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System for the condensation of reliably in a unit casing of a nuclear reactor in the case of an accident steam released suddenly
System for the condensation of reliably in a unit casing of a nuclear reactor in the case of an accident steam released suddenly
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机译:在突然释放事故蒸汽的情况下,可靠地冷凝在核反应堆单元壳体中的系统
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摘要
1,135,826. Reactors. ALLMANNA SVENSKA ELEKTRISKA A.B. 13 April, 1966 [13 April, 1965], No. 16130/66. Heading G6C. The pressure rise inside a containment structure of a steam cooled nuclear reactor is limited in the event of a failure of the reactor pressure vessel by a steam condensing system within the structure. As shown, the reactor 1 is surrounded by the containment 4 which also contains the cooling and heat-accumulating packing 5. If pipes 2 or 3 burst, steam flows to the packing 5 and is condensed. Later sprinkler tubes 10, 15 are coupled to the space 8 by the pump 12 and heat exchanger 12.
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机译:1,135,826。反应堆。 ALLMANNA SVENSKA ELEKTRISKA A.B. 1966年4月13日[1965年4月13日],第16130/66号。标题G6C。在反应堆压力容器发生故障的情况下,蒸汽冷却的核反应堆的安全壳结构内的压力升高会受到该结构内的蒸汽冷凝系统的限制。如图所示,反应器1被安全壳4包围,安全壳4还包含冷却和蓄热的填料5。如果管道2或3破裂,则蒸汽流向填料5并被冷凝。随后的喷水管10、15通过泵12和热交换器12联接到空间8。
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