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Title: Overview of NSTX Upgrade initial results and modelling highlights

Journal Article · · Nuclear Fusion
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  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Univ. of Illinois, Urbana-Champaign, IL (United States)
  3. Columbia Univ., New York, NY (United States)
  4. Univ. of California, Los Angeles, CA (United States)
  5. Univ. of Wisconsin, Madison, WI (United States)
  6. Univ. of California, Irvine, CA (United States)
  7. Univ. of Washington, Seattle, WA (United States)
  8. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  9. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  10. Nova Photonics, Princeton, NJ (United States)
  11. Univ. of California, Davis, CA (United States)
  12. Princeton Univ., NJ (United States)
  13. General Atomics, San Diego, CA (United States)
  14. The College of New Jersey, Ewing, NJ (United States)
  15. Johns Hopkins Univ., Baltimore, MD (United States)
  16. Univ. of Tennessee, Knoxville, TN (United States)
  17. X Science LLC, Plainsboro, NJ (United States)
  18. College of William and Mary, Williamsburg, VA (United States)
  19. Lodestar Research Corporation, Boulder, CO (United States)
  20. Univ. of Michigan, Ann Arbor, MI (United States)
  21. Lehigh Univ., Bethlehem, PA (United States)

The National Spherical Torus Experiment (NSTX) has undergone a major upgrade, and the NSTX Upgrade (NSTX-U) Project was completed in the summer of 2015. NSTX-U first plasma was subsequently achieved, diagnostic and control systems have been commissioned, the H-mode accessed, magnetic error fields identified and mitigated, and the first physics research campaign carried out. During ten run weeks of operation, NSTX-U surpassed NSTX record pulse-durations and toroidal fields (TF), and high-performance ~1 MA H-mode plasmas comparable to the best of NSTX have been sustained near and slightly above the n = 1 no-wall stability limit and with H-mode confinement multiplier H98y,2 above 1. Transport and turbulence studies in L-mode plasmas have identified the coexistence of at least two ion-gyro-scale turbulent micro-instabilities near the same radial location but propagating in opposite (i.e. ion and electron diamagnetic) directions. These modes have the characteristics of ion-temperature gradient and micro-tearing modes, respectively, and the role of these modes in contributing to thermal transport is under active investigation. The new second more tangential neutral beam injection was observed to significantly modify the stability of two types of Alfven eigenmodes. Improvements in offline disruption forecasting were made in the areas of identification of rotating MHD modes and other macroscopic instabilities using the disruption event characterization and forecasting code. Finally, the materials analysis and particle probe was utilized on NSTX-U for the first time and enabled assessments of the correlation between boronized wall conditions and plasma performance. These and other highlights from the first run campaign of NSTX-U are described.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-09CH11466; AC52-07NA27344
OSTI ID:
1367916
Alternate ID(s):
OSTI ID: 1888627
Report Number(s):
LLNL-JRNL-840085
Journal Information:
Nuclear Fusion, Vol. 57, Issue 10; Related Information: Please use this identifier to cite or link to this item: http://arks.princeton.edu/ark:/88435/dsp016w924f316; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 45 works
Citation information provided by
Web of Science

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Cited By (14)

Overview of new MAST physics in anticipation of first results from MAST Upgrade journal June 2019
Effect of wall boundary on the scrape-off layer losses of high harmonic fast wave in NSTX and NSTX-U journal June 2019
Design and simulation of the snowflake divertor control for NSTX–U journal January 2019
Effect of deuterium irradiation on graphite boronized in the NSTX-U tokamak journal February 2019
Orbit modeling of fast particle redistribution induced by sawtooth instability journal July 2018
Divertor leg filaments in NSTX-U journal October 2018
Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U journal January 2018
Error field impact on mode locking and divertor heat flux in NSTX-U journal June 2019
Real-time capable modeling of neutral beam injection on NSTX-U using neural networks journal March 2019
Compact steady-state tokamak performance dependence on magnet and core physics limits journal February 2019
NSTX/NSTX-U theory, modeling and analysis results journal June 2019
Effect of sawtooth crashes on fast ion distribution in NSTX-U journal July 2018
Initial transport and turbulence analysis and gyrokinetic simulation validation in NSTX-U L-mode plasmas journal April 2019
UKAEA capabilities to address the challenges on the path to delivering fusion power
  • Chapman, I. T.; Morris, A. W.
  • Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141 https://doi.org/10.1098/rsta.2017.0436
journal February 2019

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