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Electron injection by edge localized neutral beams
Nuclear Fusion, 1990A negative potential in the edge region of a tokamak plasma may induce a transition from L-mode to H-mode confinement. Such a negative potential may be produced by injection of various atomic species via edge localized neutral beams, with subsequent prompt loss of ions.
T. Ohkawa, R.L. Miller
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Status of the ITER neutral beam injection system.
The Review of scientific instruments, 2008The ITER neutral beam injectors are the first injectors to be designed to operate under conditions and constraints similar to those that will be encountered with a fusion reactor. The injectors will use a single large ion source and accelerator that will produce 40 A D(-) 1 MeV beams for pulse lengths of up to 3600 s.
Hemsworth R S, Tanga A, Antoni V
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Engineering of Cryopump for Neutral Beam Injection
Plasma Science and Technology, 2006Neutrals beam injection (NBI) has proven to be a very effective method for plasma heating. A set of positive-ion-based NBI system is being designed, manufactured and tested at ASIPP. The aim of this study was to ascertain the most effective cryocondensation pump structure for the hydrogen NBI system.
Xie yuanlai +2 more
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High Power Neutral Beam Injection in LHD
Plasma Science and Technology, 2006The results on high power injection with the neutral beam injection (NBI) system for the Large Helical Device (LHD) are reported. The system consists of three beam-lines with two hydrogen negative ion (H− ion) sources installed in each beam-line. In order to improve the injection power, a new beam accelerator with a multi-slot grounded grid (MSGG) has ...
K Tsumori +10 more
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Neutral beam injection optimization at TJ-II
Fusion Engineering and Design, 2005Abstract Neutral beam injection (NBI) heating has been used on the TJ-II stellarator for the first time. The beam has a port-through power between 200 and 400 kW and injection energy 28 kV. Beam transmission is limited by beam interception at the injection port and the first toroidal field coil, therefore, beam steering optimization is of critical ...
C. Fuentes +15 more
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Neutral beam injection system for JT-60.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1986日本原子力研究所では,臨界プラズマ試験装置JT-60のジュール加熱実験に引き続いて,臨界プラズマ条件の達成を目指す第2段加熱(追加熱)実験を実施する予定である。その実験に必要な中性粒子入射加熱装置の建設も終盤を迎え,製作段階から試験段階へ移行しつつある。本加熱装置は大容量,長パルスのシステムとして世界最大級のものである。本稿では,JT-60中性粒子入射加熱装置について,開発研究の経緯,装置の概要と特徴,建設の現状を紹介する。
Hirofumi SHIRAKATA, Masato AKIBA
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The JT-60 neutral beam injection system
Fusion Engineering and Design, 1987The JT-60 neutral beam injection system has been designed to inject a neutral hydrogen beam power of 20 MW at energies of 75–100 keV for 10 s. The system consists of 14 beamline units, 14 power supply units for the ion sources, a liquid helium and liquid nitrogen cryogenic system for the beamline cryopumps, a demineralized cooling system for heat dump ...
S. Matsuda +24 more
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Relativistic electron beam injection into neutral gases
Plasma Physics, 1983Relativistic Electron Beam (REB) (UD approximately=1 MV, Ib approximately=10 kA, tau b=60 ns) injection into gases (He, SF6, He+SF6+H2 mixture and air) in a wide pressure range 1-750 torr (for air 10-3-750 torr) is investigated experimentally. The maximum energy loss of REB in SF6 at P0 approximately=750 torr had order of 1090 Joules (about 40% of the ...
S G Arutyunyan +7 more
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High power beams for neutral injection heating
Vacuum, 1984Abstract High power neutral beams are commonly used for the heating of magnetically confined plasmas in the fusion programme throughout the world. These beams are generated by the acceleration of multi-ampere beams of positive ions extracted from large area ion sources.
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