R. Kumazawa et al., Ion cyclotron range of frequency heating experiments on the large helical device and high energy ion behavior, PHYS PLASMA, 8(5), 2001, pp. 2139-2147
Ion cyclotron range of frequency (ICRF) heating experiments on the Large He
lical Device (LHD) [O. Motojima Fus. Eng. Des. 20, 3 (1993)] achieved signi
ficant advances during the third experimental campaign carried out in 1999.
They showed significant results in two heating modes; these are modes of t
he ICH-sustained plasma with large plasma stored energy and the neutral bea
m injection (NBI) plasma under additional heating. A long-pulse operation o
f more than 1 minute was achieved at a level of 1 MW. The characteristics o
f the ICRF heated plasma are the same as those of the NBI heated plasma. Th
e energy confinement time is longer than that of International Stellarator
Scaling 95. Three keys to successful ICRF heating are as follows: (1) an in
crease in the magnetic field strength, (2) the employment of an inward shif
t of the magnetic axis, (3) the installation of actively cooled graphite pl
ates along the divertor legs. Highly energetic protons accelerated by the I
CRF electric field were experimentally observed in the energy range from 30
to 250 keV and the tail temperature depended on the energy balance between
the wave heating and the electron drag. The transfer efficiency from the h
igh energy ions to the bulk plasma was deduced from the increase in the ene
rgy confinement time due to the high energy ions in the lower density disch
arge, which agrees fairly well with the result obtained by the Monte Carlo
simulation. The transfer efficiency is expected to be 95% at an electron de
nsity of more than n(e)=5.0x10(19) m(-3) even in the high power heating of
10 MW. The accumulation of impurities, e.g., FeXVI and OV was not observed
in high rf power and long pulse operation. The well-defined divertor intrin
sic to LHD is believed to be useful in reducing the impurity influx. (C) 20
01 American Institute of Physics.