Commissioning of heating neutral beams for COMPASS-D tokamak

Deichuli, P. P.; Давыденко, В. И.; Belov, V. P.; Gorbovsky, A. I.; Dranichnikov, A.; Ivanov, A. A.; Сорокин, А. В.; Mishagin, V. V.; Abdrashitov, A. F.; Kolmogorov, V. V.; Kondakov, A. A.

doi:10.1063/1.3672108

Cited by 14 publications

(11 citation statements)

References 4 publications

(3 reference statements)

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“…They are lost at the plasma edge. It is shown in [2] that the population of this fraction is quite low (<5%); therefore, we do The beam composition is determined from the intensity of the Doppler-shifted spectral lines, which directly depends on the number of the extracted ions. The composition of the extracted ion beam was measured with two arrangements of the ion source: with and without the Faraday copper shield in the ion source.…”

Section: Resultsmentioning

confidence: 99%

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Energy composition of high-energy neutral beams on the COMPASS tokamak

et al. 2016

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Abstract. The COMPASS tokamak is equipped with two identical neutral beam injectors (NBI) for additional plasma heating. They provide a beam of deuterium atoms with a power of up to ~(2 × 300) kW. We show that the neutral beam is not monoenergetic but contains several energy components. An accurate knowledge of the neutral beam power in each individual energy component is essential for a detailed description of the beam--plasma interaction and better understanding of the NBI heating processes in the COMPASS tokamak. This paper describes the determination of individual energy components in the neutral beam from intensities of the Doppler-shifted D lines, which are measured by a high-resolution spectrometer viewing the neutral beam-line at the exit of NBI. Furthermore, the divergence of beamlets escaping single aperture of the last accelerating grid is deduced from the width of the Doppler-shifted lines. Recently, one of the NBI systems was modifi ed by the removal of the Faraday copper shield from the ion source. The comparison of the beam composition and the beamlet divergence before and after this modifi cation is also presented.

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Section: Resultsmentioning

confidence: 99%

“…Two NBI systems were designed and manufactured at the Budker Institute of Nuclear Physics, Novosibirsk, for the COMPASS tokamak [2]. Each of them can produce the beam with energy of up to 40 keV and the power of up to 300 kW.…”

Section: Neutral Beam Injector (Nbi)mentioning

confidence: 99%

Energy composition of high-energy neutral beams on the COMPASS tokamak

et al. 2016

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“…The standard configuration of the NBI heating system in COMPASS [3] consists of two identical injectors as shown in figure 1. Each NBI injects a deuterium beam in the co-current direction tangentially into the tokamak vessel.…”

Section: Nbi System At the Compass Tokamakmentioning

confidence: 99%

“…It is equipped with a neutral beam injection (NBI) system for additional heating. Its power, energy and geometry of the beam were chosen carefully in view of the specific properties of the COMPASS tokamak, which is a compact tokamak with a short trajectory of interaction between neutrals and plasma [2,3].…”

Section: Introductionmentioning

confidence: 99%

Experimental observations of local plasma parameters in the COMPASS divertor in NBI-assisted L-mode plasmas

Dimitrova¹,

Popov²,

Havlíček³

et al. 2021

J. Inst.

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A: This paper presents an experimental characterization of the local plasma parameters in the COMPASS open divertor in deuterium, L-mode plasmas by means of Langmuir probes during neutral beam injection (NBI) heating. The effect of NBI heating of the core plasma on the local divertor plasma parameters is investigated under different plasma configurations and different directions of the magnetic field and plasma current for different line-averaged electron densities. At low line-averaged densities below 6 × 10 19 m −3 , a low NBI heating power level does not lead to any significant changes in the plasma parameters in the divertor region. It is also found that for a reversed magnetic field the influence of NBI in the divertor is stronger at higher line-averaged electron density and plasma current. In the divertor, the impact of the NBI heating is more pronounced at high delivered powers (above 𝑃 NBI = 320 kW) and line-averaged densities (above 7 × 10 19 m −3 ). The electron temperature and the floating potential at the outer target increases respectively with 10-50% and 100%, while the plasma potential in the inner divertor increases twofold. At a higher line-averaged density, the NBI heating affects the edge plasma, namely, the electron temperature in the midplane scrape-off layer and the heating moves toward the divertor. Thus, a twice as high electron temperature is observed in the divertor and a bi-Maxwellian electron energy distribution function arises. K: Plasma diagnostics -probes; Data processing methods; Ionization and excitation processes Deceased.

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“…Powerful beams of hydrogen or deuterium atoms (neutral beams) are widely used for plasma heating in fusion facilities [1][2][3][4][5]. Neutral beam (NB) injector for the TCV tokamak has been designed to produce a deuterium beam with energy 30 keV, equivalent current up to 50 A, and pulse duration 2 s [6][7].…”

Section: Introductionmentioning

confidence: 99%

Assessment of neutron production in neutral beam injector of TCV tokamak

Polosatkin¹,

Давыденко²,

Deichuli³

et al. 2016

AIP Conference Proceedings

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Abstract. Neutral beam (NB) injector for the TCV tokamak has been designed to produce a deuterium beam with energy 30 keV, equivalent current up to 50 A, and pulse duration 2 s. The injector operation is accompanied by generation of fast neutrons produced in deuterium-deuterium collisions via a nuclear fusion reaction D(D,n)3He. Main sources of the neutrons are a beam neutralizer and a deuterium-saturated surface of beam dump. Measurements of the neutron yields from the both sources were produced on the prototype of TCV injector in the Budker Institute of Nuclear Physics. Neutron yields from neutralizer and beam dump are equal to 9.5x10 8 s −1 and 2.3x10 9 s −1 for the nominal parameters of the injector (30 kV, 50 A).

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Commissioning of heating neutral beams for COMPASS-D tokamak

Cited by 14 publications

References 4 publications

Energy composition of high-energy neutral beams on the COMPASS tokamak

Energy composition of high-energy neutral beams on the COMPASS tokamak

Experimental observations of local plasma parameters in the COMPASS divertor in NBI-assisted L-mode plasmas

Assessment of neutron production in neutral beam injector of TCV tokamak

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