Heating and Current Drive by N-NBI in JT-60U and LHD

Journal Article · Mon Sep 15 00:00:00 EDT 2003 · Fusion Science and Technology

OSTI ID:20849565

Kaneko, O ^[1]; Yamamoto, T ^[2]; Akiba, M ^[2]; Hanada, M ^[2]; Ikeda, K ^[1]; Inoue, T ^[2]; Nagaoka, K ^[1]; Oka, Y ^[1]; Osakabe, M ^[1]; Takeiri, Y ^[1]; Tsumori, K ^[1]; Umeda, N ^[2]; Watanabe, K ^[2]

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1. National Institute for Fusion Science (Japan)
2. Japan Atomic Energy Research Institute (Japan)

Two pilot facilities of advanced negative-ion-based neutral beam injection heating system have been working successfully on the JT-60U tokamak and the LHD heliotron in Japan. These were the first applications of negative-ion technology to the production of high current neutral beam for plasma heating as well as current drive. High energy deuterium beam of 400 keV (5.8 MW) was injected in JT-60U for efficient current drive, and high power hydrogen beam of 9.0 MW (160 keV) was injected in LHD producing high performance plasmas. These results demonstrate the feasibility of negative ion beam system for future fusion reactors such as ITER.

• OSTI ID: 20849565
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 2 Vol. 44; ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ANIONS
BEAM INJECTION HEATING
DEUTERIUM
HYDROGEN
ITER TOKAMAK
JT-60U TOKAMAK
KEV RANGE
LHD DEVICE
NEUTRAL ATOM BEAM INJECTION
PERFORMANCE
PLASMA