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Controlling marginally detached divertor plasmas

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [4];  [5];  [5];  [6];  [7];  [7];  [5];  [8]
  1. General Atomics, San Diego, CA (United States); Princeton Univ., Princeton, NJ (United States); General Atomics
  2. Princeton Univ., Princeton, NJ (United States)
  3. Sandia National Lab. (SNL-CA), Livermore, CA (United States)
  4. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  5. General Atomics, San Diego, CA (United States)
  6. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  7. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  8. Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
A new control system at DIII-D has stabilized the inter-ELM detached divertor plasma state for H-mode in close proximity to the threshold for reattachment, thus demonstrating the ability to maintain detachment with minimal gas puffing. When the same control system was instead ordered to hold the plasma at the threshold (here defined as Te = 5 eV near the divertor target plate), the resulting Te profiles separated into two groups with one group consistent with marginal detachment, and the other with marginal attachment. The plasma dithers between the attached and detached states when the control system attempts to hold at the threshold. The control system is upgraded from the one described in and it handles ELMing plasmas by using real time Dα measurements to remove during-ELM slices from real time Te measurements derived from divertor Thomson scattering. The difference between measured and requested inter-ELM Te is passed to a PID (proportionalintegral-derivative) controller to determine gas puff commands. While some degree of detachment is essential for the health of ITER’s divertor, more deeply detached plasmas have greater radiative losses and, at the extreme, confinement degradation, making it desirable to limit detachment to the minimum level needed to protect the target plate. However, the observed bifurcation in plasma conditions at the outer strike point with the ion B × $$\nabla $$ B drift into the divertor makes this a significant challenge. If the divertor plasma were to reattach between ELMs, there would be a long (depending on delays in the gas puff system) window of high heat flux before detachment could be re-established. Thus, good understanding of detachment behavior near the threshold for re-attachment is required to properly tune an active control system to maintain ideal divertor performance without reattaching. Furthermore, the top-of-pedestal electron densities during dithering across the bifurcation and during stable marginally detached operation are the same within uncertainty, showing the need for local real-time measurements of the divertor conditions.
Research Organization:
General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
FC02-04ER54698
OSTI ID:
1374843
Alternate ID(s):
OSTI ID: 1888118
OSTI ID: 22738457
OSTI ID: 22925733
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 6 Vol. 57; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (4)

A scalable real-time framework for Thomson scattering analysis: Application to NSTX-U journal April 2019
MANTIS: A real-time quantitative multispectral imaging system for fusion plasmas journal December 2019
OMFIT Tokamak Profile Data Fitting and Physics Analysis journal January 2018
Plasma detachment in divertor tokamaks journal February 2018

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