To study the potential applications of liquid lithium (Li) as plasma facing material, the third generation of flowing liquid Li (FLiLi) limiter has been designed and successfully tested in EAST tokamak H-mode discharges in the 2018 run campaign. The stability of liquid Li on FLiLi surface, and Li splashing and its effect on the plasma performance are investigated in detail. Li splashing was observed in L-mode and H-mode discharges due to Rayleigh-Taylor (R-T) instability, resulting from electromagnetic forces $\overrightarrow{J}\times \overrightarrow{B}$. Li splashing in low-parameter plasma decreased both core and edge electron temperatures, resulting in the degradation of plasma energy confinement and even H-L back transition, however, it almost did not influence plasma confinement performance in high-parameter plasma. These findings indicate that high-parameter plasma has higher tolerance to Li impurities than low-parameter plasma. By contrast, tungsten splashing from the melted layer on the upper divertor was also induced by the R-T instability but generally resulted in plasma disruption, which suggests lower tolerance to tungsten impurities in EAST tokamak.

为了研究液态锂（Li）作为面向等离子体的材料的潜在应用，已设计了第三代液态锂（FLiLi）限流器，并在2018年的竞选活动中成功地在EAST托卡马克H型放电器中进行了测试。详细研究了液态锂在FLiLi表面的稳定性，Li的飞溅及其对等离子体性能的影响。由于电磁力引起的瑞利-泰勒（RT）不稳定性，在L模式和H模式放电中观察到Li飞溅$\overrightarrow{Ĵ}\times \overrightarrow{乙}$。Li在低参数等离子体中的溅射降低了核心和边缘电子的温度，导致等离子体能量限制的下降甚至HL反向跃迁，但是，它几乎不影响高参数等离子体中的等离子体限制性能。这些发现表明，高参数等离子体对锂杂质的耐受性比低参数等离子体高。相比之下，RT不稳定性也会引起钨从上部分流器上的熔融层飞溅，但通常会导致等离子体破裂，这表明对EAST托卡马克中的钨杂质耐受性较低。