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Title: CONTROL OF NEOCLASSICAL TEARING MODES IN DIII-D

Abstract

The development of techniques for neoclassical tearing mode (NTM) suppression or avoidance is crucial for successful high beta/high confinement tokamaks. Neoclassical tearing modes are islands destabilized and maintained by a helically perturbed bootstrap current and represent a significant limit to performance at higher poloidal beta. The confinement-degrading islands can be reduced or completely suppressed by precisely replacing the ''missing'' bootstrap current in the island O-point or by interfering with the fundamental helical harmonic of the pressure. Implementation of such techniques is being studied in the DIII-D tokamak [J.L. Luxon, et al., Plasma Phys. and Control. Fusion Research, Vol. 1 (International Atomic Energy Agency, Vienna, 1987) p. 159] in the presence of periodic q = 1 sawtooth instabilities, a reactor relevant regime. Radially localized off-axis electron cyclotron current drive (ECCD) must be precisely located on the island. In DIII-D the plasma control system is put into a ''search and suppress'' mode to make either small rigid radial position shifts of the entire plasma (and thus the island) or small changes in toroidal field (and thus, ECCD location) to find and lock onto the optimum position for complete island suppression by ECCD. This is based on real-time measurements of an m/n =more » 3/2 mode amplitude dB{sub {theta}}/dt. The experiment represents the first use of active feedback control to provide continuous, precise positioning. An alternative to ECCD makes use of the six toroidal section ''C-Coil'' on DIII-D to provide a large non-resonant static m = 1, n = 3 helical field to interfere with the fundamental harmonic of an m/n = 3/2 NTM. While experiments show success in inhibiting the NTM if a large enough n = 3 field is applied before the island onset, there is a considerable plasma rotation decrease due to n = 3 ''ripple''.« less

Authors:
; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
GENERAL ATOMICS (US)
Sponsoring Org.:
(US)
OSTI Identifier:
805255
DOE Contract Number:  
AC03-99ER54463
Resource Type:
Conference
Resource Relation:
Conference: 43rd Annual Meeting of the Division of Plasma Physics, Long Beach, CA (US), 10/29/2001--11/02/2001; Other Information: This is a preprint of an invited paper to be presented at the 43rd Annual Meeting of the Division of Plasma Physics in Long Beach, California, October 29 through November 2, 2001 and to be published in Phys. Plasma.; PBD: 1 Nov 2001
Country of Publication:
United States
Language:
English
Subject:
29 ENERGY PLANNING, POLICY AND ECONOMY; 43 PARTICLE ACCELERATORS; AMPLITUDES; AVOIDANCE; BOOTSTRAP CURRENT; CONFINEMENT; CONTROL SYSTEMS; CYCLOTRONS; DOUBLET-3 DEVICE; ELECTRONS; FEEDBACK; HARMONICS; IMPLEMENTATION; NUCLEAR ENERGY; POSITIONING; ROTATION

Citation Formats

LA HAYE, R J, GUNTER, S, HUMPHREYS, D A, LOHR, J, LUCE, T C, MARASCHEK, M E, PETTY, C C, PRATER, R, SCOVILLE, J T, and STRAIT, E J. CONTROL OF NEOCLASSICAL TEARING MODES IN DIII-D. United States: N. p., 2001. Web.
LA HAYE, R J, GUNTER, S, HUMPHREYS, D A, LOHR, J, LUCE, T C, MARASCHEK, M E, PETTY, C C, PRATER, R, SCOVILLE, J T, & STRAIT, E J. CONTROL OF NEOCLASSICAL TEARING MODES IN DIII-D. United States.
LA HAYE, R J, GUNTER, S, HUMPHREYS, D A, LOHR, J, LUCE, T C, MARASCHEK, M E, PETTY, C C, PRATER, R, SCOVILLE, J T, and STRAIT, E J. Thu . "CONTROL OF NEOCLASSICAL TEARING MODES IN DIII-D". United States. https://www.osti.gov/servlets/purl/805255.
@article{osti_805255,
title = {CONTROL OF NEOCLASSICAL TEARING MODES IN DIII-D},
author = {LA HAYE, R J and GUNTER, S and HUMPHREYS, D A and LOHR, J and LUCE, T C and MARASCHEK, M E and PETTY, C C and PRATER, R and SCOVILLE, J T and STRAIT, E J},
abstractNote = {The development of techniques for neoclassical tearing mode (NTM) suppression or avoidance is crucial for successful high beta/high confinement tokamaks. Neoclassical tearing modes are islands destabilized and maintained by a helically perturbed bootstrap current and represent a significant limit to performance at higher poloidal beta. The confinement-degrading islands can be reduced or completely suppressed by precisely replacing the ''missing'' bootstrap current in the island O-point or by interfering with the fundamental helical harmonic of the pressure. Implementation of such techniques is being studied in the DIII-D tokamak [J.L. Luxon, et al., Plasma Phys. and Control. Fusion Research, Vol. 1 (International Atomic Energy Agency, Vienna, 1987) p. 159] in the presence of periodic q = 1 sawtooth instabilities, a reactor relevant regime. Radially localized off-axis electron cyclotron current drive (ECCD) must be precisely located on the island. In DIII-D the plasma control system is put into a ''search and suppress'' mode to make either small rigid radial position shifts of the entire plasma (and thus the island) or small changes in toroidal field (and thus, ECCD location) to find and lock onto the optimum position for complete island suppression by ECCD. This is based on real-time measurements of an m/n = 3/2 mode amplitude dB{sub {theta}}/dt. The experiment represents the first use of active feedback control to provide continuous, precise positioning. An alternative to ECCD makes use of the six toroidal section ''C-Coil'' on DIII-D to provide a large non-resonant static m = 1, n = 3 helical field to interfere with the fundamental harmonic of an m/n = 3/2 NTM. While experiments show success in inhibiting the NTM if a large enough n = 3 field is applied before the island onset, there is a considerable plasma rotation decrease due to n = 3 ''ripple''.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2001},
month = {11}
}

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