Central Solenoid for Spherical Tokamak Globus-M

Гусев, В. К.; Sakharov, N. V.; Шпейзман, В. В.; Korotkov, V. A.; Panin, A.; Soikin, V.F.; Kivivuori, Seppo; Helenius, Asko J.; Somerkoski, J.; Heikkinen, Jukka

doi:10.13182/fst98-a59

Cited by 10 publications

(3 citation statements)

References 3 publications

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“…V. Gusev and N. Sakharov (Ioffe Institute) reported on the status of Globus-M [18,19] (R/a = 1.5, R = 0.36 m, a = 0.24 m), which was completed in September 1998, and is scheduled to start operation in December 1998. 4 Nominal parameters are B T = 0.65 T, I p = 0.5 MA and τ pulse = 0.3 s with possible increase of plasma current and pulse duration up to the ultimate levels of 1 MA and 1 s for low repetition rate and limited time.…”

Section: Globus-mmentioning

confidence: 99%

Spherical Tori

Takase

Katsurai

1999

Nucl. Fusion

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Section: Globus-mmentioning

confidence: 99%

Spherical Tori

Takase

Katsurai

1999

Nucl. Fusion

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“…There were successful experiments in the PPPL stellarator-C as early as 1968; the first Kharkov torsatrons and the US mirror traps date from that same era. In small tokamaks such as TM-1-Vch (1974) [2], TO-2 [3] in RRC 'Kurchatov institute', T-11M [4] in SRC RF TRINITI and Globus-M [5] in the 'Ioffe Institute' good heating results at the fundamental cyclotron frequency of the majority ions have also been reported. Furthermore, successful fundamental ion cyclotron resonance heating (ICRH) experiments were carried out in the L-2 stellarator [6].…”

Section: Introductionmentioning

confidence: 99%

Fundamental ion cyclotron resonance heating of JET deuterium plasmas

Krasilnikov

Eester²,

Lerche³

et al. 2009

Plasma Phys. Control. Fusion

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Radio frequency heating of majority ions is of prime importance for understanding the basic role of auxiliary heating in the activated D-T phase of ITER. Majority Deuterium Ion-Cyclotron Resonance Heating (ICRH) experiments at the fundamental cyclotron frequency were performed in JET. In spite of the poor antenna coupling at the lowest possible commissioned RF frequency (25MHz), this heating scheme proved promising when adopted in combination with D Neutral Beam Injection (NBI). The experiments were performed in a ~90% D, 5% H plasma with some pulses including traces of Be and Ar. Up to 2MW of ICRH power was applied with dipole phasing in conjunction tõ 6MW of NBI power, either using 80keV "normal" beam or 130keV "tangential" beam injection. The toroidal magnetic field strength was typically B 0 = 3.3T, providing core ICRH of the bulk D ions. The effect of fundamental D ICRH was clearly demonstrated in these experiments: By adding 25% of heating power (P ICRH = 1.7MW / P NBI+OH = 7MW) the fusion power was increased up to 30-50%, depending on the type of NBI adopted. At this power level, the ion and electron temperatures increased from T i ~ 4.0keV and T e ~ 4.5keV (NBI-only phase) to T i ~ 5.5keV and T e ~ 5.2keV (ICRH+NBI phase), respectively. The increase in the neutron yield was stronger when 80keV rather than 130keV Deuterons were injected in the plasma. It is shown that the neutron rate, the diamagnetic energy and the electron as well as ion temperature scale roughly linearly with the applied RF power. A synergistic effect of the combined use of ICRF and NBI heating was observed: (i) The number of neutron counts measured by the neutron camera during the combined ICRF+NBI phases of the discharges exceeded the sum of the individual counts of the NBI-only and ICRF-only phases; (ii) A substantial increase in the number of slowing-down beam ions was detected by the TOFOR spectrometer when ICRF power was switched-on; (iii) A small D subpopulation with energies slightly above the NBI launch energy were detected by the neutral particle analyzer and gray spectroscopy.

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“…Ioffe Physico-Technical Institute in March 1999. The design description, operational principles and experimental programme are described in Refs [1,2]. The basic design characteristics are as follows: aspect ratio A = R/a = 1.5, major plasma radius R = 0.36 m, minor plasma radius a = 0.24 m, toroidal magnetic field at the vessel axis B T ≤ 0.62 T, plasma current I p ≤ 0.5 MA and pulse duration with inductive current drive τ pulse ≤ 0.3 s.…”

Section: Introductionmentioning

confidence: 99%

Plasma formation and first OH experiments in the Globus-M tokamak

et al. 2001

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The article reports the results of experimental campaigns on plasma ohmic heating performed during 1999-2000 on the spherical tokamak Globus-M. Later experimental results with the tokamak fed by thyristor rectifiers are presented in detail. The toroidal magnetic field and plasma pulse duration in these experiments were significantly increased. The method of stray magnetic field compensation is described. The technology of vacuum vessel conditioning, including boronization of the vessel performed at the end of the experiments, is briefly discussed. Specific features of neutral gas column breakdown in spherical tokamaks by applied inductive voltage are outlined. Also discussed is the influence of ECR preionization on the breakdown conditions. Experimental data on plasma column formation and current ramp-up in different regimes of operation with the magnetic flux of the central solenoid limited to ∼100 mWb are presented. A significant reduction of the background density after boronization (below 2 × 1018m-3) allows the density to be completely controlled with external gas puffing and makes the influence of the wall negligible. The magnetic flux consumption efficiency is discussed. The results of magnetic equilibrium simulations are presented and compared with experiment. Ramp-up of the plasma current of 0.25 MA for a time interval of about 0.03 s with about 0.02 s flat-top at a toroidal field strength of 0.35 T allows the conclusion that the target design parameters of Globus-M could be achieved in a double swing regime.

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Central Solenoid for Spherical Tokamak Globus-M

Cited by 10 publications

References 3 publications

Spherical Tori

Spherical Tori

Fundamental ion cyclotron resonance heating of JET deuterium plasmas

Plasma formation and first OH experiments in the Globus-M tokamak

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