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

EAST team

Research output: Contribution to journalArticlepeer-review

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 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.

Original languageEnglish (US)
Pages (from-to)99-104
Number of pages6
JournalNuclear Materials and Energy
Volume18
DOIs
StatePublished - Jan 2019

Keywords

  • EAST
  • Limiter
  • Lithium
  • Plasma facing component

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science (miscellaneous)

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