ITER R&amp;D: Auxiliary Systems: Neutral Beam Heating and Current Drive System

Inoue, Takashi; Hemsworth, R.; Kulygin, V. M.; Okumura, Y.

doi:10.1016/s0920-3796(01)00202-2

Cited by 26 publications

(12 citation statements)

References 9 publications

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“…Figure 5͑b͒ shows the operational gas pressure as a function of the volume to surface ratio of the plasma. 14 Here, the volume means the plasma volume and the surface means the plasma loss area, i.e., the total line cusp area. It is found that lower gas pressure operation is realized in a source with a higher volume to surface ratio.…”

Section: Large-volume Plasma Productionmentioning

confidence: 99%

Negative ion source development for fusion application (invited)

Takeiri

2010

Review of Scientific Instruments

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Giant negative ion sources, producing high-current of several tens amps with high energy of several hundreds keV to 1 MeV, are required for a neutral beam injector ͑NBI͒ in a fusion device. The giant negative ion sources are cesium-seeded plasma sources, in which the negative ions are produced on the cesium-covered surface. Their characteristic features are discussed with the views of large-volume plasma production, large-area beam acceleration, and high-voltage dc holding. The international thermonuclear experimental reactor NBI employs a 1 MeV-40 A of deuterium negative ion source, and intensive development programs for the rf-driven source plasma production and the multistage electrostatic acceleration are in progress, including the long pulse operation for 3600 s. Present status of the development, as well as the achievements of the giant negative ion sources in the working injectors, is also summarized.

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Section: Large-volume Plasma Productionmentioning

confidence: 99%

Negative ion source development for fusion application (invited)

Takeiri

2010

Review of Scientific Instruments

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“…By these modifications, the input arc power to the ion source was increased to 40 kW which could generate the H − ions at 200 A / m 2 . 9,12 The negative ions are extracted from nine apertures ͑in 3 ϫ 3 lattice pattern, each 14 mm in diameter͒ of the plasma grid by potential difference of several kilovolts applied between the plasma grid and the next extraction grid. The pulse length of the beam extraction was typically 0.2-1.0 s every 60 s.…”

Section: Vacuum-insulated Mev Acceleratormentioning

confidence: 99%

“…Since the Kamaboko source itself has already achieved 300 A / m 2 H − -ion productions ͑at 50 keV͒, 9,12 acceleration of H − -ion beams at the ITER requirement is to be achieved soon.…”

Section: Acceleration Of High-current-density H − Ionsmentioning

confidence: 99%

Acceleration of MeV-class energy, high-current-density H−-ion beams for ITER neutral beam system

Takeuchi

Inoue

Kashiwagi

et al. 2006

Review of Scientific Instruments

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For the ITER neutral beam system, reasearch and development of a vacuum-insulated MeV accelerator has been carried out at Japan Atomic Energy Research Institute. After a successful 1 MV insulation in vacuum for more than 2 h, H − -ion-beam acceleration test is in progress to fulfill the ITER requirement of the current density of 200 A / m 2 at 1 MeV, with good beam optics quality of Ͻ7 mrad divergence. For such a high-current-density H − -ion-beam acceleration, the Kamaboko negative-ion source was operated at high input power, with increased filament number and magnetic filter strength. The optimum perveance was investigated by scanning the extraction and acceleration voltages, together with the beam divergence measurement. As a consequence, H − -ion beams of 146 A / m 2 ͑total ion-beam current: 206 mA͒ were obtained at 836 keV, of which power density is in the "ITER relevant" level. Such high-power-density beams with a divergence as low as 5 mrad were obtained at the optimum perveance corresponding to that of the ITER ͑200 A / m 2 at 1 MeV͒.

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“…Neutral beam injection (NBI) heating for the ITER tokamak foresees [1] 1 MeV deuterium beams from two injectors with a total power of 33 MW and a pulse length of 1 h. This is to be achieved by extracting and accelerating negative deuterium ions from a plasma source of roughly 1.8 m x 0.9 m with a net extraction area of 0.2 m 2 . At a source filling pressure of 0.3 Pa, the accelerated current density (i.e.…”

Section: Introductionmentioning

confidence: 99%

Development of a RF-driven ion source for the ITER NBI system

Staebler

Fantz

Franzen

et al. 2009

Fusion Engineering and Design

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Extensive R&D work on RF-driven negative hydrogen ion sources carried out at IPP Garching led to the decision of ITER to select this type of source as the new reference source for the ITER NBI system. The principle suitability of the RF source has been demonstrated in a small scale, short pulse length experiment: accelerated current densities, co-extracted electron currents at a source operation pressure, all well inside the range of the ITER requirements have been achieved simultaneously. In subsequent experiments, pulse lengths up to 1 h and the possibility of modularly extending the source to ITER source dimensions were demonstrated. The results achieved at the various IPP test beds, the lessons learnt during optimising the source for negative ion production and extraction as well as the problems still to be solved are summarized. As the next step in support of the NBI development for ITER, IPP plans to build a new test facility for beam extraction from a source of half the size for ITER.

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ITER R&D: Auxiliary Systems: Neutral Beam Heating and Current Drive System

Cited by 26 publications

References 9 publications

Negative ion source development for fusion application (invited)

Negative ion source development for fusion application (invited)

Acceleration of MeV-class energy, high-current-density H−-ion beams for ITER neutral beam system

Development of a RF-driven ion source for the ITER NBI system

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