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Title: The Effect of Progressively Increasing Lithium Coatings on Plasma Discharge Characteristics, Transport, Edge Profiles, and ELM Stability in the National Spherical Torus Experiment

Journal Article · · Nuclear Fusion
 [1];  [2];  [1];  [3];  [3];  [4];  [3];  [3];  [1];  [3];  [3];  [3];  [3];  [3];  [5];  [6];  [7];  [8]
  1. ORNL
  2. Princeton University
  3. Princeton Plasma Physics Laboratory (PPPL)
  4. Purdue University
  5. General Atomics
  6. University of Washington, Seattle
  7. Columbia University
  8. Lawrence Livermore National Laboratory (LLNL)

Lithium wall coatings have been shown to reduce recycling, suppress edge localized modes (ELMs), and improve energy confinement in the National Spherical Torus Experiment (NSTX). Here we document the effect of gradually increasing lithium wall coatings on the discharge characteristics, with the reference ELMy discharges obtained in boronized, i.e. non-lithiated, conditions. We observed a continuous but not quite monotonic reduction in recycling and improvement in energy confinement, a gradual alteration of edge plasma profiles, and slowly increasing periods of ELM quiescence. The measured edge plasma profiles during the lithium coating scan were simulated with the SOLPS code, which quantified the reduction in divertor recycling coefficient from ~98% to ~90%. The reduction in recycling and core fueling, coupled with a drop in the edge particle transport rate, reduced the average edge density profile gradient, and shifted it radially inward from the separatrix location. In contrast, the edge electron temperature (Te) profile was unaffected in the H-mode pedestal steep gradient region within the last 5% of normalized poloidal flux, N; however, the region of steep Te gradients extended radially inward from the top of the H-mode pedestal for 0.8< N <0.94 with lithium coatings. The peak pressure gradients were comparable during ELMy and ELM-free phases, but were shifted away from the separatrix in the ELM-free discharges, which is stabilizing to the current driven instabilities thought to be responsible for ELMs in NSTX.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
DOE Contract Number:
DE-AC05-00OR22725
OSTI ID:
1055015
Journal Information:
Nuclear Fusion, Vol. 52, Issue 8; ISSN 0029--5515
Country of Publication:
United States
Language:
English

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Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST journal November 2018
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Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment journal July 2017
Bootstrap Current for the Edge Pedestal Plasma in a Diverted Tokamak Geometry report August 2012