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Title: Development of robust and multi-mode control of tearing in DIII-D

Neoclassical tearing modes (NTMs) are instabilities that can produce undesirable magnetic islands in tokamak plasmas. They can be stabilized by applying electron cyclotron current drive (ECCD) at the island. The NTM control system on DIII-D can now control multiple modes. Each of 6 mirrors that reflect ECCD beams into the plasma can be assigned to different surfaces in the plasma where NTMs are unstable. The control system then steers the mirrors to keep the beams aimed at the surfaces. The system routinely stabilizes one NTM preemptively and has now also been used to control two modes in the same discharge. With the “catch-and-subdue” function, ECCD-generating gyrotrons can be turned on when NTMs appear and off after suppression. Newly triggered NTMs can be promptly suppressed if mode onset is detected early and ECCD immediately applied. Early mode detection is achieved in this paper by spectral analysis of Mirnov probes with a band-pass filter for the expected mode frequency. Targeted surfaces are tracked by equilibrium reconstructions (that include measurements of the motional Stark effect). The ECCD position is tracked by ray-tracing using the TORBEAM code. Several techniques are being explored for fine-tuning alignment when NTMs occur. One method adjusts ECCD alignment inmore » steps until the island decays fast enough. A second method sweeps the alignment to find the optimum. A third method pulses gyrotrons and uses electron cyclotron emission to compare where the resulting temperature pulses are relative to temperature fluctuations from a rotating NTM. NTM control in ITER is expected to use active profile regulation to maximize controllability, followed by repeated catch-and-subdue actions if modes are retriggered, in order to maintain island size below the disruptive threshold while maximizing confinement and fusion gain. Between events, real-time tracking will be performed to maintain alignment and readiness for subsequent catch-andsubdue actions. Methods for active probing of stability boundaries will be studied as possible diagnostics for the profile regulation. Finally, selected elements of this ITER NTM control vision will be discussed and assessed.« less
 [1] ;  [1] ;  [1] ;  [2] ;  [3]
  1. General Atomics, San Diego, CA (United States)
  2. Princeton Univ., NJ (United States)
  3. Columbia Univ., New York, NY (United States)
Publication Date:
Grant/Contract Number:
FC02-04ER54698; AC02-09CH11466; SC0008520
Accepted Manuscript
Journal Name:
Fusion Engineering (SOFE), 2015 IEEE 26th Symposium
Additional Journal Information:
Journal Name: Fusion Engineering (SOFE), 2015 IEEE 26th Symposium; Conference: 26. Symposium on Fusion Engineering (SOFE), Austin, TX (United States), 31 May-4 Jun 2015
Research Org:
General Atomics, San Diego, CA (United States); Princeton Univ., NJ (United States); Columbia Univ., New York, NY (United States)
Sponsoring Org:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Gyrotrons; Mirrors; Plasmas; Control systems; Real-time systems; Particle beams; Tracking; NTM; Tokamak; Plasma control
OSTI Identifier: