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SECURITY INSTRUCTIONS CONCERNED BY A NUCLEAR REACTOR PRESSURER

机译:核反应堆加压器应注意的安全说明

摘要

A safety device against overpressure failure of a nuclear reactor pressure vessel in case of inadequate core cooling, includes a pressure relief system responding as a function of temperature. A differential-pressure-loaded pressure relief valve set in a wall or an immediately adjacent pipeline of the pressure vessel which is exposed to primary pressure, has a closure piece that is preferably a differential-pressure piston being mounted so as to be longitudinally displaceable and being sealingly retained in a closure position thereof by a fusible stop. When an upper threshold temperature is reached in the interior of the reactor, which causes the fusible stop to melt due to a threshold temperature heat flow reaching the stop, the differential-pressure piston is moved into an opened position thereof. With correspondingly lower cross-sectional dimensions of the pressure relief valve and lines connected thereto, the pressure relief line may alternatively be constructed as a control line for a separate relief valve.
机译:在堆芯冷却不充分的情况下,防止核反应堆压力容器超压故障的安全装置包括一个随温度变化而响应的卸压系统。设置在暴露于初级压力的压力容器的壁或紧邻的管道中的,加载有差压的压力溢流阀具有一个封闭件,该封闭件优选地是差压活塞,该封闭件被安装成可纵向移动并且可纵向移动。通过可熔止动件密封地保持在其关闭位置。当在反应堆内部达到上限温度时,由于到达止动点的阈值温度热流导致可熔止动块熔化,压差活塞移动到其打开位置。在减压阀和与之连接的管路的相应较小的横截面尺寸的情况下,减压管路可替代地构造为用于单独的减压阀的控制管路。

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