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    • 2. 发明授权
    • Passive shut-down heat removal system
    • 被动关闭除热系统
    • US4780270A
    • 1988-10-25
    • US896030
    • 1986-08-13
    • Rolv HundalJohn E. Sharbaugh
    • Rolv HundalJohn E. Sharbaugh
    • G21C1/03G21C13/02G21C15/18
    • G21C15/18G21C1/03G21C13/02Y02E30/34Y02E30/35
    • An improved shut-down heat removal system for a liquid metal nuclear reactor of the type having a vessel for holding hot and cold pools of liquid sodium is disclosed herein. Generally, the improved system comprises a redan or barrier within the reactor vessel which allows an auxiliary heat exchanger to become immersed in liquid sodium from the hot pool whenever the reactor pump fails to generate a metal-circulating pressure differential between the hot and cold pools of sodium. This redan also defines an alternative circulation path between the hot and cold pools of sodium in order to equilibrate the distribution of the decay heat from the reactor core. The invention may take the form of a redan or barrier that circumscribes the inner wall of the reactor vessel, thereby defining an annular space therebetween. In this embodiment, the bottom of the annular space communicates with the cold pool of sodium, and the auxiliary heat exchanger is placed in this annular space just above the drawn-down level that the liquid sodium assumes during normal operating conditions. Alternatively, the redan of the invention may include a pair of vertically oriented, concentrically disposed standpipes having a piston member disposed between them that operates somewhat like a pressure-sensitive valve. In both embodiments, the cessation of the pressure differential that is normally created by the reactor pump causes the auxiliary heat exchanger to be immersed in liquid sodium from the hot pool. Additionally, the redan in both embodiments forms a circulation flow path between the hot and cold pools so that the decay heat from the nuclear core is uniformly distributed within the vessel.
    • 本文公开了一种用于液体金属核反应堆的改进的关闭除热系统,其具有用于容纳液体钠的冷热池的容器。 通常,改进的系统包括反应器容器内的重蒸或障碍物,其允许辅助热交换器在热反应器泵不能在热池和热池之间产生金属循环压差时从热池中浸入液体钠中 钠。 这个redan还定义了钠和钠的热池和冷池之间的替代循环路径,以平衡来自反应堆堆芯的衰变热分布。 本发明可以采取围绕反应堆容器的内壁的重蒸或障碍物的形式,由此在它们之间形成环形空间。 在该实施例中,环形空间的底部与钠的冷库连通,并且辅助热交换器被放置在刚好在正常操作条件下液体钠所采取的拉下水平面的该环形空间中。 或者,本发明的重量可以包括一对垂直取向的同心设置的立管,其具有设置在它们之间的活塞构件,其稍微像压敏阀一样操作。 在两个实施例中,通常由反应堆泵产生的压差的停止导致辅助热交换器从热池中浸入液体钠中。 另外,两个实施例中的重蒸组合形成了热池和冷池之间的循环流动路径,使得来自核芯的衰减热均匀地分布在容器内。