阅读说明：本技术 核电厂严重事故的应对安全系统及其控制方法 (Coping safety system for severe accident of nuclear power plant and control method thereof ) 是由 展德奎 赵鑫海 夏少雄 陈鹏 符卉 吴梓杰 于 2020-01-07 设计创作，主要内容包括：一种核电厂严重事故的应对安全系统及其控制方法,应对安全系统包括至少一用于向反应堆压力容器(1)内注水的堆内注水系统(10)；堆内注水系统(10)包括多阶段安注箱(11)、连接一回路系统(3)冷管段(301)的第一注水管线(12)；多阶段安注箱(11)的内部空间包括自上而下分布的气相空间(101)、第一阶段注水空间(102)以及第二阶段注水空间(103)；多阶段安注箱(11)上设有第一流量管线(111)和管径小于第一流量管线(111)的第二流量管线(112),第一流量管线(111)连通第一阶段注水空间(102)和第一注水管线(12),第二流量管线(112)连通第二阶段注水空间(103)和第一注水管线(12)。该核电厂严重事故的应对安全系统以堆内注水系统(10)配合堆外冷却注水系统(20)进行堆内、堆外冷却,实现严重事故后维持反应堆压力容器(1)的完整性。(A safety system for dealing with serious accidents of a nuclear power plant and a control method thereof are provided, wherein the safety system for dealing with serious accidents of the nuclear power plant comprises at least one in-reactor water injection system (10) for injecting water into a reactor pressure vessel (1); the in-pile water injection system (10) comprises a multi-stage safety injection box (11) and a first water injection pipeline (12) connected with a cold pipe section (301) of the loop system (3); the internal space of the multi-stage safety injection box (11) comprises a gas phase space (101), a first-stage water injection space (102) and a second-stage water injection space (103) which are distributed from top to bottom; the multi-stage safety injection box (11) is provided with a first flow pipeline (111) and a second flow pipeline (112) with the pipe diameter smaller than that of the first flow pipeline (111), the first flow pipeline (111) is communicated with the first-stage water injection space (102) and the first water injection pipeline (12), and the second flow pipeline (112) is communicated with the second-stage water injection space (103) and the first water injection pipeline (12). According to the safety system for dealing with the severe accident of the nuclear power plant, the in-reactor water injection system (10) is matched with the out-reactor cooling water injection system (20) to carry out in-reactor and out-reactor cooling, so that the integrity of the reactor pressure vessel (1) is maintained after the severe accident.)