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U.S. Department of Energy
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Plasma confinement improvement by RHF in IR-T1 Tokamak

Conference ·
OSTI ID:423063
; ; ; ;  [1]
  1. I.A.U., Tehran (Iran, Islamic Republic of). Plasma Physics Research Center

It has been known that the tokamak plasma parameters and the energy confinement time may be reduced by plasma impurity radiation. The plasma MHD stabilities may also be influenced by the impurities. Experiments have been performed on the IR-T1 Tokamak to investigate the influence of magnetic perturbations and impurities radiation on confinement. The perturbations are either imposed, via external windings, or natural plasma fluctuations. For this purpose, L = 2 and L = 3 helical windings have been installed on the IR-T1 Tokamak. Diagnostic signals from MHD instabilities have been obtained and studied during discharges with resonant helical fields (RHFs). Both the L = 2 and L = 3 RHFs can suppress the corresponding 2/1 and 3/1 MHD modes and can simultaneously suppress all other modes, RHFs could increase the amplitude, ramp-up and collapse slopes of Sawtooth oscillation. Generally, the stability properties of the discharge are improved by RHFs and also by the suppression of modes signals at SXR diodes.

OSTI ID:
423063
Report Number(s):
CONF-960634--
Country of Publication:
United States
Language:
English

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