Conceptual design of 5MW-NBI injector for HL-2M tokamak

Cao, Jianfei; Wei, Hui-Ling; Gui-Qing, Zou; He, Liu; Guang-Jiu, Lei; Zhang, Xian‐Ming; Yang, Xianfu; Yu, Liming; Jiang, Tao; Jiang, Shaofeng; Rao, Jun

doi:10.1016/j.fusengdes.2013.03.034

Cited by 13 publications

(2 citation statements)

References 10 publications

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“…Neutral beam injection (NBI) is one of the most essential ways of heating fusion plasmas in TOKAMAK and has been developed rapidly in recent years. [1][2][3] In 2007, ITER selected a radio-frequency (RF)-driven ion source instead of the original filament source. [4] The heating system requires a reliable negative ion source providing high current density (> 200 A•m −2 ) with high uniformity and at low pressure < 0.3 Pa. [5] It hence needs a high-density, large-area plasma source with good uniformity.…”

Section: Introductionmentioning

confidence: 99%

Influence of a centered dielectric tube on inductively coupled plasma source: Chamber structures and plasma characteristics

Hong

Guang-Jiu

et al. 2017

Chinese Phys. B

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A high-density RF ion source is an essential part of a neutral beam injector. In this study, the authors attempt to retrofit an original regular RF ion source reactor by inserting a thin dielectric tube through the symmetric axis of the discharge chamber. With the aid of this inner tube, the reactor is capable of generating a radial magnetic field instead of the original transverse magnetic field, which solves the E × B drift problem in the current RF ion source structure. To study the disturbance of the dielectric tube, a fluid model is introduced to study the plasma parameters with or without the internal dielectric tube, based on the inductively coupled plasma (ICP) reactor. The simulation results show that while introducing the internal dielectric tube into the ICP reactor, both the plasma density and plasma potential have minor influence during the discharge process, and there is good uniformity at the extraction region. The influence of the control parameters reveals that the plasma densities at the extraction region decrease first and subsequently slow down while enhancing the diffusion region.

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Section: Introductionmentioning

confidence: 99%

Influence of a centered dielectric tube on inductively coupled plasma source: Chamber structures and plasma characteristics

Hong

Guang-Jiu

et al. 2017

Chinese Phys. B

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“…In China, the HL-2A has a beam line with beam power of 3 MW. A 5 MW beam power NBI system is currently under design for the HL-2M [14] . On the EAST, two beam lines with beam power of 8 MW need to be delivered into the core plasma [15] .…”

Section: Introductionmentioning

confidence: 99%

Overview of Development Status for EAST-NBI System

Xie

et al. 2015

Plasma Sci. Technol.

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The neutral beam injection (NBI) system was developed on the Experimental Advanced Superconducting Tokamak (EAST) for plasma heating and current driving. This paper presents the brief history, design, development, and the main experimental results of the R&D of neutral beam injector on the test bed and on EAST. In particular, it will describe: (1) how the two beamlines with a total beam power of 8 MW were developed; (2) the design of the EAST-NBI system including the high power ion source, main vacuum chamber, inner components, beam diagnostic system and sub-system; (3) the experimental results of beamline-1 on the summer campaign of EAST in 2014 and, (4) the status of beamline-2 and the future plan of EAST-NBIs.

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Status of the cryogenic system of the HL-2M tokamak

Chen

et al. 2020

Cryogenics

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Conceptual design of 5MW-NBI injector for HL-2M tokamak

Cited by 13 publications

References 10 publications

Influence of a centered dielectric tube on inductively coupled plasma source: Chamber structures and plasma characteristics

Influence of a centered dielectric tube on inductively coupled plasma source: Chamber structures and plasma characteristics

Overview of Development Status for EAST-NBI System

Status of the cryogenic system of the HL-2M tokamak

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