WO2015010399A1 - 核电站堆腔注水系统及方法 - Google Patents

核电站堆腔注水系统及方法 Download PDF

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Publication number
WO2015010399A1
WO2015010399A1 PCT/CN2013/087739 CN2013087739W WO2015010399A1 WO 2015010399 A1 WO2015010399 A1 WO 2015010399A1 CN 2013087739 W CN2013087739 W CN 2013087739W WO 2015010399 A1 WO2015010399 A1 WO 2015010399A1
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Prior art keywords
water injection
water
reactor
stack
nuclear power
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PCT/CN2013/087739
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English (en)
French (fr)
Inventor
咸春宇
黄威
魏淑虹
张国庆
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中广核工程有限公司
中国广核集团有限公司
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Publication of WO2015010399A1 publication Critical patent/WO2015010399A1/zh

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    • 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
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • 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 nuclear power plant stack cavity water injection system and method, and more particularly to a passive and active nuclear power plant stack cavity water injection system and method. Background technique
  • the design concept of retention in the pressure vessel is as follows: After the core melts and collapses to the lower end of the pressure vessel, the lower head of the pressure vessel is immersed in the cold water of the stack by means of water injection in the stack, and is cooled by the outside of the pressure vessel. Severe accident management measures ensure the integrity of the pressure vessel and retain the melt in the pressure vessel.
  • the external retention of the pressure vessel is such that after the pressure vessel is melted through, the core melt is introduced into the core trap located at the lower part of the stack outside the pressure vessel or on the side of the stack, and then passive means are used to promote the retention of the melt.
  • the core melt is cooled by the means of lower cooling and upper submerging, preventing the bottom plate from being melted by the reaction between the molten material and the concrete shell floor concrete, thereby avoiding damage to the integrity of the safety shell, thereby avoiding The resulting fission product release and the consequences of groundwater contamination.
  • the external detention of the pressure vessel mainly includes the melt expansion scheme and the core trap scheme. Both of the technical schemes have high reliability, but the reliability of the equipment is high and the cost is high. Therefore, the pressure vessel internal retention scheme for reactor water injection has received widespread attention in various innovative passive and even active reactors.
  • the existing active cavity injection system is a serious accident at the nuclear power plant, and the core melt falls into the reaction.
  • the pressure vessel is closed under the head, the outside of the pressure vessel is cooled by pumping water from the dedicated pool into the stack chamber.
  • the cavity injection is simultaneously operated with other safety functions (such as primary circuit relief) to maintain the integrity of the pressure vessel, and to retain the core melt debris in the pressure vessel to prevent most of the reactors that may threaten the integrity of the containment.
  • Phenomena such as direct heating of the containment, steam explosion, melt-concrete reaction, etc.
  • the above-mentioned stack cavity water injection system mainly injects cooling water into the stack cavity through the active equipment pump, and the probability of successful water injection is extremely high, but the realization of the system function largely depends on the reliability of the pump operation, and the early stage of the accident is not considered.
  • the passive means so the reliability is poor.
  • the object of the present invention is to provide a highly reliable nuclear power plant stack cavity water injection system and method.
  • the present invention provides a nuclear power plant reactor cavity water injection system comprising two subsystems: a passive reactor cavity water injection and an active reactor cavity water injection.
  • the passive reactor water injection subsystem comprises a special water tank and a water injection pipeline disposed between the special water tank and the stack chamber, and the water injection pipeline is provided with an openable and closed valve.
  • the special water tank is disposed in the safety shell or outside the safety shell, and the boron water is stored therein, and the position and water level of the special water tank ensure that it can pass the gravity into the reactor cavity. Inject enough water to submerge the lower head of the pressure vessel.
  • the water injection pipeline of the passive reactor water injection subsystem comprises a large flow water injection pipeline and a d flow water injection pipeline, and the two water injection pipelines can be used simultaneously or separately.
  • one end of the large flow water injection pipe is connected to the side of the special water tank, and the other end is connected to the bottom of the pile cavity, and the large flow water injection pipe is provided with an electric valve that can be opened and closed. .
  • one end of the small flow water injection pipe It is connected to the bottom of the special water tank, and the other end is connected to the bottom of the stacking chamber.
  • the small-flow water injection pipe is provided with an electric valve that can be opened and closed.
  • the active reactor water injection subsystem comprises an active stack water injection line and a water injection pump and an electric isolation valve disposed on the active pile water injection line.
  • the active reactor water injection line is connected between the stack chamber and the displacement tank in the containment.
  • the stack cavity is provided with a stack liquid level monitoring instrument for monitoring the water level of the stack.
  • the present invention also provides a method for water injection in a nuclear power plant, in which, in the event of a serious accident, the two subsystems of the passive reactor water injection and the active reactor water injection are used, and the water injection by the combination of passive and active In a manner, a sufficient amount of water is injected into the reactor cavity to perform cooling of the pressure vessel.
  • the passive injection cavity water injection subsystem is first opened, and the boron-containing water is injected into the reactor cavity in a passive manner, thereby rapidly establishing an early stage in the heap cavity.
  • the water level maintains the early water level; when the water volume of the passive reactor water injection subsystem is insufficient, the active reactor water injection subsystem is activated to inject boron-containing water into the reactor cavity in an active manner.
  • the passive reactor water injection subsystem comprises a special water tank and a water injection pipeline disposed between the special water tank and the stack chamber, and the water injection pipeline is provided with an openable and closable valve.
  • the special water tank is disposed in the safety shell or outside the safety shell, and the boron water is stored therein, and the position and water level of the special water tank ensure that it can pass the gravity into the reactor cavity. Inject enough water to submerge the lower head of the pressure vessel.
  • a passive large-flow water injection is performed into the reactor cavity; after the early water level is quickly established, the large-flow water injection is turned off, and only the passive small-flow is performed into the reactor cavity.
  • the flow is filled with water to replenish the amount of water in the stack due to heat transfer.
  • the water injection pipeline of the passive reactor water injection subsystem comprises a large flow water injection pipeline and a d flow irrigation water pipeline, and the two water injection pipelines can be used simultaneously or separately;
  • two injection water pipes are used to perform passive large-flow water injection into the reactor cavity. After the early water level is established quickly, the large-flow water injection pipeline is closed, and only the small-flow water injection pipeline is used to perform the passive small-flow water injection into the reactor cavity. .
  • one end of the large-flow water injection pipe is connected to the side of the special water tank, and the other end is connected to the bottom of the pile cavity, and the large-flow water injection pipe is provided with an electric valve that can be opened and closed. .
  • one end of the small-flow water injection pipe is connected to the bottom of the special water tank, and the other end is connected to the bottom of the stack cavity, and the small-flow water injection pipe is provided with an electric valve that can be opened and closed. .
  • the active water injection subsystem of the active reactor is activated, and the reactor cavity is actively moved into the reactor cavity. Inject boron-containing water.
  • the active stack cavity water injection subsystem comprises an active stack water injection pipeline and a water injection pump and an electric isolation valve disposed on the active stack water injection line;
  • the steps of the system include starting the water injection pump and opening the electric isolation valve on the active stack water line.
  • the active reactor water injection line is connected between the stack chamber and the displacement tank in the containment.
  • a stack liquid level monitoring instrument for monitoring the water level of the stack is provided on the stack chamber.
  • the nuclear power plant water injection system and method of the invention adopts a combination of passive and active water injection mode, which ensures the early passive cavity inundation and cooling, and can ensure long-term water injection cooling. Better maintain pressure vessels while ensuring a high probability of successful water injection The integrity of the containment greatly reduces the possibility of failure of the containment.
  • FIG. 1 is a schematic structural view of a nuclear power plant water injection system of the present invention. detailed description
  • the nuclear power plant water injection system of the present invention comprises two subsystems: a passive reactor cavity water injection and a dynamic reactor cavity water injection.
  • the passive reactor water injection subsystem includes a dedicated water tank 10, a large flow water injection conduit 16 and a small flow water injection conduit 12.
  • the special water tank 10 is disposed in the safety shell or outside the safety shell, and contains boron-containing water therein. The position and water level of the special water tank 10 ensure that it can be injected into the stack chamber 20 by gravity enough to immerse the lower head of the pressure vessel 22. The amount of water.
  • One end of the large flow water injection pipe 16 is connected to the side of the dedicated water tank 10, and the other end is connected to the bottom of the stack chamber 20.
  • the large flow water injection pipe 16 is provided with an electric valve 15 that can be opened and closed: the electric valve 15 under severe accident conditions Turning on, the boron-containing water in the dedicated water tank 10 can be quickly injected into the stack chamber 20 through the large-flow water injection pipe 16.
  • the small flow water injection pipe 12 is connected to the bottom of the special water tank 10, and the other end is connected to the bottom of the stack chamber 20.
  • the small flow water injection pipe 12 is provided with an electric valve 14 that can be opened and closed: the electric valve 14 is under severe accident conditions.
  • the boron-containing water in the special water tank 10 can be simultaneously injected into the stack chamber 20 through the small-flow water injection pipe 12 and the large-flow water injection pipe 16; after the large-flow injection is completed, the boron-containing water in the special water tank 10 continues to be injected through the small flow rate.
  • the conduit 12 is injected into the stack chamber 20 in a small flow rate to supplement the amount of evaporation of water in the stack chamber 20 due to heat exchange.
  • the active stack water injection subsystem includes an active stack water injection line 30, a water injection pump 32 and an electric isolation valve 34.
  • the active stack water injection line 30 is connected between the stack chamber 20 and the containment water tank 36 in the containment, and the water injection pump 32 and the electric isolation valve 34 are respectively disposed on the active stack water injection line 30.
  • the stack chamber 20 is provided with a stack liquid level monitoring instrument 24 for monitoring the water level of the stack chamber.
  • the electric valves 14 and 15 of the water injection pipes 12 and 16 between the special water tank 10 and the stack chamber 20 are opened, and the pile chamber 20 is injected into the stack chamber 20 in a passive manner.
  • the boron-containing water is used to establish an early water level in the stack chamber 20; after the large-flow injection is completed, the electric valve 15 is closed, and the boron-containing water in the dedicated water tank 10 is injected into the stack chamber 20 through the small-flow water injection conduit 12 in a small flow rate. To supplement the amount of evaporation of water in the stack chamber 20 due to heat transfer.
  • the operator manually activates the active stack cavity water injection subsystem, including releasing the trunk chamber water injection administrative isolation, starting the water injection pump 32, and opening the active stack chamber water injection line 30.
  • the electric isolation valve 34 is configured to actively inject boron-containing water into the reactor stack 20.
  • the nuclear power plant water injection system and method of the present invention combines the water injection method by passively (taking water from the special water tank 10 inside or outside the containment) and the active water (taking water from the replacement tank water tank 36 in the containment).
  • a sufficient amount of water is injected into the reactor cavity 20 for external cooling of the pressure vessel 22, and simultaneously with other safety functions (such as primary circuit pressure relief, etc.) to conduct heat out of the containment to maintain the integrity of the pressure vessel 22.
  • the core melt can be retained in the pressure vessel 22 to prevent most of the extra-pile phenomena (safety shell direct heating, melt-to-concrete reaction, etc.) that may threaten the integrity of the containment.
  • the decay heat of the melt is transmitted through the wall surface of the pressure vessel 22,
  • the water injected into the stack chamber 20 carries heat away from the outer wall surface of the pressure vessel 22.
  • the insulation flow path of the pressure vessel 22 is specifically designed to improve the natural circulation flow characteristics of the cooling water and to improve its heat transfer capability.
  • the nuclear power plant water injection system and method of the invention adopts a combination of passive and active water injection mode, which ensures the early passive cavity flooding and cooling, and ensures long-term water injection cooling, which can ensure In the case of a very high probability of successful water injection, the integrity of the pressure vessel 22 is better maintained, and the possibility of failure of the containment is greatly reduced; even if the pressure vessel 22 fails, the core melt and the concrete can be greatly reduced. It produces a combustible gas, reduces the risk of the containment due to hydrogen explosion, and at the same time washes the fission products released by the core fragments and reduces the amount of radioactive release. It can be seen that the nuclear power injection system of the nuclear power plant of the present invention considers the success probability of water injection, system reliability, construction cost and the like, and the comprehensive performance is obviously superior to the prior art scheme.

Abstract

一种核电站堆腔注水系统及方法，核电站堆腔注水系统包括非能动堆腔注水和能动注水两个子系统；核电站堆腔注水方法是在发生严重事故时，利用非能动堆腔注水和能动堆腔注水两个子系统，通过非能动与能动相结合的注水方式，向反应堆堆腔（20）内注入足够水量而进行压力容器（22）的外部冷却。上述核电站堆腔注水系统及方法既确保了早期非能动的堆腔淹没和冷却，又能保证长期注水冷却，在确保极高的注水成功概率的情况下，更好地保证压力容器的完整性，大大降低了安全壳失效的可能性。

Description

核电站堆腔注水系统及方法 技术领域
本发明涉及一种核电站堆腔注水系统及方法， 更具体地说， 本发明涉及一 种非能动与能动相结合的核电站堆腔注水系统及方法。 背景技术
为了从实际上消除由于底板熔穿导致安全壳后期损坏的严重事故工况， 必 须设置合理的堆芯熔融物滞留稳定和冷却的緩解措施。 目前， 国际上对压力容 器熔穿及熔融物滞留采取压力容器内滞留和压力容器外滞留两种緩解策略。
压力容器内滞留的设计理念为： 在堆芯熔化塌落至压力容器下封头后期， 通过采取堆腔注水等方式使压力容器下封头浸没在堆腔的冷水中， 通过压力容 器外部冷却的严重事故管理措施， 确保压力容器完整性， 将熔融物滞留在压力 容器内。
压力容器外滞留是在压力容器被熔穿后， 把堆芯熔融物导入到位于压力容 器外的堆腔下部或堆腔侧面的堆芯捕集器中， 再采取非能动的手段促使熔融物 滞留在堆芯捕集器内， 并通过下部冷却、 上部淹没的手段实现堆芯熔融物的冷 却， 防止熔融物和安全壳底板混凝土反应引起的底板熔穿， 避免安全壳完整性 受到破坏， 从而避免由此引起的裂变产物释放以及地下水受到污染的后果。
压力容器外滞留主要包括熔融物堆外扩展方案和堆芯捕集器方案， 这两种 技术方案本身均具有较高的可靠性， 但其对设备的可靠性要求较高， 且造价很 高。 因此， 堆腔注水的压力容器内滞留方案在各种革新型非能动乃至能动型反 应堆中得到普遍重视。
现有某能动堆腔注水系统是在核电站发生严重事故、 堆芯熔融物落入反应 堆压力容器下封头时， 通过泵从专用水池向堆腔内注水进行压力容器外部冷却。 堆腔注水与其他安全功能 (如一回路卸压等）同时作用而保持压力容器的完整性， 实现将堆芯熔融物碎片滞留于压力容器内， 以防止大多数可能威胁安全壳完整 性的堆外现象 (如安全壳直接加热、 蒸汽爆炸、 熔融物-混凝土反应等)。
上述堆腔注水系统主要是通过能动设备泵将冷却水注入到堆腔中， 其注水 成功的概率虽然极高， 但是系统功能的实现很大程度上依赖于泵运行的可靠性， 未考虑事故早期的非能动手段， 因此可靠性较差。
有鉴于此， 确有必要提供一种可靠性较高的核电站堆腔注水系统及方法。 发明内容
本发明的目的在于： 提供一种可靠性较高的核电站堆腔注水系统及方法。 为了实现上述发明目的， 本发明提供了一种核电站堆腔注水系统， 其包括 非能动堆腔注水和能动堆腔注水两个子系统。
作为本发明核电站堆腔注水系统的一种改进， 所述非能动堆腔注水子系统 包括专用水箱及设于专用水箱和堆腔之间的注水管道， 注水管道上设置有可开 闭的阀门。
作为本发明核电站堆腔注水系统的一种改进， 所述专用水箱设于安全壳内 或安全壳外， 其内贮存有含硼水， 专用水箱的位置和水位保证其能够通过重力 向堆腔内注入足够将压力容器的下封头浸没的水量。
作为本发明核电站堆腔注水系统的一种改进， 所述非能动堆腔注水子系统 的注水管道包括大流量注水管道和 d、流量注水管道， 两条注水管道可同时使用 或分别单独使用。
作为本发明核电站堆腔注水系统的一种改进， 所述大流量注水管道的一端 连接在专用水箱的侧面， 另一端连接至堆腔的底部， 大流量注水管道上设置有 可开闭的电动阀门。
作为本发明核电站堆腔注水系统的一种改进， 所述小流量注水管道的一端 连接在专用水箱的底部， 另一端连接至堆腔的底部， 小流量注水管道上设置有 可开闭的电动阀门。
作为本发明核电站堆腔注水系统的一种改进， 所述能动堆腔注水子系统包 括能动堆腔注水管线和设于能动堆腔注水管线上的注水泵、 电动隔离阀。
作为本发明核电站堆腔注水系统的一种改进， 所述能动堆腔注水管线连接 于堆腔和安全壳内置换料水箱之间。
作为本发明核电站堆腔注水系统的一种改进， 所述堆腔上设有监测堆腔水 位的堆腔液位监测仪表。
为了实现上述发明目的， 本发明还提供了一种核电站堆腔注水方法， 其在 发生严重事故时， 利用非能动堆腔注水和能动堆腔注水两个子系统， 通过非能 动与能动相结合的注水方式， 向反应堆堆腔内注入足够水量而进行压力容器的 夕卜部冷却。
作为本发明核电站堆腔注水方法的一种改进， 在发生严重事故时， 首先打 开非能动堆腔注水子系统， 通过非能动方式向堆腔内注入含硼水， 从而在堆腔 内快速建立早期水位并维持早期水位； 当非能动堆腔注水子系统水量不足时， 启动能动堆腔注水子系统， 以能动方式向反应堆堆腔内注入含硼水。
作为本发明核电站堆腔注水方法的一种改进， 所述非能动堆腔注水子系统 包括专用水箱及设于专用水箱和堆腔之间的注水管道， 注水管道上设置有可开 闭的阀门。
作为本发明核电站堆腔注水方法的一种改进， 所述专用水箱设于安全壳内 或安全壳外， 其内贮存有含硼水， 专用水箱的位置和水位保证其能够通过重力 向堆腔内注入足够将压力容器的下封头浸没的水量。
作为本发明核电站堆腔注水方法的一种改进， 发生严重事故时， 首先向堆 腔内进行非能动大流量注水； 快速建立早期水位后， 关闭大流量注水， 仅向堆 腔内进行非能动小流量注水， 以补充堆腔内的水因为换热产生的蒸发量。 作为本发明核电站堆腔注水方法的一种改进， 所述非能动堆腔注水子系统 的注水管道包括大流量注水管道和 d、流量注水管道， 两条注水管道可同时使用 或分别单独使用； 发生严重事故时， 首先同时利用两条注水管道向堆腔内进行 非能动大流量注水； 快速建立早期水位后， 关闭大流量注水管道， 仅利用小流 量注水管道向堆腔内进行非能动小流量注水。
作为本发明核电站堆腔注水方法的一种改进， 所述大流量注水管道的一端 连接在专用水箱的侧面， 另一端连接至堆腔的底部， 大流量注水管道上设置有 可开闭的电动阀门。
作为本发明核电站堆腔注水方法的一种改进， 所述小流量注水管道的一端 连接在专用水箱的底部， 另一端连接至堆腔的底部， 小流量注水管道上设置有 可开闭的电动阀门。
作为本发明核电站堆腔注水方法的一种改进， 当非能动堆腔注水子系统的 专用水箱内含硼水液位较低时， 启动能动堆腔注水子系统， 以能动方式向反应 堆堆腔内注入含硼水。
作为本发明核电站堆腔注水方法的一种改进， 所述能动堆腔注水子系统包 括能动堆腔注水管线和设于能动堆腔注水管线上的注水泵、 电动隔离阀； 启动 能动堆腔注水子系统的步骤包括启动注水泵和开启能动堆腔注水管线上的电动 隔离阀。
作为本发明核电站堆腔注水方法的一种改进， 所述能动堆腔注水管线连接 于堆腔和安全壳内置换料水箱之间。
作为本发明核电站堆腔注水方法的一种改进， 所述堆腔上设有监测堆腔水 位的堆腔液位监测仪表。
与现有技术相比， 本发明核电站堆腔注水系统及方法通过采用非能动与能 动相结合的注水方式， 既确保了早期非能动的堆腔淹没和冷却， 又能够保证长 期注水冷却， 可以在确保极高的注水成功概率的情况下， 更好地保持压力容器 的完整性， 大大降低了安全壳失效的可能性。 附图说明
下面结合附图和具体实施方式， 对本发明核电站堆腔注水系统及方法进行 详细说明， 其中：
图 1为本发明核电站堆腔注水系统的结构示意图。 具体实施方式
为了使本发明的发明目的、 技术方案及其有益技术效果更加清晰， 以下结 合附图和具体实施方式， 对本发明进行进一步详细说明。 应当理解的是， 本说 明书中描述的具体实施方式仅仅是为了解释本发明， 并非为了限定本发明。
请参阅图 1 所示， 本发明核电站堆腔注水系统包括非能动堆腔注水和能动 堆腔注水两个子系统。
非能动堆腔注水子系统包括专用水箱 10、大流量注水管道 16和小流量注水 管道 12。 专用水箱 10设于安全壳内或安全壳外， 其内贮存有含硼水， 专用水箱 10的位置和水位保证其能够通过重力向堆腔 20内注入足够将压力容器 22的下 封头浸没的水量。 大流量注水管道 16的一端连接在专用水箱 10的侧面， 另一 端连接至堆腔 20的底部； 大流量注水管道 16上设置有可开闭的电动阀门 15: 电动阀门 15在严重事故工况下打开， 使专用水箱 10内的含硼水能够迅速通过 大流量注水管道 16注入堆腔 20内。
小流量注水管道 12的一端连接在专用水箱 10的底部， 另一端连接至堆腔 20的底部； 小流量注水管道 12上设置有可开闭的电动阀门 14: 电动阀门 14在 严重事故工况下打开， 使专用水箱 10 内的含硼水能够通过小流量注水管道 12 和大流量注水管道 16同时注入堆腔 20内； 大流量注入结束后， 专用水箱 10内 的含硼水继续通过小流量注水管道 12以小流量的方式注入堆腔 20内， 以补充 堆腔 20内的水因为换热产生的蒸发量。 能动堆腔注水子系统包括能动堆腔注水管线 30、 注水泵 32和电动隔离阀 34。 能动堆腔注水管线 30连接于堆腔 20和安全壳内置换料水箱 36之间， 注水 泵 32和电动隔离阀 34分别设于能动堆腔注水管线 30上。
堆腔 20上设有监测堆腔水位的堆腔液位监测仪表 24。
在严重事故工况下， 当堆芯出口温度超过 650°C时， 打开专用水箱 10与堆 腔 20之间注水管道 12、 16的电动阀门 14、 15 , 通过非能动方式向堆腔 20内注 入含硼水， 从而在堆腔 20 内建立早期水位； 大流量注入结束后， 电动阀门 15 关闭， 专用水箱 10内的含硼水仅通过小流量注水管道 12以小流量的方式注入 堆腔 20内， 以补充堆腔 20内的水因为换热产生的蒸发量。 随后， 当专用水箱 10 内的含硼水液位较低时， 由操作员手动启动能动堆腔注水子系统， 包括解除 堆腔注水行政隔离、 启动注水泵 32、开启能动堆腔注水管线 30上的电动隔离阀 34 , 以向反应堆堆腔 20内能动地注入含硼水。
在事故早期阶段， 要求以非能动大流量注入模式将含硼水注入堆腔 20, 在 相当短的时间内将堆腔 20充满水；当堆腔液位监测仪表 24显示堆腔 20满水后， 即转入非能动小流量注入模式以补偿堆腔 20 内水的蒸发损失； 当专用水箱 10 的液位低时， 由操作员手动切换到能动小流量注入模式； 在此后运行过程中， 若堆腔 20内的水位低于整定值， 则切换至能动大流量注入模式向堆腔 20内注 水。
通过以上描述可知， 本发明核电站堆腔注水系统及方法通过非能动 (从安全 壳内或外的专用水箱 10取水)与能动 (从安全壳内置换料水箱 36中取水)相结合 的注水方式， 在假想发生严重事故时， 往反应堆堆腔 20内注入足够水量进行压 力容器 22外部冷却， 并与其他安全功能 (如一回路卸压等)同时作用将热量导出 安全壳而保持压力容器 22的完整性，因此能够将堆芯熔融物滞留于压力容器 22 中， 防止大多数可能威胁安全壳完整性的堆外现象 (安全壳直接加热、 熔融物- 混凝土反应等)。在这个过程中，熔融物的衰变热量通过压力容器 22的壁面传出， 注入堆腔 20的水则从压力容器 22外壁面将热量带走。 压力容器 22的保温层流 道经专门设计以改善冷却水的自然循环流动特性， 提高其传热能力。
与现有技术相比， 本发明核电站堆腔注水系统及方法采用非能动与能动相 结合的注水方式， 既确保了早期非能动的堆腔淹没和冷却， 又能够保证长期注 水冷却， 可以在确保极高的注水成功概率的情况下， 更好地保持压力容器 22的 完整性， 大大降低了安全壳失效的可能性； 即使压力容器 22失效， 也能极大的 减少堆芯熔融物与混凝土相互作用而产生可燃气体， 降低安全壳由于氢气燃爆 而引发的风险， 同时可洗涤由堆芯碎片释放的裂变产物， 降低放射性释放量。 可见， 本发明核电站堆腔注水系统从注水成功概率、 系统可靠性、 建造成本等 多方面考虑， 综合性能都明显优于现有技术方案。
根据上述说明书的揭示和教导， 本发明所属领域的技术人员还可以对上述 实施方式进行适当的变更和修改。 因此， 本发明并不局限于上面揭示和描述的 具体实施方式， 对本发明的一些修改和变更也应当落入本发明的权利要求的保 护范围内。 此外， 尽管本说明书中使用了一些特定的术语， 但这些术语只是为 了方便说明， 并不对本发明构成任何限制。

Claims

权 利 要 求 书
1. 一种核电站堆腔注水系统， 其特征在于： 包括非能动堆腔注水和能动堆 腔注水两个子系统。
2. 根据权利要求 1所述的核电站堆腔注水系统， 其特征在于： 所述非能动 堆腔注水子系统包括专用水箱与设于专用水箱和堆腔之间的注水管道， 注水管 道上设置有可开闭的阀门。
3. 根据权利要求 2所述的核电站堆腔注水系统， 其特征在于： 所述专用水 箱设于安全壳内或安全壳外， 其内贮存有含硼水， 专用水箱的位置和水位保证 其能够通过重力向堆腔内注入足够将压力容器的下封头浸没的水量。
4. 根据权利要求 2所述的核电站堆腔注水系统， 其特征在于： 所述非能动 堆腔注水子系统的注水管道包括大流量注水管道和 d、流量注水管道， 两条注水 管道可同时使用或分别单独使用。
5. 根据权利要求 4所述的核电站堆腔注水系统， 其特征在于： 所述大流量 注水管道的一端连接在专用水箱的侧面， 另一端连接至堆腔的底部， 大流量注 水管道上设置有可开闭的电动阀门。
6. 根据权利要求 4所述的核电站堆腔注水系统， 其特征在于： 所述小流量 注水管道的一端连接在专用水箱的底部， 另一端连接至堆腔的底部， 小流量注 水管道上设置有可开闭的电动阀门。
7. 根据权利要求 2所述的核电站堆腔注水系统， 其特征在于： 所述能动堆 腔注水子系统包括能动堆腔注水管线和设于能动堆腔注水管线上的注水泵、 电 动隔离阀。
8. 根据权利要求 7所述的核电站堆腔注水系统， 其特征在于： 所述能动堆 腔注水管线连接于堆腔和安全壳内置换料水箱之间。
9. 根据权利要求 1至 8中任一项所述的核电站堆腔注水系统，其特征在于： 所述堆腔上设有监测堆腔水位的堆腔液位监测仪表。
10. 一种核电站堆腔注水方法， 其特征在于： 在发生严重事故时， 利用非能 动堆腔注水和能动堆腔注水两个子系统， 通过非能动与能动相结合的注水方式， 向反应堆堆腔内注入足够水量而进行压力容器的外部冷却。
11. 根据权利要求 10所述的核电站堆腔注水方法， 其特征在于： 在发生严 重事故时， 首先打开非能动堆腔注水子系统， 通过非能动方式向堆腔内注入含 硼水， 从而在堆腔内快速建立早期水位并维持早期水位； 当非能动堆腔注水子 系统水量不足时， 启动能动堆腔注水子系统， 以能动方式向反应堆堆腔内注入 含硼水。
12.根据权利要求 11所述的核电站堆腔注水方法， 其特征在于： 所述非能 动堆腔注水子系统包括专用水箱及设于专用水箱和堆腔之间的注水管道， 注水 管道上设置有可开闭的阀门。
13.根据权利要求 12所述的核电站堆腔注水方法， 其特征在于： 所述专用 水箱设于安全壳内或安全壳外， 其内贮存有含硼水， 专用水箱的位置和水位保 证其能够通过重力向堆腔内注入足够将压力容器的下封头浸没的水量。
14.根据权利要求 12所述的核电站堆腔注水方法， 其特征在于： 发生严重 事故时， 首先向堆腔内进行非能动大流量注水； 快速建立早期水位后， 关闭大 流量注水， 仅向堆腔内进行非能动小流量注水， 以补充堆腔内的水因为换热产 生的蒸发量。
15.根据权利要求 14所述的核电站堆腔注水方法， 其特征在于： 所述非能 动堆腔注水子系统的注水管道包括大流量注水管道和小流量注水管道， 两条注 水管道可同时使用或分别单独使用； 发生严重事故时， 首先同时利用两条注水 管道向堆腔内进行非能动大流量注水； 快速建立早期水位后， 关闭大流量注水 管道， 仅利用小流量注水管道向堆腔内进行非能动小流量注水。
16.根据权利要求 15所述的核电站堆腔注水方法， 其特征在于： 所述大流 量注水管道的一端连接在专用水箱的侧面， 另一端连接至堆腔的底部， 大流量 注水管道上设置有可开闭的电动阀门。
17.根据权利要求 15所述的核电站堆腔注水方法， 其特征在于： 所述小流 量注水管道的一端连接在专用水箱的底部， 另一端连接至堆腔的底部， 小流量 注水管道上设置有可开闭的电动阀门。
18.根据权利要求 12所述的核电站堆腔注水方法， 其特征在于： 当非能动 堆腔注水子系统的专用水箱内含硼水液位较低时， 启动能动堆腔注水子系统， 以能动方式向反应堆堆腔内注入含硼水。
19.根据权利要求 18所述的核电站堆腔注水方法， 其特征在于： 所述能动 堆腔注水子系统包括能动堆腔注水管线和设于能动堆腔注水管线上的注水泵、 电动隔离阀； 启动能动堆腔注水子系统的步骤包括启动注水泵和开启能动堆腔 注水管线上的电动隔离阀。
20.根据权利要求 19所述的核电站堆腔注水方法， 其特征在于： 所述能动 堆腔注水管线连接于堆腔和安全壳内置换料水箱之间。
21.根据权利要求 10至 20中任一项所述的核电站堆腔注水方法，其特征在 于： 所述堆腔上设有监测堆腔水位的堆腔液位监测仪表。
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