安全壳降压系统、反应堆厂房及安全壳降压方法

By installing a hot water exchange tank and an exhaust piping system inside the containment vessel, and using cooling water to remove substances from the radioactive gas, the problem of pressure exceeding the design pressure inside the containment vessel was solved. This achieved effective pressure relief of the containment vessel and retention of radioactive materials, simplified the system structure, and reduced costs.

CN120913898BActive Publication Date: 2026-07-17CHINA NUCLEAR POWER ENGINEERING CO LTD

Patent Information

Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
CHINA NUCLEAR POWER ENGINEERING CO LTD
Filing Date
2025-08-05
Publication Date
2026-07-17

AI Technical Summary

Technical Problem

In existing technologies, the pressure of radioactive gases inside the containment may exceed the design pressure, leading to containment accidents. Existing pressure relief systems are complex in structure and expensive.

Method used

A hot water exchange tank and an outlet pipeline system are used to introduce radioactive gases from inside the containment vessel into the cooling water of the hot water exchange tank. Gas-liquid separation is performed through a flow guide hood, and radioactive materials are removed using the cooling water. The depressurization process is automatically controlled by a control component.

Benefits of technology

It achieved effective depressurization of the containment vessel, reduced the emission of radioactive materials, simplified the system structure, and lowered construction and maintenance costs.

✦ Generated by Eureka AI based on patent content.

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Abstract

本发明公开了一种安全壳降压系统、反应堆厂房及安全壳降压方法,能够实现安全壳的泄压,并简化安全壳降压系统的结构。该安全壳降压系统包括换热水池和排放降压回路。排放降压回路包括导出管道和导流罩。导出管道的第一端与安全壳内部连通,导出管道的第二端伸入换热水池后位于换热水池内的冷却水液面以下,用于将安全壳内部的放射性气体导出至换热水池内的冷却水中,以通过冷却水去除放射性气体中的放射性物质。导流罩倒扣设置在导出管道第二端的正上方,导流罩的顶部位于换热水池内的冷却水液面以上,导流罩的底部淹没在换热水池内的冷却水液面以下,用于接收去除放射性物质后的气体。
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