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Recent results from the DIII-D tokamak have contributed to the understanding of many elements of tokamak physics and the application of this understanding to the design of next generation devices including ITER and CIT. The limitations of magnetohydrodynamic stability on the values of plasma beta (the ratio of kinetic pressure to the containing pressure of the magnetic field) that can be attained have been demonstrated experimentally and found to be described by existing theory. Values of beta (10.7%) well in excess of those required for proposed devices have been demonstrated. Regimes of confinement (H-mode) that scale favourably to proposed next generation devices have been established. Experiments demonstrating the dependence of the energy confinement on plasma size have been completed. Experimental results in plasma transport and edge plasma phenomena are found to agree with theories based on short wavelength turbulence. Control of the divertor heat loads and impurity influx has been demonstrated, and new progress has been made in understanding plasma edge phenomena.

Additional information

Authors: LUXON J L ET AL., General Atomics, San Diego (US)
Bibliographic Reference: Article: Plasma Physics and Controlled Fusion, Vol. 32 (1990) No. 11, pp. 869-887
Record Number: 199110269 / Last updated on: 1994-12-02
Original language: en
Available languages: en