skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Dependence of recycling and edge profiles on lithium evaporation in high triangularity, high performance NSTX H-mode discharges

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [1];  [1];  [1];  [3];  [1];  [1];  [1];  [1];  [1];  [4];  [1];  [5]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Columbia Univ., New York, NY (United States). Applied Physics and Applied Math Dept.
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

In this paper, the effects of a pre-discharge lithium evaporation variation on highly shaped discharges in the National Spherical Torus Experiment (NSTX) are documented. Lithium wall conditioning ('dose') was routinely applied onto graphite plasma facing components between discharges in NSTX, partly to reduce recycling. Reduced D-alpha, emission from the lower and upper divertor and center stack was observed, as well as reduced midplane neutral pressure; the magnitude of reduction increased with the pre-discharge lithium dose. Improved energy confinement, both raw tau(E) and H-factor normalized to scalings, with increasing lithium dose was also observed. At the highest doses, we also observed elimination of edge-localized modes. The midplane edge plasma profiles were dramatically altered, comparable to lithium dose scans at lower shaping, where the strike point was farther from the lithium deposition centroid. This indicates that the benefits of lithium conditioning should apply to the highly shaped plasmas planned in NSTX-U. (C) 2014 Elsevier B.V. All rights reserved.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Lawrence Livermore National Lab., Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC05-00OR22725; AC02-09CH11466; FC02-04ER54698; FC02-99ER54512; AC52-07NA27344
OSTI ID:
1341539
Alternate ID(s):
OSTI ID: 1260716; OSTI ID: 1281680
Report Number(s):
LLNL-JRNL-696263; AT1030100; ERAT021
Journal Information:
Journal of Nuclear Materials, Vol. 463, Issue C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 17 works
Citation information provided by
Web of Science

References (24)

Observations concerning the injection of a lithium aerosol into the edge of TFTR discharges journal December 2001
Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak journal August 2006
First experiments with lithium limiter on FTU journal June 2007
Impact of lithium-coated walls on plasma performance in the TJ-II stellarator journal June 2009
Approaches towards long-pulse divertor operations on EAST by active control of plasma–wall interactions journal November 2013
Edge transport and turbulence reduction with lithium coated plasma facing components in the National Spherical Torus Experiment journal May 2011
The relationships between edge localized modes suppression, pedestal profiles and lithium wall coatings in NSTX journal September 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
Effect of plasma shaping on performance in the National Spherical Torus Experiment journal May 2006
Overview of the physics and engineering design of NSTX upgrade journal July 2012
Exploration of the equilibrium operating space for NSTX-Upgrade journal August 2012
Evaporated lithium surface coatings in NSTX journal June 2009
The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment journal May 2008
Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment journal November 2009
Characteristics of energy transport of Li-conditioned and non-Li-conditioned plasmas in the National Spherical Torus Experiment (NSTX) journal November 2009
The dependence of H-mode energy confinement and transport on collisionality in NSTX journal April 2013
Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces journal June 2009
Multi-Fluid Modeling of Low-Recycling Divertor Regimes journal May 2010
Measurements and 2-D modeling of recycling and edge transport in discharges with lithium-coated PFCs in NSTX journal August 2011
Varying the pre-discharge lithium wall coatings to alter the characteristics of the ELM-free H-mode pedestal in NSTX journal July 2013
Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performance journal December 2013
ITER L mode confinement database journal September 1997
Scaling studies of the high mode pedestal journal May 1998
Edge microstability of NSTX plasmas without and with lithium-coated plasma-facing components journal September 2013

Cited By (3)