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Author(s):
M. Okamoto and S. Murakami
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Title:
Plasma Heating in Toroidal Systems
Date of publication:
Feb. 1993
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Key words:
plasma heating, fast ions, alpha heating, NBI heating, wave heating, ICRF heating, current drive, bootstrap current
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Abstract:
The purpose of this paper is to review the present status of plasma heating in toroidal systems (mainly tokamaks and helical systems) for astrophysical plasma scientists. The main method of plasma heating in toroidal systems or tori is to utilize fast ions (NBI heating and alpha heating). The maximum ion temperature of 38 keV has been achieved at the plasma center by neutral beam injections (NBls) in the JT-60U tokamak. Ripple-trapped losses of fast ions produced by NBIs have been measured also in the JT-60U. The first tokamak discharges in deuterium-tritium fuelled mixtures have been carried out, successfully in the JET tokamak. These experimental results are compared with the theoretical predictions based on t,he Coulomb collisions. Another powerful method is the ICRF heating (Ion Cyclotron Range of Frequency). However, this article will be focussed mainly on the NBI and alpha heatings. Related to plasma heating the current drive will be mentioned briefly placing an emphasis on the bootstrap current.
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