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Ex-vessel core melt retention device preventing molten core concrete interaction

机译:前容器芯熔体保持装置,防止熔融芯混凝土相互作用

摘要

The present invention relates to a safety design and risk management of a reactor of a nuclear plant, and more particularly, to an ex-vessel core melt device preventing molten core concrete interaction, which is to handle very severe accidents caused by cooling-function loss to nuclear fuel. Due to the large quantity of nuclear fuel existing in the reactor and decay heat which is latent and continuously generated within the fuel mass for a long time after the nuclear chain reaction, the nuclear fuel is melted in gross at temperature up to 2,500 degrees centigrade, and thereby the surrounding structures and a reactor vessel are attacked and damaged, and in the end, a containment building floor is eroded. This situation may cause environmental radioactivity either by ultimate penetration of the cavity floor or by the buildup of non-condensable gas pressure (i.e., pressurizing the containment building structure), unless the reaction is arrested. The ex-vessel core melt retention device preventing molten core concrete interaction, which is installed for alleviating risks due to unexpected accidents over accidents considered as a design criteria of a nuclear plant, includes: horizontal jacket pipes located on a shell boundary of a cavity floor, the horizontal jacket pipes having water inlets A formed at their lower half in an appropriate density for allowing water to enter the bottom of the pipes; vertical pipes connected at both ends of the horizontal jacket pipes in the form of a dovetail to communicate with each other; and a water supply part located at the lower portion of the horizontal jacket pipes for allowing water to enter from the whole area of the bottom.
机译:本发明涉及核电站反应堆的安全设计和风险管理,尤其涉及一种防止熔融核混凝土相互作用的前容器堆芯熔融装置,该装置将处理由于冷却功能丧失而引起的非常严重的事故。核燃料。由于反应堆内存在大量核燃料,并且在核链反应后很长一段时间内,在燃料团块中潜伏并连续产生的衰减热,使核燃料在最高2500摄氏度的温度下熔化,因此,周围的结构和反应堆容器受到攻击和损坏,最后,安全壳建筑地板被侵蚀。除非反应被阻止,否则这种情况可能通过腔底的最终渗透或通过不可凝气体压力的积累(即,对安全壳建筑结构加压)而引起环境放射性。防止熔融核与混凝土相互作用的容器外堆芯熔体保持装置是为了减轻意外事故造成的风险而安装的,该事故被视为核电站的设计标准,该装置包括:位于型腔底板壳体边界上的水平套管。 ,水平套管在其下半部分形成有适当密度的进水口A,以允许水进入管的底部。垂直管以燕尾形的形式连接在水平套管的两端,以彼此连通。供水部分位于水平套管的下部,以允许水从底部的整个区域进入。

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