WO2014029305A1 - 一种核电站堆腔注水冷却系统 - Google Patents

一种核电站堆腔注水冷却系统 Download PDF

Info

Publication number
WO2014029305A1
WO2014029305A1 PCT/CN2013/081727 CN2013081727W WO2014029305A1 WO 2014029305 A1 WO2014029305 A1 WO 2014029305A1 CN 2013081727 W CN2013081727 W CN 2013081727W WO 2014029305 A1 WO2014029305 A1 WO 2014029305A1
Authority
WO
WIPO (PCT)
Prior art keywords
water injection
backup
isolation valve
pipe
reactor cavity
Prior art date
Application number
PCT/CN2013/081727
Other languages
English (en)
French (fr)
Inventor
黄伟
任云
赖建永
张玉龙
隋海明
曾畅
Original Assignee
中国核动力研究设计院
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 中国核动力研究设计院 filed Critical 中国核动力研究设计院
Priority to GB1504123.9A priority Critical patent/GB2520215B/en
Publication of WO2014029305A1 publication Critical patent/WO2014029305A1/zh

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to a cooling system, in particular to a reactor cavity water injection cooling system which is used for accident response and mitigation in the case of a nuclear power plant accident.
  • the design features are as follows: After a serious accident occurs, the water in the refueling tank in the containment is used as cooling water, and is injected into the stack in a passive manner by gravity, submerging the lower head of the reactor pressure vessel and the cylinder at a certain height.
  • the cooling water flows through the flow path between the reactor pressure vessel and its insulation layer and cools the outer wall surface of the reactor pressure vessel, is heated to form steam, and then returns to the containment space through the opening of the upper portion of the insulation layer.
  • the technical problem to be solved by the present invention is to provide a core melting in a nuclear power plant.
  • the outer wall surface of the reactor pressure vessel can be cooled by a combination of active and passive cooling water injection, thereby trapping the core melt in the reactor pressure vessel to prevent a reactor cavity water injection cooling system that may threaten the integrity of the containment vessel. .
  • the technical solution of the present invention is a nuclear power plant reactor cavity water injection cooling system, comprising: a reactor stack chamber disposed in a reactor containment, a pressure vessel disposed in the reactor stack chamber, located in the reactor stack chamber and An insulating barrier between the pressure vessels and surrounding the pressure vessel, further comprising an external water injection system and a high water injection system disposed in the safety enclosure;
  • the external water injection system includes an external water source, an external water injection pipe connected to the external water source, and a stack water injection pump disposed on the external water injection pipe; the external water injection pipe is connected to the bottom of the heat insulation barrier through the safety shell;
  • the high water injection system includes a high water injection tank, and a high water injection pipe connecting the bottom of the high water injection tank and the external water injection pipe.
  • the external water source is located at a fire water source outside the containment.
  • first isolation valve and a second isolation valve disposed upstream and downstream of the stack water injection pump, and a third isolation valve disposed on the high position water injection pipe.
  • a heat exchanger disposed outside the containment vessel, a fourth isolation valve disposed between the stacker water injection pump and the first isolation valve, coupled between the stacker water injection pump and the fourth isolation valve a heat exchange outlet pipe on the external water injection pipe, a heat exchange water inlet pipe connected to the external water injection pipe between the first isolation valve and the fourth isolation valve, the heat exchange water outlet pipe and the heat exchange water inlet pipe respectively It is connected to the water inlet and the water outlet of the heat exchange.
  • a first backup isolation valve and a backup stack injection water pump are sequentially disposed, and the first backup pipeline is connected in parallel with an external water injection pipe connected to the first isolation valve and the stack cavity water injection pump.
  • a backup heat exchanger disposed outside the containment, a second backup isolation valve disposed between the backup stack water pump and the first backup standby valve, and a water injection pump connected to the backup stack chamber a backup heat exchange outlet pipe on the first backup line between the second backup isolation valve, and a standby heat exchange inlet pipe connected to the first backup line between the first backup isolation valve and the second backup isolation valve
  • the standby heat exchange outlet pipe and the standby heat exchange inlet pipe are respectively connected to the water inlet and the water outlet of the standby heat exchanger.
  • the low water injection system comprising a low water injection tank disposed at the bottom of the containment, a lower water injection pipe connected to the bottom of the lower water injection tank, and a fifth isolation valve disposed on the lower water injection pipe
  • the lower main water pipe is connected to an external water injection pipe between the stack water injection pump and the second isolation valve.
  • the second backup line is provided with a third backup isolation valve, the second standby line is connected at one end to the bottom of the low water injection tank, and the other end is connected to the upstream of the backup stack water pump On a spare line.
  • a check valve is disposed on the fire pipe between the second isolation valve and the connection between the low water injection pipe and the external water injection pipe, and the outside between the first isolation valve and the connection between the high water injection pipe and the external water injection pipe in the safety casing
  • a check valve is arranged on the water injection pipe, and a check valve is arranged on the high water injection pipe between the fourth isolation valve and the connection between the high water injection pipe and the external water injection pipe, and the fifth isolation valve and the lower water injection pipe and the external water injection pipe
  • a check valve is disposed on the lower injection pipe between the joints, and a check valve is disposed downstream of the third backup isolation valve on the second backup line.
  • the heat insulation barrier is supported in the stack cavity, and a cavity is formed between the heat insulation barrier and the pressure vessel, and a discharge window is arranged at a junction of the cavity and the top of the stack cavity, and the discharge window is higher than the low level Water injection tank.
  • the invention has the beneficial effects that the system adopts a water injection mode combining active and passive, and the performance is stable and reliable, and can effectively alleviate the serious accident consequences and ensure the integrity of the reactor pressure vessel under severe accidents.
  • FIG. 1 is a schematic diagram of a water injection cooling system for a pressurized water reactor nuclear power plant;
  • FIG. 1 1-pressure vessel, 2-insulation barrier, 3-low water injection tank, 4-high water injection tank, 5-fifth isolation valve , 501-third alternate isolation valve, 6-check valve, 7-stack injection pump, 8- fourth isolation valve, 801-second alternate isolation valve, 9-first isolation valve, 901-first alternate isolation Valve, 10-second isolation valve, 11-third isolation valve, 12-reactor containment, 13-reactor stack, 14-external water source, 15-external water injection pipe, 16-high water injection pipe, 17-low water injection pipe , 18 - First backup line, 19 - Second backup line, 20 - Discharge window.
  • a pressurized water injection cooling system of a pressurized water reactor nuclear power plant of the present invention is provided with a reactor stack chamber 13 in a reactor containment vessel 12, a pressure vessel 1 is disposed in the reactor stack chamber 13, and a heat insulation barrier 2 is located in the reactor stack chamber. 13 and the pressure vessel 1 and surrounding the pressure vessel 1, the high water injection system is disposed in the safety shell 12; the structure of the heat insulation barrier 2 can adopt the design scheme of the currently known AP1000, and the heat insulation barrier 2 is supported in the reactor cavity 13 Forming a cavity with the pressure vessel, the cavity being provided at the junction with the top of the stack cavity Discharge window 20.
  • An external water injection system is further provided in the heap water injection cooling system of the present invention, the external water injection system comprising an external water source 14, an external water injection pipe 15 connected to the external water source 14, and a stack cavity disposed on the external water injection pipe 15. a water injection pump 7, a first isolation valve 9 and a second isolation valve 10 respectively disposed upstream and downstream of the stack water injection pump 7; the external water injection pipe 15 passes through the safety shell 12 and enters the reactor cavity 13 and is insulated The bottom of the barrier 2 is connected; the external water source 14 described above may be a fire water source disposed outside the containment.
  • the high water injection system includes a high water injection tank 4 disposed above the core height, a high water injection pipe 16 connecting the bottom of the high water injection tank 4 and the external water injection pipe 15 entering the safety casing 12, and is disposed on the high water injection pipe 16
  • the third isolation valve 11 may be an isolation valve block composed of two or more parallel isolation valves.
  • the heat exchanger is disposed outside the containment vessel 12, and the fourth isolation valve 8 is disposed on the pipe section of the external water injection pipe 15 between the stacker water injection pump 7 and the first isolation valve 9, and one end of the heat exchange water pipe is connected to the On the external water injection pipe 15 between the stacking water injection pump 7 and the fourth isolation valve 8, one end of the heat exchange inlet pipe is connected to the external water injection pipe 15 between the first isolation valve 9 and the fourth isolation valve 8.
  • the other ends of the heat exchange outlet pipe and the heat exchange inlet pipe are respectively connected to the water inlet and the water outlet of the heat exchange.
  • the low-level water injection system of the present invention includes a low-level water injection system 3, a low-position water injection tank 3 disposed at the bottom of the safety housing, and a low-position water injection pipe 17 connected to the bottom of the low-level water injection tank 3
  • a fifth isolation valve 5 on the lower water injection pipe 17 is connected to the external water injection pipe 15 between the stack water injection pump 7 and the second isolation valve 10.
  • a check valve 6 is disposed on the external water injection pipe 15 between the second isolation valve 10 and the connection between the lower water injection pipe 17 and the external water injection pipe 15, and the first isolation valve 9 and the high water injection pipe 16 and the outside in the containment case 12
  • a check valve 6 is disposed on the external water injection pipe 15 between the joints of the water injection pipes 15, and a check is provided on the high water injection pipe 16 between the fourth isolation valve 11 and the connection between the high water injection pipe 16 and the external water injection pipe 15.
  • the valve 6, a check valve 6 is provided on the lower water injection pipe 17 between the fifth isolation valve 5 and the connection between the lower water injection pipe 17 and the external water injection pipe 15.
  • a first backup isolation valve 901 and a backup stack injection water pump 701 are disposed on the first backup line 18 from the upstream to the downstream, and the first backup line 18 is connected to the first isolation valve 9 and the stack cavity water pump 7
  • the outer water injection pipes 15 are connected in parallel, that is, one end thereof is connected downstream of the first isolation valve 9, and the other end is connected between the stack water injection pump 7 and the check valve 6 downstream of the second isolation valve 10.
  • a backup heat exchanger is further disposed outside the containment vessel 12; a second backup isolation valve 801 is disposed between the backup stack water injection pump 701 and the first provided isolation valve 901, and a standby heat exchange outlet pipe is connected at the end A first backup line between the backup stack water pump 701 and the second backup isolation valve 801 is connected between the first backup isolation valve 901 and the second backup isolation valve 801 at one end.
  • the other ends of the standby heat exchange outlet pipe and the backup heat exchange inlet pipe are respectively connected to the water inlet and the water outlet of the backup heat exchanger.
  • the second backup line 19 is connected at one end to the bottom of the lower water injection tank 3, the other end is connected to the first standby line 18 upstream of the backup stack water pump 701, and the second standby line 19 is provided with a third backup isolation valve 501. .
  • Third backup isolation valve on the second backup line 19 A check valve is provided downstream of the 501.
  • a spray line is connected downstream of the fifth isolation valve 5 on the low water injection pipe 17, and the other end of the spray line is connected with the safety shell spray system, and the spray line is used as a bypass to the safety shell under accident conditions.
  • Spraying at the same time, a backup spray line is connected downstream of the third backup isolation valve 501 on the second backup line 19, and the other end of the backup spray line is connected to the safety shell spray system, the spare spray The pipeline is used as a backup;
  • the discharge window 20 is horizontally higher than the lower header tank 3.
  • the reactor water injection cooling system of the present invention is isolated under the normal operation of the unit and the design basis accident, and the stage is not put into operation.
  • the system is manually put into operation by the operator when a serious accident causes the core to melt.
  • the reactor water injection cooling system of the present invention is put into operation when a serious accident causes the core to melt.
  • the operator manually opens the first isolation valve 9, the fourth isolation valve 8 and the fifth isolation valve 5 according to the core outlet temperature signal, starts the stack injection pump 7, takes water from the lower injection tank 3 and injects into the outer wall of the reactor pressure vessel 1 and Between the heat insulating barriers 2, the outer wall of the reactor pressure vessel 1 is cooled, and the cooled water flows back through the discharge window 20 to the lower header tank 3 for circulation operation.
  • the temperature of the cooling water is continuously increased due to being heated, and the heat exchange outlet pipe and the heat exchange inlet pipe connected to the heat exchanger in the stack water injection cooling system can be manually opened by the operator, and the heat exchanger can be It is a heat exchanger of the safety shell sprinkler system; the fourth isolation valve 8 on the external water injection pipe 15 is closed, and the water sucked by the low water injection tank 3 is cooled by the heat exchanger and then injected into the reactor cavity 13; the external water source 14
  • the reactor stack chamber 13 can be filled with water together with the low water injection tank 3; specifically, when the low water injection tank 3 fails or is low When the position water injection pipe 17 or the second backup line 19 fails, the fifth isolation valve 5 and the third backup isolation valve 501 are closed, the second isolation valve 10 is opened, and the reactor stack chamber 13 is filled with water by the external water source 14.
  • the third isolation valve 11 of the high water injection pipe 16 at the lower end of the high water injection tank 4 in the containment can be opened, and the water in the high water injection tank 4 is injected into the reactor cavity 13 through the external water injection pipe 15 by gravity, and is submerged.
  • the reactor stack 13 is brought to a certain height to achieve continuous flooding of the reactor stack 13 and continuous cooling of the outer wall of the reactor pressure vessel 1.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

本发明涉及一种核电站堆腔注水冷却系统，包括：设置在反应堆安全壳内的反应堆堆腔、设置在反应堆堆腔内的压力容器，位于反应堆堆腔与压力容器之间并包围压力容器的隔热屏障，还包括外部注水系统和设置在安全壳内的高位注水系统；外部注水系统包括外部水源、与外部水源连接的外部注水管、在外部注水管上设置的堆腔注水泵、在堆腔注水泵上游和下游分别设置的第一隔离阀和第二隔离阀；该外部注水管穿过安全壳与隔热屏障底部连接；高位注水系统包括高位注水箱、连接高位注水箱底部与外部注水管的高位注水管、设置在高位注水管上的第三隔离阀。本发明性能稳定可靠，可以有效地缓解严重事故后果，确保严重事故下反应堆压力容器的完整性。

Description

M 明 书
一种核电站堆腔注水冷却系统
技术领域
本发明涉及一种冷却系统，具体涉及一种应用于核电站事故情况 下， 进行事故应对及缓解的堆腔注水冷却系统。 景
针对压水堆核电站严重事故， 目前国际上采取了很多缓解措施， 在电厂发生堆芯融化的严重事故时， 目前较新的技术为熔融物堆内滞 留措施（ IVR )。熔融物堆内滞留措施是一种核电站严重事故缓解措施， 即在压水堆核电厂（站）发生堆芯熔化的严重事故时， 通过反应堆压 力容器外部冷却， 将堆内热量导出， 实现堆芯熔融物滞留， 确保反应 堆压力容器的完整性。 在美国 AP600/1000堆型中已经采用该技术缓 解严重事故后果。 其设计特点为： 在严重事故发生后， 安全壳内换料 水箱中的水作为冷却水， 依靠重力， 以非能动的方式注入堆腔， 淹没 反应堆压力容器下封头及一定高度的筒体，冷却水在以反应堆压力容 器及其保温层之间流道中流过并冷却反应堆压力容器外壁面，被加热 形成蒸汽后通过保温层上部的开孔返回安全壳空间。这种设计的缺点 是仅有一种 "非能动"注入淹没的冷却手段， 注入水流量较小， 无法 实现高效的换热； 并且缺少有效的对冷却水的冷却， 难以保证系统运 行后期的换热效果。 发明内容
本发明要解决的技术问题是提供一种在核电站发生堆芯融化的 严重事故时，能够以能动与非能动相结合的冷却水注入方式冷却反应 堆压力容器外壁面， 从而将堆芯熔融物滞留在反应堆压力容器中， 防 止可能威胁安全壳完整性的堆腔注水冷却系统。
为了解决上述技术问题， 本发明的技术方案为， 一种核电站堆腔 注水冷却系统， 包括： 设置在反应堆安全壳内的反应堆堆腔、 设置在 反应堆堆腔内的压力容器，位于反应堆堆腔与压力容器之间并包围压 力容器的隔热屏障，还包括外部注水系统和设置在安全壳内的高位注 水系统；
所述外部注水系统包括外部水源、与所述外部水源连接的外部注 水管、在所述外部注水管上设置的堆腔注水泵； 该外部注水管穿过安 全壳与隔热屏障底部连接；
所述高位注水系统包括高位注水箱、连接所述高位注水箱底部与 外部注水管的高位注水管。
进一步所述外部水源位于安全壳外侧的消防水源。
进一步还包括在所述堆腔注水泵上游和下游分别设置的第一隔 离阀和第二隔离阀， 以及设置在所述高位注水管上的第三隔离阀。
进一步还包括设置在安全壳外侧的换热器、设置在所述堆腔注水 泵与第一隔离阀之间的第四隔离阀、连接在所述堆腔注水泵与该第四 隔离阀之间的外部注水管上的换热出水管、连接在所述第一隔离阀与 该第四隔离阀之间的外部注水管上的换热进水管，所述换热出水管和 换热进水管分别与所述换热的进水口和出水口连接。
进一步还包括第一备用管路，所述第一备用管路上从上游至下游 依次设置有第一备用隔离阀和备用堆腔注水泵，该第一备用管路与连 接第一隔离阀和堆腔注水泵的外部注水管并联连接。
进一步还包括设置在安全壳外侧的备用换热器、设置在所述备用 堆腔注水泵与第一隔备用离阀之间的第二备用隔离阀、连接在所述备 用堆腔注水泵与该第二备用隔离阀之间的第一备用管路上的备用换 热出水管、连接在所述第一备用隔离阀与该第二备用隔离阀之间的第 一备用管路上的备用换热进水管，所述备用换热出水管和备用换热进 水管分别与所述备用换热器的进水口和出水口连接。
进一步还包括低位注水系统，所述低位注水系统包括设置在安全 壳内底部的低位注水箱、 与所述低位注水箱底部连接的低位注水管、 设置在所述低位注水管上的第五隔离阀，所述低位主水管连接到所述 堆腔注水泵与第二隔离阀之间的外部注水管上。
进一步还包括第二备用管路，所述第二备用管路上设置有第三备 用隔离阀， 该第二备用管路一端连接到低位注水箱底部， 另一端连接 到备用堆腔注水泵上游的第一备用管路上。
进一步在第二隔离阀与低位注水管和外部注水管连接处之间的 消防管上设置有止回阀，在安全壳内第一隔离阀与高位注水管和外部 注水管连接处之间的外部注水管上设置有止回阀，在第四隔离阀与高 位注水管和外部注水管连接处之间的高位注水管上设置有止回阀，在 第五隔离阀与低位注水管和外部注水管连接处之间的低位注水管上 设置有止回阀，在第二备用管路上第三备用隔离阀的下游设置有止回 阀。 进一步所述隔热屏障支撑在堆腔内，该隔热屏障与压力容器之间 形成一个空腔， 所述空腔与堆腔顶部结合处设有排放窗口， 所述排放 窗口水平高度高于低位注水箱。
本发明的有益效果： 该系统采取能动与非能动相结合的注水方 式， 性能稳定可靠， 可以有效地缓解严重事故后果， 确保严重事故下 反应堆压力容器的完整性。
附图说明
图 1为本发明一种压水堆核电站堆腔注水冷却系统示意图； 图中： 1-压力容器， 2-隔热屏障， 3-低位注水箱， 4-高位注水箱， 5-第五隔离阀， 501-第三备用隔离阀， 6-止回阀， 7-堆腔注水泵， 8- 第四隔离阀， 801-第二备用隔离阀， 9-第一隔离阀， 901-第一备用隔 离阀， 10-第二隔离阀， 11-第三隔离阀， 12-反应堆安全壳， 13-反应 堆堆腔， 14-外部水源， 15-外部注水管， 16-高位注水管， 17-低位注 水管， 18-第一备用管路， 19-第二备用管路， 20-排放窗口。
具体实施方式
以下结合图 1和实施例对本发明做进一步描述。
如图 1所示本发明一种压水堆核电站堆腔注水冷却系统，在反应 堆安全壳 12内设置反应堆堆腔 13，压力容器 1设置在反应堆堆腔 13 内， 隔热屏障 2位于反应堆堆腔 13与压力容器 1之间并包围压力容 器 1， 高位注水系统设置在安全壳 12内； 隔热屏障 2的结构可以采 用目前公知的 AP1000的设计方案， 隔热屏障 2支撑在反应堆堆腔 13 内， 其与压力容器之间形成一个空腔， 该空腔与堆腔顶部结合处设有 排放窗口 20。
本发明的堆腔注水冷却系统中还设置有外部注水系统，该外部注 水系统包括外部水源 14、 与所述外部水源 14连接的外部注水管 15、 在所述外部注水管 15上设置的堆腔注水泵 7、 在所述堆腔注水泵 7 上游和下游分别设置的第一隔离阀 9和第二隔离阀 10; 该外部注水 管 15穿过安全壳 12并进入反应堆堆腔 13内与隔热屏障 2底部连接; 上述的外部水源 14可以是设置在安全壳外的消防水源。
高位注水系统包括高于堆芯高度设置的高位注水箱 4、 连接所述 高位注水箱 4底部与进入安全壳 12内的外部注水管 15的高位注水管 16、 设置在所述高位注水管 16上的第三隔离阀 11。 所述第三隔离阀 11可以是由两个或多个并联的隔离阀构成的隔离阀组。
换热器设置在安全壳 12外侧， 第四隔离阀 8设置在所述堆腔注 水泵 7与第一隔离阀 9之间的外部注水管 15的管段上， 换热出水管 一端连接在所述堆腔注水泵 7与该第四隔离阀 8之间的外部注水管 15上， 换热进水管一端连接在所述第一隔离阀 9与该第四隔离阀 8 之间的外部注水管 15上， 所述换热出水管和换热进水管的另一端分 别与所述换热的进水口和出水口连接。
本发明的堆腔注水冷却系统中还设置有低位注水系统，所述低位 注水系统包括设置在安全壳内底部的低位注水箱 3、 与所述低位注水 箱 3底部连接的低位注水管 17、 设置在所述低位注水管 17上的第五 隔离阀 5， 所述低位注水管 17连接到所述堆腔注水泵 7与第二隔离 阀 10之间的外部注水管 15上。 在第二隔离阀 10与低位注水管 17和外部注水管 15连接处之间 的外部注水管 15上设置有止回阀 6， 在安全壳 12内第一隔离阀 9与 高位注水管 16和外部注水管 15连接处之间的外部注水管 15上设置 有止回阀 6， 在第四隔离阀 11与高位注水管 16和外部注水管 15连 接处之间的高位注水管 16上设置有止回阀 6， 在第五隔离阀 5与低 位注水管 17和外部注水管 15连接处之间的低位注水管 17上设置有 止回阀 6。
在第一备用管路 18上从上游至下游依次设置有第一备用隔离阀 901和备用堆腔注水泵 701， 该第一备用管路 18与连接第一隔离阀 9 和堆腔注水泵 7的外部注水管 15并联连接， 即其一端连接到第一隔 离阀 9的下游， 另一端连接到堆腔注水泵 7和第二隔离阀 10下游的 止回阀 6之间。
在安全壳 12外侧还设置有备用换热器； 第二备用隔离阀 801设 置在所述备用堆腔注水泵 701与第一备有隔离阀 901之间，备用换热 出水管一端连接在所述备用堆腔注水泵 701与该第二备用隔离阀 801 之间的第一备用管路上，备用换热进水管一端连接在所述第一备用隔 离阀 901与该第二备用隔离阀 801之间的第一备用管路 18上， 所述 备用换热出水管和备用换热进水管的另一端分别与所述备用换热器 的进水口和出水口连接。
第二备用管路 19一端连接到低位注水箱 3底部， 另一端连接到 备用堆腔注水泵 701上游的第一备用管路 18上，第二备用管路 19上 设置有第三备用隔离阀 501。 在第二备用管路 19上第三备用隔离阀 501的下游设置有止回阀。
在低位注水管 17上第五隔离阀 5下游连接有喷淋管路， 该喷淋 管路另一端与安全壳喷淋系统连接，该喷淋管路作为旁路在事故工况 下对安全壳进行喷淋； 同时， 在备第二备用管路 19上第三备用隔离 阀 501下游连接有备用喷淋管路，该备用喷淋管路另一端与安全壳喷 淋系统连接， 该备用喷淋管路作为备用；
本发明中排放窗口 20水平高度高于低位注水箱 3。
在机组正常运行和设计基准事故下本发明的堆腔注水冷却系统 被隔离， 级不投入运行。在严重事故发生导致堆芯熔化时由操作员手 动投入该系统。
在严重事故发生导致堆芯熔化时，本发明堆腔注水冷却系统投入 运行。 操纵员根据堆芯出口温度信号， 手动打开第一隔离阀 9、 第四 隔离阀 8和第五隔离阀 5， 启动堆腔注水泵 7， 从低位注水箱 3取水 并注入反应堆压力容器 1外壁和隔热屏障 2之间，对反应堆压力容器 1外壁进行冷却， 冷却后的水通过所述排放窗口 20流回至低位注水 箱 3中， 进行循环运行。
系统运行过程中， 冷却水由于被加热而温度持续升高， 可由操作 员手动开启该堆腔注水冷却系统中的与换热器相连的换热出水管和 换热进水管， 该换热器可以是安全壳喷淋系统的换热器； 关闭外部注 水管 15上的第四隔离阀 8， 由低位注水箱 3吸入的水经过换热器的 冷却后再注入反应堆堆腔 13中； 外部水源 14可以配合低位注水箱 3 一起对反应堆堆腔 13进行注水； 具体地， 当低位注水箱 3失效或低 位注水管 17或第二备用管路 19失效时，关闭第五隔离阀 5和第三备 用隔离阀 501， 打开第二隔离阀 10， 利用外部水源 14对反应堆堆腔 13进行注水。
当机组丧失全部电源，可开启安全壳内高位注水箱 4下端的高位 注水管 16的第三隔离阀 11， 高位注水箱 4内的水依靠重力通过外部 注水管 15注入反应堆堆腔 13， 并淹没反应堆堆腔 13到一定高度， 实现对反应堆堆腔 13的持续淹没和反应堆压力容器 1外壁的持续冷 却。

Claims

禾'」 要
1、 一种核电站堆腔注水冷却系统， 包括： 设置在反应堆安全壳 内的反应堆堆腔、设置在反应堆堆腔内的压力容器， 位于反应堆堆腔 与压力容器之间并包围压力容器的隔热屏障， 其特征在于： 还包括外 部注水系统和设置在安全壳内的高位注水系统；
所述外部注水系统包括外部水源、与所述外部水源连接的外部注 水管、在所述外部注水管上设置的堆腔注水泵； 该外部注水管穿过安 全壳与隔热屏障底部连接；
所述高位注水系统包括高位注水箱、连接所述高位注水箱底部与 外部注水管的高位注水管。
2、 按照权利要求 1所述的核电站堆腔注水冷却系统， 其特征在 于： 所述外部水源为位于安全壳外侧的消防水源。
3、 按照权利要求 1所述的核电站堆腔注水冷却系统， 其特征在 于：还包括在所述堆腔注水泵上游和下游分别设置的第一隔离阀和第 二隔离阀， 以及设置在所述高位注水管上的第三隔离阀。
4、 按照权利要求 3所述的核电站堆腔注水冷却系统， 其特征在 于： 还包括设置在安全壳外侧的换热器、设置在所述堆腔注水泵与第 一隔离阀之间的第四隔离阀、连接在所述堆腔注水泵与该第四隔离阀 之间的外部注水管上的换热出水管、连接在所述第一隔离阀与该第四 隔离阀之间的外部注水管上的换热进水管，所述换热出水管和换热进 水管分别与所述换热的进水口和出水口连接。
5、 按照权利要求 1所述的核电站堆腔注水冷却系统， 其特征在 于： 还包括第一备用管路， 所述第一备用管路上从上游至下游依次设 置有第一备用隔离阀和备用堆腔注水泵，该第一备用管路与连接第一 隔离阀和堆腔注水泵的外部注水管并联连接。
6、 按照权利要求 5所述的核电站堆腔注水冷却系统， 其特征在 于： 还包括设置在安全壳外侧的备用换热器、设置在所述备用堆腔注 水泵与第一隔备用离阀之间的第二备用隔离阀、连接在所述备用堆腔 注水泵与该第二备用隔离阀之间的第一备用管路上的备用换热出水 管、连接在所述第一备用隔离阀与该第二备用隔离阀之间的第一备用 管路上的备用换热进水管，所述备用换热出水管和备用换热进水管分 别与所述备用换热器的进水口和出水口连接。
7、 按照权利要求 6所述的核电站堆腔注水冷却系统， 其特征在 于： 还包括低位注水系统， 所述低位注水系统包括设置在安全壳内底 部的低位注水箱、与所述低位注水箱底部连接的低位注水管、设置在 所述低位注水管上的第五隔离阀，所述低位主水管连接到所述堆腔注 水泵与第二隔离阀之间的外部注水管上。
8、 按照权利要求 7所述的核电站堆腔注水冷却系统， 其特征在 于： 还包括第二备用管路， 所述第二备用管路上设置有第三备用隔离 阀， 该第二备用管路一端连接到低位注水箱底部， 另一端连接到备用 堆腔注水泵上游的第一备用管路上。
9、 按照权利要求 8所述的核电站堆腔注水冷却系统， 其特征在 于：在第二隔离阀与低位注水管和外部注水管连接处之间的消防管上 设置有止回阀，在安全壳内第一隔离阀与高位注水管和外部注水管连 接处之间的外部注水管上设置有止回阀，在第四隔离阀与高位注水管 和外部注水管连接处之间的高位注水管上设置有止回阀，在第五隔离 阀与低位注水管和外部注水管连接处之间的低位注水管上设置有止 回阀， 在第二备用管路上第三备用隔离阀的下游设置有止回阀。
10、按照权利要求 1所述的核电站堆腔注水冷却系统， 其特征在 于： 所述隔热屏障支撑在堆腔内， 该隔热屏障与压力容器之间形成一 个空腔， 所述空腔与堆腔顶部结合处设有排放窗口， 所述排放窗口水 平高度高于低位注水箱。
PCT/CN2013/081727 2012-08-20 2013-08-19 一种核电站堆腔注水冷却系统 WO2014029305A1 (zh)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB1504123.9A GB2520215B (en) 2012-08-20 2013-08-19 A water flooding system for cooling a nuclear power plant reactor cavity

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201210295150.0A CN103632736B (zh) 2012-08-20 2012-08-20 一种核电站堆腔注水冷却系统
CN201210295150.0 2012-08-20

Publications (1)

Publication Number Publication Date
WO2014029305A1 true WO2014029305A1 (zh) 2014-02-27

Family

ID=50149432

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CN2013/081727 WO2014029305A1 (zh) 2012-08-20 2013-08-19 一种核电站堆腔注水冷却系统

Country Status (3)

Country Link
CN (1) CN103632736B (zh)
GB (1) GB2520215B (zh)
WO (1) WO2014029305A1 (zh)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105741887A (zh) * 2014-12-11 2016-07-06 中广核工程有限公司 核电站非能动堆腔注水系统及方法
CN111720201A (zh) * 2020-07-23 2020-09-29 中船动力有限公司 柴油发电机冷却水供水系统

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104183285B (zh) * 2014-08-12 2017-11-24 中国核电工程有限公司 一种反应堆压力容器外部冷却系统
CN105895172A (zh) * 2014-12-26 2016-08-24 姚明勤 压水堆非能动安全的快速有效设计措施
CN104766637B (zh) * 2015-04-01 2017-03-29 中广核研究院有限公司 安全注入成套系统
CN105047235B (zh) * 2015-06-09 2017-12-29 中国核动力研究设计院 核反应堆严重事故状态下熔融物堆内滞留非能动冷却系统
CN106803436B (zh) * 2015-11-26 2018-08-17 大亚湾核电运营管理有限责任公司 核电厂后备事故缓解电源事故应用功能的验证方法及装置
CN107945891B (zh) * 2017-10-19 2021-01-19 中国核电工程有限公司 一种具有反应堆堆芯熔融物堆内滞留和堆外滞留功能的系统
WO2022047622A1 (zh) * 2020-09-01 2022-03-10 中广核研究院有限公司 一种核电站熔融物堆内滞留系统
CN112489842A (zh) * 2020-11-04 2021-03-12 中国核电工程有限公司 一种堆腔注水冷却系统能动执行机构的组合报警方法
CN113205893B (zh) * 2021-04-02 2022-03-22 中国核电工程有限公司 一种核电站堆芯淹没水池的布置方法及系统

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4950448A (en) * 1989-05-11 1990-08-21 General Electric Company Passive heat removal from containment
US5349616A (en) * 1992-04-30 1994-09-20 Hitachi, Ltd. Reactor cooling system for boiling water reactors
CN201570286U (zh) * 2009-11-25 2010-09-01 中科华核电技术研究院有限公司 一种用于核电系统的堆腔注水系统
CN102169733A (zh) * 2011-02-14 2011-08-31 中国核电工程有限公司 一种核电站非能动与能动相结合的专设安全系统

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0242393A (ja) * 1988-08-03 1990-02-13 Toshiba Corp 原子炉の非常用炉心冷却装置
JPH03274493A (ja) * 1990-03-26 1991-12-05 Toshiba Corp 原子炉非常時冷却装置
JP2002122689A (ja) * 2000-10-17 2002-04-26 Toshiba Corp 沸騰水型原子力発電プラント
JP2004061192A (ja) * 2002-07-25 2004-02-26 Toshiba Corp 原子力発電設備
JP4385218B2 (ja) * 2003-12-09 2009-12-16 日立Ｇｅニュークリア・エナジー株式会社 原子炉注水設備
CN201689688U (zh) * 2010-06-04 2010-12-29 中科华核电技术研究院有限公司 堆芯冷却、堆腔充水及安全壳热量导出的系统
CN201698776U (zh) * 2010-06-04 2011-01-05 中科华核电技术研究院有限公司 用于核电站的可连续运行的安注及喷淋系统
CN102034559B (zh) * 2010-09-19 2012-08-01 中广核工程有限公司 一种核电站的快速互备系统及其互备方法
CN202102729U (zh) * 2011-05-06 2012-01-04 中科华核电技术研究院有限公司 备用堆芯冷却与堆腔充水系统
CN202217513U (zh) * 2011-08-18 2012-05-09 中广核工程有限公司 核电站压力容器保温层的预埋支撑装置

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4950448A (en) * 1989-05-11 1990-08-21 General Electric Company Passive heat removal from containment
US5349616A (en) * 1992-04-30 1994-09-20 Hitachi, Ltd. Reactor cooling system for boiling water reactors
CN201570286U (zh) * 2009-11-25 2010-09-01 中科华核电技术研究院有限公司 一种用于核电系统的堆腔注水系统
CN102169733A (zh) * 2011-02-14 2011-08-31 中国核电工程有限公司 一种核电站非能动与能动相结合的专设安全系统

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105741887A (zh) * 2014-12-11 2016-07-06 中广核工程有限公司 核电站非能动堆腔注水系统及方法
CN105741887B (zh) * 2014-12-11 2017-11-14 中广核工程有限公司 核电站非能动堆腔注水系统及方法
CN111720201A (zh) * 2020-07-23 2020-09-29 中船动力有限公司 柴油发电机冷却水供水系统
CN111720201B (zh) * 2020-07-23 2023-09-01 中船动力有限公司 柴油发电机冷却水供水系统

Also Published As

Publication number Publication date
GB2520215A (en) 2015-05-13
GB2520215B (en) 2018-04-18
GB201504123D0 (en) 2015-04-22
CN103632736B (zh) 2016-08-10
CN103632736A (zh) 2014-03-12

Similar Documents

Publication Publication Date Title
WO2014029305A1 (zh) 一种核电站堆腔注水冷却系统
CN102163469B (zh) 一种核电站非能动专设安全系统
CN102169733B (zh) 一种核电站非能动与能动相结合的专设安全系统
CN202887746U (zh) 一种核电站能动与非能动结合的堆芯剩余热量排出系统
CN201689688U (zh) 堆芯冷却、堆腔充水及安全壳热量导出的系统
WO2014048290A1 (zh) 一种能动与非能动相结合的堆腔注水冷却系统
KR101242743B1 (ko) 일체형 피동안전탱크를 이용한 일체형 원자력 발전 시스템
CN103295656A (zh) 用于核反应堆的多样化专设安全系统
CN106328223B (zh) 一种新型非能动安全壳能量控制系统
WO2014048292A1 (zh) 一种能动与非能动相结合的堆芯注水热量导出装置
CN104103325B (zh) 一种长期非能动安全壳热量导出系统
CN104143361A (zh) 无源安全壳喷淋系统
CN201788707U (zh) 一种用于保证核电站安全的安全系统
CN104021824B (zh) 核电站事故后堆内熔融物滞留系统
CN202332312U (zh) 利用非能动换热预防反应堆压力容器熔穿的应急保护装置
CN201698776U (zh) 用于核电站的可连续运行的安注及喷淋系统
WO2024002383A1 (zh) 浸没式储能电池热管理系统及消防控制方法
WO2015010399A1 (zh) 核电站堆腔注水系统及方法
CN102306507B (zh) 一种预防反应堆压力容器熔穿的应急保护系统
CN203839055U (zh) 一种非能动安全壳外侧冷却系统
CN202102729U (zh) 备用堆芯冷却与堆腔充水系统
CN205541969U (zh) 压水堆非能动保护系统以及压差自力阀
CN205751539U (zh) 一种核电站的非能动专设安全设施
CN104036833B (zh) 具有导热堆坑外墙的核电站事故后堆内熔融物滞留系统
CN204010703U (zh) 一种能动、非能动结合的安全壳地坑水冷却系统

Legal Events

Date Code Title Description
121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 13831492

Country of ref document: EP

Kind code of ref document: A1

NENP Non-entry into the national phase

Ref country code: DE

ENP Entry into the national phase

Ref document number: 1504123

Country of ref document: GB

Kind code of ref document: A

Free format text: PCT FILING DATE = 20130819

WWE Wipo information: entry into national phase

Ref document number: 1504123.9

Country of ref document: GB

122 Ep: pct application non-entry in european phase

Ref document number: 13831492

Country of ref document: EP

Kind code of ref document: A1