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Effect of progressively increasing lithium conditioning on edge transport and stability in high triangularity NSTX H-modes

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [1];  [3];  [1];  [1];  [1];  [1];  [4];  [5];  [5]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Princeton Univ., NJ (United States)
  4. Columbia Univ., New York, NY (United States)
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
A sequence of H-mode discharges with increasing levels of pre-discharge lithium evaporation (‘dose’) was conducted in high triangularity and elongation boundary shape in NSTX. Energy confinement increased, and recycling decreased with increasing lithium dose, similar to a previous lithium dose scan in medium triangularity and elongation plasmas. Data-constrained SOLPS interpretive modeling quantified the edge transport change: the electron particle diffusivity decreased by 10-30x. The electron thermal diffusivity decreased by 4x just inside the top of the pedestal, but increased by up to 5x very near the separatrix. These results provide a baseline expectation for lithium benefits in NSTX-U, which is optimized for a boundary shape similar to the one in this experiment.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; AC52-07NA27344; FC02-04ER54698; FC02-99ER54512
OSTI ID:
1358036
Alternate ID(s):
OSTI ID: 1771440
OSTI ID: 22626655
Report Number(s):
LLNL-JRNL-820480; PPPL--5278; PII: S0920379616304550
Journal Information:
Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 117; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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