Beam performance of negative-ion based NBI system for JT-60

Itoh, Takaò; Akino, N.; Ebisawa, N.; Grisham, L.; Honda, Akira; Hu, Liqun; Kawai, M.; Kazawa, M.; Kuriyama, M.; Kusaka, M.; Mogaki, K.; Nishitani, T.; Ohga, T.; Okumura, Y.; Oohara, H.; Ooshima, K.; Satoh, F.; Seki, Hiroshi; Tanai, Y.; Toyokawa, R.; Usui, K.; Watanabe, K.; Yamaguti, Masao; Yamazaki, H.; Yamazaki, T.

doi:10.1016/s0920-3796(00)00438-5

Cited by 15 publications

(2 citation statements)

References 7 publications

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“…It is widely known in the international fusion community that neutral beam injection (NBI) is one of the most effective means for plasma heating [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

Hot Cathode’s Working Voltage Impacts on the Operation of High Current Ion Source

Chen

Liu

et al. 2014

J Fusion Energ

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High power ion source is one of the important parts of the neutral beam injection. It produces high energy beam by extracting and accelerating ions from its arc chamber. The hot cathode (filaments) in the arc chamber of the ion source operates in two modes. Operation mode of the cathode has great effect on the stable operation of the ion source. Based on the theory of hot cathode and experimental results, this paper presents the operation results (beam current, arc efficiency) of an ion source with various cathode temperatures (controlled by voltage applied to the cathode).

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“…It is widely known in the international fusion community that neutral beam injection (NBI) is one of the most effective means for plasma heating [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

Hot Cathode’s Working Voltage Impacts on the Operation of High Current Ion Source

Chen

Liu

et al. 2014

J Fusion Energ

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“…Neutral beam injection (NBI) is one of main auxiliary heating methods adopted in tokamaks like JET [1] , JT-60U [2,3] , and ASDEX-U, as well as ITER in future. It usually plays an important role in the L-H mode transition, current drive and control, rotation generation and MHD instability control [4] .…”

Section: Introductionmentioning

confidence: 99%

Predictive Calculation of Neutral Beam Heating Plasmas in EAST Tokamak by NUBEAM Code for Certain Parameter Ranges

Ni¹,

Tieshuan²,

Zhang³

et al. 2010

Plasma Sci. Technol.

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A predictive calculation is carried out for neutral beam heating of fusion plasmas in EAST by using NUBEAM code under certain plasma conditions. Results calculated are analyzed for different plasma parameters. Relations between major plasma parameters, such as density and temperature, are obtained and key physical processes in the neutral beam heating, including beam power deposition, trapped fraction, heating efficiency, and power loss, are simulated. Other physical processes, such as current-drive, toroidal rotation and neutron emission, are also discussed.

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Calculation of Beam Extraction Pulse Duration for Beam Angular Divergence Measurement of EAST Neutral Beam Injection

Xie

et al. 2010

J Fusion Energ

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Beam performance of negative-ion based NBI system for JT-60

Cited by 15 publications

References 7 publications

Hot Cathode’s Working Voltage Impacts on the Operation of High Current Ion Source

Hot Cathode’s Working Voltage Impacts on the Operation of High Current Ion Source

Predictive Calculation of Neutral Beam Heating Plasmas in EAST Tokamak by NUBEAM Code for Certain Parameter Ranges

Calculation of Beam Extraction Pulse Duration for Beam Angular Divergence Measurement of EAST Neutral Beam Injection

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