Thermomechanical Analysis of a Blanket with Liquid Li17Pb83 Breeder for an Experimental Fusion Reactor

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1983-08-22T00:00:00+00:00

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N - Mechanical and Thermal Problems of Future Fusion Reactor Power Plants
N4 - Fusion Reactor Blanket and Materials
SMiRT 7 - Chicago, USA. August 22-26, 1983

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IASMiRT

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