Deuterium-tritium plasmas in the Joint European Torus (JET): Behavior and implications

摘要

This paper reports the first deuterium-tritium (D-T) fusion experiments in the geometry of the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, V. Chuyanov, M. Huguet, R. Parker, Y. Shimamura, and the ITER Joint Central Team and Home Teams, Proceedings of the 16th International Conference on Fusion Energy (International Atomic Energy Agency, Vienna), Fusion Energy 1, 3 (1996)], with long pulse length and an ITER-like divertor. Physics aspects, such as the isotope dependence of confinement, the H-mode (high confinement) threshold, shear optimisation, heating methods, high fusion performance and alpha particle heating, are discussed together with their implications. The technology aspects of tritium wall loading and clean-up, the close coupled tritium plant and the future remote handling divertor target exchange are also mentioned. (C) 1998 American Institute of Physics. [References: 20]