6.2 Neutral Beam System for Heating and Current Drive
نویسندگان
چکیده
منابع مشابه
Progress in ITER Heating and Current Drive System
Recent progress in the R&D and the design work of plasma heating and current drive (H&CD) technologies for ITER are described. The H&CD systems are composed of 20 MW electron cyclotron (EC), 20 MW ion cyclotron (IC) and 33 MW negative ion based neutral beam (N-NB) systems, and design and R&D work continues for plasma commissioning. Significant progress in R&D during the preceding two years has ...
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Modification of the two existing DIII-D neutral beam lines is proposed to allow vertical steering to provide off-axis neutral beam current drive (NBCD) as far off-axis as half the plasma radius. New calculations indicate very good current drive with good localization off-axis as long as the toroidal magnetic field, BT, and the plasma current, Ip, are in the same direction (for a beam steered do...
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N. Takeuchi, H. Idei, A. Fukuyama, T. Seki, R. Kumazawa, T. Mutoh, K. Saito, H. Kasahara, Y. Nakamura, Y. Takase, T. Watari, and LHD ICRF group 1) Ariake National College of Technology, Omuta, Fukuoka 836-8585, Japan 2) Research Institute for Applied Mechanics, Kyushu University, Kasuga, Fukuoka 816-8580, Japan 3) Department of Nuclear Engineering, Kyoto University, Kyoto 606-8501, Japan 4) Nat...
متن کاملSpectral Effects on Fast Wave Core Heating and Current Drive
RF heating and current drive is an essential component in most magnetic fusion devices, including ITER. Recent results obtained with high harmonic fast wave (HHFW) heating and current drive (CD) on NSTX strongly support the hypothesis that the onset of perpendicular fast wave propagation right at or very near the launcher is a primary cause for reduced core heating efficiency at long wavelength...
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ژورنال
عنوان ژورنال: RADIOISOTOPES
سال: 2018
ISSN: 0033-8303,1884-4111
DOI: 10.3769/radioisotopes.67.165