Current experiments on ISX-B, Alcator C, PDX, and PLT respectively address the four areas of principal concern in the development of a tokamak reactor: optimization of MHD-stability at high ..beta..-values; achievement of high n tau/sub E/; preservation of plasma purity; and development of effective techniques for achieving high plasma temperatures. The neutral-beam-heated ISX-B is the first tokamak device to have reached a ..beta..-level of approximately 3%, thus exploring - or even challenging - the theoretical MHD beta limit. Pellet fueling has also been demonstrated successfully. Alcator C, in its initial half-field operation, has obtained tau/sub E/ values exceeding 20 msec …
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Current experiments on ISX-B, Alcator C, PDX, and PLT respectively address the four areas of principal concern in the development of a tokamak reactor: optimization of MHD-stability at high ..beta..-values; achievement of high n tau/sub E/; preservation of plasma purity; and development of effective techniques for achieving high plasma temperatures. The neutral-beam-heated ISX-B is the first tokamak device to have reached a ..beta..-level of approximately 3%, thus exploring - or even challenging - the theoretical MHD beta limit. Pellet fueling has also been demonstrated successfully. Alcator C, in its initial half-field operation, has obtained tau/sub E/ values exceeding 20 msec and has found a modified empirical scaling pattern. The Poloidal Divertor Experiment (PDX) has entered initial round-plasma operation at currents up to 500 kA. Low-power ion-cyclotron heating on PLT has given bulk-ion-temperature rises up to 600 eV and energetic efficiencies exceeding those of neutral-beam heating. Interactive energization of beam-injected ions has also been demonstrated.
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