Title: Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST

Journal Article · · Nuclear Fusion
 [1];  [2];  [3]; ORCiD logo [4];  [1];  [1];  [5];  [5];  [1];  [1];  [6];  [1];  [1];  [1];  [1]; ORCiD logo [1];  [1];  [1];  [1];  [1] more »;  [7];  [3]; ORCiD logo [3];  [8];  [1] « less
  1. Chinese Academy of Sciences, Anhui (China)
  2. Chinese Academy of Sciences, Anhui (China); CAS key Laboratory of Photovoltaic and Energy Conservation Materials, Hefei (China)
  3. Princeton Univ., Princeton, NJ (United States)
  4. Chinese Academy of Sciences, Anhui (China); Princeton Univ., Princeton, NJ (United States)
  5. Chinese Academy of Sciences, Anhui (China); Shenzhen Univ., Shenzhen (China)
  6. Hefei Univ. of Technology, Hefei (China)
  7. Johns Hopkins Univ., Baltimore, MD (United States)
  8. Univ. of Chinese Academy of Sciences, Beijing (China)

Significant engineering and physic progress was made by the upgrade of a flowing liquid lithium limiter (FLiLi) inserted into EAST H-mode discharges in 2016. The progress includes an improvement of liquid Li coverage uniformity, no macroscopic surface erosion by plasma materials interaction, effective removal of 55% of the discharge heat flux using high pressure He cooling during ohmic discharges, and the demonstrated ability to restart Li flow for a second experiment performed a week after the first. With increasing Li flow rate, fuel particle recycling and Fe impurity radiation gradually decreased, and plasma performance slightly improved, but there was no impact on the edge tungsten influx. No obvious Li bursts appeared during operation with up to about 4.5 MW auxiliary heating power with peak heat flux reaching ~4 MW m–2 on FLiLi. In addition, a gradual mitigation of edge localized mode (ELM) activity was observed with FLiLi operation. Lastly, short-lived ELM-free phases were observed for the first time in EAST during FLiLi insertion, with increasing τ E and transient H98(y, 2) < 2.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Contributing Organization:
EAST team
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
1512785
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 1 Vol. 59; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (45)

Liquid lithium divertor system for fusion reactor journal June 2009
Review of FTU results with the liquid lithium limiter journal November 2010
Active radiative liquid lithium divertor concept journal December 2014
Liquid lithium surface control and its effect on plasma performance in the HT-7 tokamak journal December 2014
An overview of lithium experiments on HT-7 and EAST during 2012 journal December 2014
Molecular dynamics simulation of wetting behaviors of Li on W surfaces journal April 2017
Density profile evolution on EAST tokamak by the polarimeter/interferometer system journal June 2018
Effects of large area liquid lithium limiters on spherical torus plasmas journal March 2005
Impact of lithium-coated walls on plasma performance in the TJ-II stellarator journal June 2009
First results of lithium experiments on EAST and HT-7 journal August 2011
Macroscopic motion of liquid metal plasma facing components in a diverted plasma journal August 2011
Modelling of lithium erosion and transport in FTU lithium experiments journal July 2013
Overview of TJ-II experiments
  • López-Bruna, D.
  • PLASMA AND FUSION SCIENCE: 16th IAEA Technical Meeting on Research using Small Fusion Devices; XI Latin American Workshop on Plasma Physics, AIP Conference Proceedings https://doi.org/10.1063/1.2405965
conference January 2006
A flowing liquid lithium limiter for the Experimental Advanced Superconducting Tokamak journal February 2015
Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment journal May 2017
Upgraded flowing liquid lithium limiter for improving Li coverage uniformity and erosion resistance in EAST device journal December 2017
Application of lithium in systems of fusion reactors. 1. Physical and chemical properties of lithium journal March 2009
Overview of the FTU results journal October 2005
Overview of the FTU results journal September 2007
Overview of TJ-II experiments journal September 2007
Overview of the FTU results journal September 2009
Performance projections for the lithium tokamak experiment (LTX) journal April 2009
Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices journal August 2011
Overview of TJ-II experiments journal August 2011
The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus Experiment journal June 2012
Overview of the physics and engineering design of NSTX upgrade journal July 2012
A simulation study of large power handling in the divertor for a Demo reactor journal November 2013
On the physics guidelines for a tokamak DEMO journal June 2013
Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas journal July 2013
Actively convected liquid metal divertor journal October 2014
Conference Report on the 3rd International Symposium on Lithium Application for Fusion Devices journal January 2015
Enhanced H-mode pedestals with lithium injection in DIII-D journal May 2015
Conference Report on the 4rd International Symposium on Lithium Applications journal September 2016
High frequency pacing of edge localized modes by injection of lithium granules in DIII-D H-mode discharges journal April 2016
Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices journal May 2006
Edge properties with the liquid lithium limiter in FTU—experiment and transport modelling journal June 2007
ELM elimination with Li powder injection in EAST discharges using the tungsten upper divertor journal January 2018
Collisional and thermal effects on liquid lithium sputtering journal November 2007
Edge-Localized-Mode Suppression through Density-Profile Modification with Lithium-Wall Coatings in the National Spherical Torus Experiment journal August 2009
Continuous Improvement of H-Mode Discharge Performance with Progressively Increasing Lithium Coatings in the National Spherical Torus Experiment journal September 2011
New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak journal February 2015
Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment journal July 2017
Magnetic Propulsion of Intense Lithium Streams in a Tokamak Magnetic Field journal January 2003
Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak journal August 2006
Latest Results From the Hybrid Illinois Device for Research and Applications (HIDRA) journal July 2018

Cited By (1)