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Title: An overview of recent physics results from NSTX

Journal Article · · Nuclear Fusion
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  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Univ. of Illinois, Urbana-Champaign, IL (United States)
  4. Univ. of California, Davis, CA (United States)
  5. Columbia Univ., New York, NY (United States)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  7. IPP, Garching (Germany)
  8. Univ. of California, San Diego, CA (United States)
  9. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  10. Univ. of Tennessee, Knoxville, TN (United States)
  11. Princeton Univ., NJ (United States)
  12. Purdue Univ., West Lafayette, IN (United States)
  13. General Atomics, San Diego, CA (United States)
  14. Univ. of California, Los Angeles, CA (United States)
  15. Lodestar Research Corp., Boulder, CO (United States)
  16. Johns Hopkins Univ., Baltimore, MD (United States)
  17. University of Wisconsin, Madison, WI (United States)
  18. Univ. of Washington, Seattle, WA (United States)
  19. Princeton University, NJ (United States)
  20. CompX, Del Mar, CA (United States)
  21. Univ. of California, Irvine, CA (United States)
  22. National Inst. for Fusion Science, Toki (Japan)
  23. XCEL, Oak Ridge, TN (United States)
  24. University of Washington, Seattle, WA (United States)
  25. University of California, Los Angeles, CA (United States)
  26. Nova Photonics, Princeton, NJ (United States)
  27. University of California, Irvine, CA (United States)
  28. University of Illinois, Urbana-Champaign, IL (United States)
  29. University of Colorado, Boulder, CO (United States)
  30. University of California, Davis, CA (United States)
  31. Columbia University, New York, NY (United States)
  32. Lehigh University, Bethlehem, PA (United States)
  33. Purdue University, West Lafayette, IN (United States)
  34. Johns Hopkins University, Baltimore, MD (United States)
  35. University of Tennessee, Knoxville, TN (United States)

Currently, the National Spherical Torus Experiment (NSTX) is being upgraded to operate at twice the toroidal field and plasma current (up to 1 T and 2 MA), with a second, more tangentially aimed neutral beam (NB) for current and rotation control, allowing for pulse lengths up to 5 s. Recent NSTX physics analyses have addressed topics that will allow NSTX-Upgrade to achieve the research goals critical to a Fusion Nuclear Science Facility. These include producing stable, 100% non-inductive operation in high-performance plasmas, assessing plasma-material interface (PMI) solutions to handle the high heat loads expected in the next-step devices and exploring the unique spherical torus (ST) parameter regimes to advance predictive capability. Non-inductive operation and current profile control in NSTX-U will be facilitated by co-axial helicity injection (CHI) as well as radio frequency (RF) and NB heating. CHI studies using NIMROD indicate that the reconnection process is consistent with the 2D Sweet-Parker theory. Full-wave AORSA simulations show that RF power losses in the scrape-off layer (SOL) increase significantly for both NSTX and NSTX-U when the launched waves propagate in the SOL. Moreover, Toroidal Alfven eigenmode avalanches and higher frequency Alfven eigenmodes can affect NB-driven current through energy loss and redistribution of fast ions. The inclusion of rotation and kinetic resonances, which depend on collisionality, is necessary for predicting experimental stability thresholds of fast growing ideal wall and resistive wall modes. Neutral beams and neoclassical toroidal viscosity generated from applied 3D fields can be used as actuators to produce rotation profiles optimized for global stability. DEGAS-2 has been used to study the dependence of gas penetration on SOL temperatures and densities for the MGI system being implemented on the Upgrade for disruption mitigation. PMI studies have focused on the effect of ELMs and 3D fields on plasma detachment and heat flux handling. Simulations indicate that snowflake and impurity seeded radiative divertors are candidates for heat flux mitigation in NSTX-U. Studies of lithium evaporation on graphite surfaces indicate that lithium increases oxygen surface concentrations on graphite, and deuterium-oxygen affinity, which increases deuterium pumping and reduces recycling. In situ and test-stand experiments of lithiated graphite and molybdenum indicate temperature-enhanced sputtering, although that test-stand studies also show the potential for heat flux reduction through lithium vapour shielding. Non-linear gyro kinetic simulations have indicated that ion transport can be enhanced by a shear-flow instability, and that non-local effects are necessary to explain the observed rapid changes in plasma turbulence. Predictive simulations have shown agreement between a microtearing-based reduced transport model and the measured electron temperatures in a microtearing unstable regime. Finally, two Alfven eigenmode-driven fast ion transport models have been developed and successfully benchmarked against NSTX data. Upgrade construction is moving on schedule with initial physics research operation of NSTX-U planned for mid-2015.

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:
AC52-07NA27344; AC02-09CH11466
OSTI ID:
1888620
Alternate ID(s):
OSTI ID: 1256734
Report Number(s):
LLNL-JRNL-840084; PPPL-5092; 1061331; TRN: US2309907
Journal Information:
Nuclear Fusion, Vol. 55, Issue 10; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 22 works
Citation information provided by
Web of Science

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Geometrical properties of a “snowflake” divertor journal June 2007
Fast-ion energy loss during TAE avalanches in the National Spherical Torus Experiment journal December 2012
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A reduced fast ion transport model for the tokamak transport code TRANSP journal April 2014
Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET journal July 2013
Measured improvement of global magnetohydrodynamic mode stability at high-beta, and in reduced collisionality spherical torus plasmas journal May 2014
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Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation journal November 2010
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Magnetic reconnection process in transient coaxial helicity injection journal September 2013
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  • Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, Vol. 30, Issue 4 https://doi.org/10.1116/1.4731196
journal July 2012
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Self-consistent equilibrium model of low aspect-ratio toroidal plasma with energetic beam ions journal August 2003
Overview of physics results from the conclusive operation of the National Spherical Torus Experiment journal September 2013
Resistive Wall Mode in Collisionless Quasistationary Plasmas journal September 2004
The effect of the fast-ion profile on Alfvén eigenmode stability journal August 2013
Non-inductive plasma start-up on NSTX and projections to NSTX-U using transient CHI journal June 2013
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Fast-wave power flow along SOL field lines in NSTX and the associated power deposition profile across the SOL in front of the antenna journal July 2013
Type-I ELM power deposition profile width and temporal shape in JET journal August 2011
The relationships between edge localized modes suppression, pedestal profiles and lithium wall coatings in NSTX journal September 2011
High density Langmuir probe array for NSTX scrape-off layer measurements under lithiated divertor conditions journal October 2010
Overview of the physics and engineering design of NSTX upgrade journal July 2012
Electron cyclotron current drive efficiency in general tokamak geometry journal October 2003
Edge-plasma models and characteristics for magnetic fusion energy devices journal July 2002
Simulation of non-resonant internal kink mode with toroidal rotation in the National Spherical Torus Experiment journal July 2013
1.5D quasilinear model and its application on beams interacting with Alfvén eigenmodes in DIII-D journal September 2012
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Cited By (8)

Effect of wall boundary on the scrape-off layer losses of high harmonic fast wave in NSTX and NSTX-U journal June 2019
Feedback control design for non-inductively sustained scenarios in NSTX-U using TRANSP journal April 2017
Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U journal January 2018
Recent progress in understanding electron thermal transport in NSTX journal March 2017
Real-time capable modeling of neutral beam injection on NSTX-U using neural networks journal March 2019
Effects of the applied magnetic fields with various toroidal phase differences on the neoclassical toroidal viscosity in JT-60SA journal October 2018
Observation of quasi-coherent edge fluctuations in Ohmic plasmas on National Spherical Torus Experiment journal April 2016
Unraveling the surface chemistry processes in lithiated and boronized plasma material interfaces under extreme conditions journal July 2018

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