Divertor target engineering for fusion r
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V.K Thompson; W.J Worraker
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Article
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1990
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Elsevier Science
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English
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It is envisaged that exhaust control in tokamak fusion reactors, e.g. NET, ITER and DEMO, will be achieved using poloidal divertors. The targets for these divertors, which will receive substantial quantities of heat from, and may be eroded by, the exhausted particles, present a significant engineeri