately 78% of the injected energy could be accounted for. The method of estimation of heat flux on upper tungsten divertor target with a high time- and spatial-resolved infrared camera has been developed, and the sum of its heat load was found to be significantly consistent with that measured through calorimetry. The record longest steady-state H-mode plasma #73 999 was sustained for up to 101.2 s with net injected energy exceeding ∼0.25 GJ in the USN configuration. Heat load analysis of this discharge using cal...

中文翻译:

在EAST上使用类似ITER的钨分流器对长脉冲高性能放电进行功率平衡研究

实验高级超导托卡马克(EAST)研究计划专注于演示类似ITER的钨分流器的稳态高性能H模式操作。量热法通过提高水温来进行功率平衡研究,从而有效地对面向等离子体的组件(PFC)进行水冷。考虑到具有单一高零位(USN)配置的EAST长脉冲高性能放电的能量平衡,到目前为止,大约可占注入能量的78%。开发了一种利用高时空分辨红外摄像机估算上部钨分流器目标热通量的方法,发现其总热负荷与通过量热法测得的热负荷总和显着一致。在USN配置中,记录的最长的稳态H型等离子体#73 999维持了长达101.2 s的净注入能量超过0.25 GJ。使用校准器对该放电进行热负荷分析
更新日期:2020-08-10
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