Experiments of continuously and stably flowing lithium limiter in EAST towards a solution for the power exhaust of future fusion devices. (January 2019)

• Record Type: Journal Article
• Authors: Hu, J.S.; Zuo, G.Z.; Maingi, R.; Sun, Z.; Tritz, K.; Xu, W.; Yang, Q.X.; Andruczyk, D.; Huang, M.; Meng, X.C.; Gong, X.Z.; Ruzic, D.N.; Ni, M.J.; Wan, B.N.; Li, J.G.
• Is Part Of: Nuclear materials and energy. Volume 18(2019)
• Page Start: 99
• Page End: 104
• Publication Date: 2019-01
• Subjects: Limiter -- Lithium -- Plasma facing component -- EAST; Nuclear energy -- Periodicals; Nuclear fuels -- Periodicals; Nuclear reactors -- Materials -- Periodicals; Radioactive substances -- Periodicals; 621.4833
• DOI: 10.1016/j.nme.2018.12.017
• Languages: English
• ISSNs: 2352-1791

Abstract

Abstract: Liquid lithium (Li) can partly ameliorate lifetime and power-exhaust issues of plasma facing components (PFCs) by enabling a self-healing, self-replenishing surface with a reduced susceptibility to neutron damage in future fusion devices. To assess operational stability and heat-exhaust capability under tokamak exposure, two generations of continuously flowing liquid Li (FLiLi) limiters on the concept of a thin flowing Li film have been successfully designed and tested in high performance discharges in EAST. The design uses a circulating Li layer with a thickness of <0.1 mm and a flow rate ∼2 cm 3 s −1 . In addition, the limiter employs a novel electro-magnetic pump to drive liquid Li flow from a collector at the bottom of the limiter into a distributor at its top. Free surface gravitational flow closes the loop for a continuously flowing liquid Li film on the wetted PFC. Here we summarize key FLiLi limiter development and experimental results in H-mode plasmas.