Ml. Watkins et al., THE JOINT EUROPEAN TORUS (JET) PUMPED DIVERTOR RESULTS AND THEIR SIGNIFICANCE FOR THE INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR (ITER), Physics of plasmas, 3(5), 1996, pp. 1881-1891
The effectiveness of the pumped divertor during the 1994/95 experiment
al campaign of the Joint European Torus (JET) [P.-H. Rebut, R. J. Bick
erton, and B. E. Keen, Nucl. Fusion 25, 1011 (1985)] has allowed the p
ursuit of a broad-based research program that is highly relevant to th
e International Thermonuclear Experimental Reactor (ITER) [K. Tomabech
i and the ITER Team, Nucl. Fusion 31, 1135 (1991)]. High-performance h
ot-ion discharges with high confinement (H-modes) free of edge localiz
ed modes (ELMs) have set a JET record neutron rate in deuterium, but a
re limited by various magnetohydrodynamic (MHD) phenomena to beta N <
1.8, where beta(N)=beta/(I/aB), beta is the ratio of the plasma pressu
re to the toroidal field pressure, I is the plasma current, B is the t
oroidal field, and alpha is the horizontal minor radius of the plasma.
Quasi-steady-state ELMy H-modes have also been studied at high power,
high current, and high beta. The underlying energy transport exhibits
a gyro-Bohm dependence that is lost close to the H-mode threshold and
at high beta. ELMy H-modes with detached divertor plasmas and radiati
ve power exhaust (the operating regime foreseen for ITER) reduce the p
ower loading to the targets, but at the expense of main plasma confine
ment and purity. Beryllium has been compared with carbon fiber composi
te as a divertor target material and melting has been induced at ITER
reference off-normal heat loads, but only a moderate degree of self-pr
otection of the beryllium target was found. (C) 1996 American Institut
e of Physics.