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Title: Avoidance of impurity-induced current quench using lower hybrid current drive

Abstract

This work reports observations of a tokamak plasma that experienced a thermal quench due to a large, transient high-Z influx but avoided a current quench. This is argued to be caused by the presence of lower hybrid range of frequency (LHRF) waves that sustain a non-thermal, current-carrying electron population. In Alcator C-Mod L-mode plasmas at Ip = 450 kA, e = 0.5 x 1020 m–3, nearly all of the current can be sustained non-inductively by injecting ≃700 kW of LHRF power at 4.6 GHz and n = 1.9. A sudden influx of a large amount of tungsten, nz/ne ≃ 0.0044, triggers a cooling wave that propagates at 2–3 m s–1 all the way into the core, dropping on-axis T e from 3 keV to temperatures less than measurement floor of 50 eV. An off-axis reheat begins after 100 ms, but T e profiles remain hollow for 300–350 ms after the injection. Throughout this temperature evolution, the plasma density, current and shape remain unchanged to within 10%. Following the expulsion of the tungsten, the plasma returns to its baseline conditions and the plasma ends as planned with a controlled current ramp-down. Energy balance analysis shows the LHRF power continues to bemore » absorbed in the plasma after the thermal quench, as a significant fraction of it is needed to be consistent with radiated power measurements. Examination of current relaxation time, τR, and fast-electron slowing down time, τs, indicate the LHRF must contribute to driving current, despite the low temperatures, as the current remains nominally stationary despite τR < 5 ms and τs < 50 ms for relativistic electrons. Furthermore, these measurements represent an important existence proof of a possible technique for avoidance of disruptions caused by sudden, unplanned influx of impurities in the form of dust or flakes of high-Z wall material. Implications and suggestions for future experimental and modeling and simulation work are summarized.« less

Authors:
ORCiD logo [1];  [2];  [3]; ORCiD logo [3];  [3];  [3]; ORCiD logo [3];  [3]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. MIT Plasma Science and Fusion Center, Cambridge, MA (United States)
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Contributing Org.:
The Alcator C-Mod Team
OSTI Identifier:
1558802
Grant/Contract Number:  
AC02-09CH11466; FG02-98ER54462
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 59; Journal Issue: 6; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; tokamak; disruption; impurity; lower hybrid; runaway electron

Citation Formats

Reinke, M. L., Scott, S., Granetz, R., Hughes, J. W., Baek, S. G., Shiraiwa, S., Tinguely, R. A., and Wukitch, S. Avoidance of impurity-induced current quench using lower hybrid current drive. United States: N. p., 2019. Web. doi:10.1088/1741-4326/ab0eb2.
Reinke, M. L., Scott, S., Granetz, R., Hughes, J. W., Baek, S. G., Shiraiwa, S., Tinguely, R. A., & Wukitch, S. Avoidance of impurity-induced current quench using lower hybrid current drive. United States. https://doi.org/10.1088/1741-4326/ab0eb2
Reinke, M. L., Scott, S., Granetz, R., Hughes, J. W., Baek, S. G., Shiraiwa, S., Tinguely, R. A., and Wukitch, S. Thu . "Avoidance of impurity-induced current quench using lower hybrid current drive". United States. https://doi.org/10.1088/1741-4326/ab0eb2. https://www.osti.gov/servlets/purl/1558802.
@article{osti_1558802,
title = {Avoidance of impurity-induced current quench using lower hybrid current drive},
author = {Reinke, M. L. and Scott, S. and Granetz, R. and Hughes, J. W. and Baek, S. G. and Shiraiwa, S. and Tinguely, R. A. and Wukitch, S.},
abstractNote = {This work reports observations of a tokamak plasma that experienced a thermal quench due to a large, transient high-Z influx but avoided a current quench. This is argued to be caused by the presence of lower hybrid range of frequency (LHRF) waves that sustain a non-thermal, current-carrying electron population. In Alcator C-Mod L-mode plasmas at Ip = 450 kA, n¯e = 0.5 x 1020 m–3, nearly all of the current can be sustained non-inductively by injecting ≃700 kW of LHRF power at 4.6 GHz and n∥ = 1.9. A sudden influx of a large amount of tungsten, nz/ne ≃ 0.0044, triggers a cooling wave that propagates at 2–3 m s–1 all the way into the core, dropping on-axis T e from 3 keV to temperatures less than measurement floor of 50 eV. An off-axis reheat begins after 100 ms, but T e profiles remain hollow for 300–350 ms after the injection. Throughout this temperature evolution, the plasma density, current and shape remain unchanged to within 10%. Following the expulsion of the tungsten, the plasma returns to its baseline conditions and the plasma ends as planned with a controlled current ramp-down. Energy balance analysis shows the LHRF power continues to be absorbed in the plasma after the thermal quench, as a significant fraction of it is needed to be consistent with radiated power measurements. Examination of current relaxation time, τR, and fast-electron slowing down time, τs, indicate the LHRF must contribute to driving current, despite the low temperatures, as the current remains nominally stationary despite τR < 5 ms and τs < 50 ms for relativistic electrons. Furthermore, these measurements represent an important existence proof of a possible technique for avoidance of disruptions caused by sudden, unplanned influx of impurities in the form of dust or flakes of high-Z wall material. Implications and suggestions for future experimental and modeling and simulation work are summarized.},
doi = {10.1088/1741-4326/ab0eb2},
journal = {Nuclear Fusion},
number = 6,
volume = 59,
place = {United States},
year = {Thu Apr 25 00:00:00 EDT 2019},
month = {Thu Apr 25 00:00:00 EDT 2019}
}

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Cited by: 4 works
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Figures / Tables:

Figure 1 Figure 1: Example of a typical disruption caused by an unplanned high-Z influx in an inductively driven plasma. PRAD$\gg$ PIN leads to a cooling wave propagating in to mid-radius, triggering the MHD instability responsible for the fast thermal-quench which transitions to the subsequent current quench.

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