Nuclear Materials and Energy (Jan 2019)

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

  • J.S. Hu,
  • G.Z. Zuo,
  • R. Maingi,
  • Z. Sun,
  • K. Tritz,
  • W. Xu,
  • Q.X. Yang,
  • D. Andruczyk,
  • M. Huang,
  • X.C. Meng,
  • X.Z. Gong,
  • D.N. Ruzic,
  • M.J. Ni,
  • B.N. Wan,
  • J.G. Li

Journal volume & issue
Vol. 18
pp. 99 – 104

Abstract

Read online

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 cm3s−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. Keywords: Limiter, Lithium, Plasma facing component, EAST