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Garber, H.J.; Watson, J.S.
Westinghouse Electric Corp., Pittsburgh, Pa. (USA); Oak Ridge National Lab., Tenn. (USA)1977
Westinghouse Electric Corp., Pittsburgh, Pa. (USA); Oak Ridge National Lab., Tenn. (USA)1977
AbstractAbstract
[en] The salient features of a tentative configuration for a fuel handling system were evolved in connection with the joint Oak Ridge National Laboratory-Westinghouse The Next Step (TNS) Tokamak preconceptual design studies. The tritium-fuel system comprises seven main subsystems: tritium storage and supply, fuel fabrication and delivery, vacuum system spent fuel reprocessing, cryogenic distillation, detritiation of secondary containment sweep gas, surface cleanup processing, and reactor-cell-atmosphere cleanup. Additionally, the tritium system has close tie-ins with other systems such as neutral-beam deuterium injection; torus vacuum pumping, including a divertor if this is required for impurity control; radioactive waste treatments; ventilation of experimental areas; vacuum vessel and shielding coolants; and central instrumentation and control
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1977; 8 p; 7. symposium on fusion research project; Knoxville, TN, USA; 25 - 29 Oct 1977; Available from NTIS., PC A02/MF A01
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