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A new developed in-between shots lithium evaporation coating system for improving plasma performance in EAST

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [3];  [3];  [4];  [5];  [3]
  1. Chinese Academy of Sciences, Hefei (China); Univ. of Science and Technology of China, Hefei (China)
  2. Chinese Academy of Sciences, Hefei (China); CAS Key Lab of Photovoltaic and Energy Conservation Materials, Hefei (China)
  3. Chinese Academy of Sciences, Hefei (China)
  4. Princeton Univ., Princeton, NJ (United States)
  5. Hunan Univ., Changsha (China)

A new in-between shots evaporative lithium coating system has been successfully developed and implemented on the Experimental Advanced Superconducting Tokamak (EAST) for the 2017 campaign. This paper describes a novel technique for the introduction of lithium into the EAST vessel allowing evaporative coatings to be applied between discharges without requiring a significant amount of time to insert and retract the lithium source. This newly designed system utilizes a rotating axis driven by a vacuum dynamic sealing feedthough under remote control to open and close a shutter. A compression bellows, which drives the delivery tube, guarantees accurate position of the oven thus avoiding possible direct contact with the plasma. This allows the new evaporation system to be operated in two distinct modes. One mode is operated in-between shots to refresh pre-coated lithium film, the other is a real-time lithium vapor injection during plasma operations to provide active wall conditioning during long pulse plasma discharges. In this paper, operation of this new lithium deposition system in the in-between shots replenishment mode is described. Initial experiments show that this system worked well during the interval of discharges in EAST, and the in-between shots lithium coating effectively reduced the wall recycling and impurity concentrations. Furthermore, the application of fresh lithium coating lead to sustain the plasma stored energy and confinement, as well as a reduction of impurity radiation.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
OSTI ID:
1461184
Alternate ID(s):
OSTI ID: 22850476
Journal Information:
Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: C Vol. 133; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (18)

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Experimental studies of lithium-based surface chemistry for fusion plasma-facing materials applications journal June 2009
Lithium coating for H-mode and high performance plasmas on EAST in ASIPP journal July 2013
Dependence of recycling and edge profiles on lithium evaporation in high triangularity, high performance NSTX H-mode discharges journal August 2015
Enhanced performance of deuterium–tritium‐fueled supershots using extensive lithium conditioning in the Tokamak Fusion Test Reactor journal November 1995
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Approaches towards long-pulse divertor operations on EAST by active control of plasma–wall interactions journal November 2013
First results of the use of a continuously flowing lithium limiter in high performance discharges in the EAST device journal March 2016
Effort of lower hybrid current drive experiments toward to H-mode in EAST journal November 2016
Wall conditioning in fusion devices and its influence on plasma performance journal September 1996
Primary Results of Lithium Coating for the Improvement of Plasma Performance in EAST journal December 2010
Mitigation of plasma–material interactions via passive Li efflux from the surface of a flowing liquid lithium limiter in EAST journal March 2017
New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak journal February 2015

Cited By (1)

Effects of lithium coating of the chamber wall on the STOR-M tokamak discharges journal June 2019

Figures / Tables (8)


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