Published January 2019 | Version v1
Journal article

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

  • 1. CAS Key Laboratory of Photovoltaic and Energy Conservation Materials, Hefei 230031 (China)
  • 2. Institue of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China)
  • 3. Princeton University, Plasma Physics Laboratory Princeton, Princeton, NJ 08543 (United States)
  • 4. Johns Hopkins University, Baltimore, MD 21211 (United States)

Description

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.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nme.2018.12.017

Additional details

Identifiers

DOI
10.1016/j.nme.2018.12.017;
PII
S2352179118301479;

Publishing Information

Journal Title
Nuclear Materials and Energy
Journal Volume
18
Journal Page Range
p. 99-104
ISSN
2352-1791

Optional Information

Copyright
Copyright (c) 2018 The Authors. Published by Elsevier Ltd.
Collaborations
EAST team