WO2014048290A1 - 一种能动与非能动相结合的堆腔注水冷却系统 - Google Patents

一种能动与非能动相结合的堆腔注水冷却系统 Download PDF

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Publication number
WO2014048290A1
WO2014048290A1 PCT/CN2013/084040 CN2013084040W WO2014048290A1 WO 2014048290 A1 WO2014048290 A1 WO 2014048290A1 CN 2013084040 W CN2013084040 W CN 2013084040W WO 2014048290 A1 WO2014048290 A1 WO 2014048290A1
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Prior art keywords
water injection
passive
stack
reactor
injection cooling
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PCT/CN2013/084040
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English (en)
French (fr)
Inventor
于勇
袁霞
赵侠
张国强
李京彦
宋代勇
万砺珂
赵斌
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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Priority to GB1504152.8A priority Critical patent/GB2519919B/en
Publication of WO2014048290A1 publication Critical patent/WO2014048290A1/zh
Anticipated expiration legal-status Critical
Priority to ZA2015/02772A priority patent/ZA201502772B/en
Ceased legal-status Critical Current

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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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • 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

  • a cavity cavity water injection cooling system combining active and passive
  • the invention belongs to a reactor design technology, and particularly relates to a reactor cavity water injection cooling system combining active and passive. Background technique
  • IRR In-Vesse l Rein ent ion
  • the AP1000's passive system is only suitable for passive safety system nuclear power plants. For nuclear power plants with active safety facilities, it is difficult to meet the requirements of the whole plant power failure.
  • the other is Ex-Ves sel Retention (ERR), such as VVER-1000, EPR.
  • EPR Ex-Ves sel Retention
  • the French EPR stack is designed to guide the expansion of the core melt into the expansion space after it has penetrated the pressure vessel.
  • the cooling water is introduced into the expansion space in a passive manner to cool the diluted core melt, which has the advantages of high safety and fast solidification of the melt, but requires a large space, a large solidified melt area, and a melt cooling.
  • the pressure is high; in Russia, the WER-type nuclear power unit collects and cools the core melt through a special core trap and cools it in a passive manner. Due to its special melt trapping device and cooling method, the melt is solidified and compact, which facilitates subsequent decomposition treatment.
  • the object of the present invention is to provide a reactor cavity water injection cooling system combining active and passive operation for the safety design of a nuclear power plant.
  • the heap water injection cooling system causes the boron-containing water to flow through the heap cavity. Take away the heat released by the core melt and lower the temperature of the reactor pressure vessel to maintain the integrity of the pressure vessel.
  • a movable cavity and a passive combined water injection cooling system comprising a passive reactor cavity water injection tank and a heap cavity water injection cooling pump, wherein the passive reactor cavity water injection tank passes the passive injection pipeline
  • the reactor cavity water injection cooling pump is disposed outside the safety enclosure, and the inlet pipe of the reactor water injection cooling pump is connected to the refueling water tank, and the outlet pipeline of the reactor water injection cooling pump is connected to the reactor stack through the safety shell.
  • the active and passive combined stack water injection cooling system as described above, wherein the passive reactor water injection tank is disposed inside the safety shell, and the passive injection pipeline connected to the passive reactor water injection tank includes Two high and low injection pipes of different pipe diameters, the two injection pipes are combined into one mother pipe and connected to the inside of the stack cavity to be connected with the pressure vessel insulation layer.
  • the high pipeline adopts a larger diameter, which is used to provide a large flow volume in the initial stage of the system operation, and the lower pipeline adopts a smaller diameter. It is used to maintain the injection flow rate of the stack cavity for a long period of time; each of the injection pipelines is provided with a DC electric valve and a check valve which are powered by the battery.
  • the passive reactor water injection tank may also be disposed outside the safety shell, the stack chamber water injection cooling pump has two, the passive injection pipeline connected to the passive reactor cavity water injection tank and the two stack chamber water injection cooling pumps respectively. The outlet line is connected.
  • the active and passive combined stack water injection cooling system wherein the stack cavity water injection cooling pump has two sets, and the two stack cavity water injection cooling pump outlet lines respectively pass through the containment isolation valve Through the containment, then merged into a mother tube connected to the mother tube of the passive injection line.
  • the active and passive combined stack water injection cooling system as described above, wherein the refueling water tank connected to the inlet pipe of the stack cavity water injection cooling pump is disposed at a pit position below the inner core of the containment vessel .
  • the active and passive combined stack water injection cooling system as described above, wherein the inlet pipe of the reactor water injection cooling pump is also connected to the fire protection water source system outside the containment.
  • the active and passive combined reactor water injection cooling system as described above, wherein when the refueling water tank is connected to the low pressure injection pump, the inlet pipe of the reactor water injection cooling pump and the inlet of the low pressure injection pump The tubes are connected.
  • the active and passive combined reactor water injection cooling system as described above, wherein the passive reactor water injection tank is a closed reinforced concrete structure and is provided with a stainless steel lining.
  • the active part of the invention is mainly capable of forcibly injecting cooling water into the stack under severe conditions to achieve rapid and long-term cyclic cooling of the forced core melt; the passive part is powered off at the entire plant. In this case, the cooling water can still be introduced into the stack to achieve long-term cooling.
  • the reactor water injection cooling system provided by the invention, after the nuclear power plant has a serious accident, the core melt can be prevented from being melted through the pressure vessel, and finally the safety shell failure can be prevented, and the LELF value can be effectively reduced.
  • the invention has the characteristics of redundancy, diversity, small occupied space, short curing time of the melt, and high reliability.
  • Fig. 1 is a structural schematic view showing an embodiment of a passive reactor water injection tank of a stack cavity water injection cooling system placed inside a containment. detailed description
  • the invention provides a combination of active and passive injection of cooling water into the stack cavity to cool the core melt in the pressure vessel, and the heat of the core melt can be derived by active and long-term circulation.
  • long-term cooling of the core melt can be achieved in a passive manner.
  • the active and passive combined reactor water injection cooling system includes a reactor cavity water injection cooling pump, a passive reactor cavity water injection tank, and associated valves and piping facilities.
  • a reactor cavity water injection cooling pump a passive reactor cavity water injection tank
  • associated valves and piping facilities Usually, two sets of water injection cooling pumps are provided, but not limited to two; one set of non-active stack water injection tanks can be installed in the safety shell or outside the safety shell.
  • the passive portion of the CIS system includes a passive stack chamber water tank located inside (or outside) the containment.
  • a passive stack chamber water tank located inside (or outside) the containment.
  • two high and low injection pipes with different pipe diameters are arranged in the passive reactor water injection tank, and the high pipelines adopt a larger diameter.
  • the specific diameter of the pipe can be designed according to the power of the reactor and the actual conditions of the project.
  • four parallel DC electric valves and two check valves are provided as isolation components. After passing through the above valves, the two passive reactor water injection lines are merged into one mother again.
  • the tube is connected to the inside of the stack chamber and connected to the pressure vessel insulation layer.
  • Four parallel electric valves are DC-driven valves powered by batteries.
  • the main part of the active part of the C I S system is placed outside the containment, and the inlet pipes of the two stacking water injection cooling pumps are connected to the refueling tank.
  • the inlet pipe of the submerged water cooling pump is respectively connected with the inlet pipes of the two rows of low-pressure injection pumps to reduce the number of the safety shell penetrations, which are all changed from the built-in (or external)
  • the refueling water tank is disposed at a pit position below the core of the containment.
  • the two stacking water injection cooling pump outlet pipelines pass through the containment after passing through the containment isolation valve, and then merged into a mother tube connected to the passive part of the stack cavity water injection.
  • the purpose of this design is to reduce the concrete structure of the pile cavity.
  • the number of holes is opened to ensure the stability of the soil structure of the stack.
  • the inlet pipe of each reactor water injection cooling pump can also be connected to the fire water source outside the containment.
  • the normal operation of the CI S system means that the CIS is put into operation in the event of a serious nuclear reactor damage.
  • the C IS system is in a shutdown state.
  • the active and passive combined reactor water injection cooling system includes a passive reactor water injection tank 1 and two stack chamber water injection cooling pumps 3, the passive reactor chamber injection
  • the water tank 1 is connected to the reactor stack chamber 2 through a passive injection line.
  • the stack chamber water injection cooling pump 3 is disposed outside the containment vessel 5.
  • the inlet tube of the stack chamber water injection cooling pump 3 is connected to the refueling water tank 4, and the stack chamber water injection cooling pump
  • the outlet line of 3 is connected to the reactor stack 2 through the containment vessel 5.
  • the refueling tank 4 can be disposed outside the containment or in the containment.
  • the preferred solution is to place the refueling tank in the pit below the core, and the refueling tank is at the lowest position. It is convenient to collect water from the safety shell spray and pipe breakage.
  • the passive reactor water injection tank is disposed inside the safety shell, and the passive injection pipeline connected to the passive reactor water injection tank includes two injection pipelines of different diameters, two injection pipelines, and two injection pipelines.
  • the combined into a mother tube is connected to the inside of the stack chamber and connected to the pressure vessel insulation layer.
  • the high pipeline adopts a larger diameter, which is used to provide a large flow volume in the initial stage of operation of the system, and the lower pipeline adopts a smaller diameter for maintaining Long-term stack injection flow; each injection line is provided with a battery-operated DC electric valve and a check valve.
  • the outlet lines of the two stacking water injection cooling pumps 3 pass through the containment isolation valve and pass through the containment 5, respectively, and then merge into a mother tube to be connected to the mother tube of the passive injection line.
  • the inlet pipe of the submerged water cooling pump is respectively connected with the inlet pipes of the two rows of low-pressure injection pumps to reduce the number of the safety shell penetrations, all from the built-in (or external)
  • the water tank takes water.
  • the inlet pipe of the water injection cooling pump 3 is also connected to the fire water source system 6 outside the containment.
  • the passive reactor water injection tank is a closed reinforced concrete structure and is provided with a stainless steel lining.
  • the piping and fittings of the system are all austenitic stainless steel.
  • the core outlet temperature reaches 65 (TC receives an alarm.
  • the active part of the CIS system is started first, and one of the two stacking water injection cooling pumps is started, from the lower part.
  • the built-in (or external) refueling tank takes water to form a continuous stacking chamber for injection cooling.
  • the water level of the built-in (or external) refueling tank is temporarily unavailable, it is connected to the fire water pipe in the containment building through the temporary take-over. Cooling water source for the CI S system.
  • the connection to the fire piping can be disconnected and the water source in the refueling tank can be restored.
  • the coolant injected into the stack flows through the surface of the pressure vessel, taking away the heat generated by the core melt in the pressure vessel, flowing out from the gap between the main pipe and the stack cavity, and finally recirculating to the refueling
  • the vertical member can manually open the battery-powered DC electric valve in the main control room or outside the safety enclosure.
  • the non-dynamic stack injection tank injects cooling water into the insulation layer and the pressure vessel. According to the core melt, the heat is released. Change, relying on gravity to maintain passive stack injection. First, the high-diameter large-diameter pipeline and the low-profile small-diameter pipeline simultaneously inundate the heap cavity, and then the low-profile small-diameter pipeline continuously replenishes the heap cavity, so that the outer wall of the pressure vessel is always submerged in the coolant to prevent the core melt from melting. Wear a pressure vessel.
  • PCS containment passive heat removal system
  • the PCS system condenses the vapor in the atmosphere of the containment, and passively collects the passive injection tank to the passive reactor water tank by gravity along the wall of the heat exchanger inside the PCS system, and the power is turned off in the whole plant. Under the water can provide hydration for the tank.
  • the maintenance personnel should restore the active part of the CIS system and the injection system to form long-term cooling of the core melt and long-term pressure reduction and cooling of the environment inside the containment.
  • the cooling water pump is continuously injected into the stack by the water injection cooling pump. Even if the electric valve powered by the battery cannot be closed, the check valve can ensure that the passive injection tank is not contaminated.
  • the present invention also provides a structure of another active and passive combined reactor water injection cooling system (CIS).
  • CIS active and passive combined reactor water injection cooling system
  • the main difference from the first embodiment is that the passive reactor water injection tank is disposed outside the safety shell, and is passive.
  • the passive injection lines connected to the stacking tank are respectively connected to the outlet lines of the two stacking water injection cooling pumps.
  • the refueling tank as a cooling water source can also take the form of an external containment.
  • the commissioning mode and working process of the CIS system of Embodiment 1 are similar to those of the CIS system of Embodiment 1. However, since the passive reactor water injection tank is placed outside the containment, it is no longer possible to replenish the passive reactor water injection tank through the steam condensate of the PCS system. Therefore, it may be considered to increase the external water supply line. It is apparent that those skilled in the art can make various modifications and variations to the invention without departing from the spirit and scope of the invention. Thus, it is intended that the present invention cover the modifications and modifications of

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

Description

一种能动与非能动相结合的堆腔注水冷却系统 技术领域
本发明属于反应堆设计技术， 具体涉及一种能动与非能动相结合的堆腔注 水冷却系统。 背景技术
在世界各国核电站中， 应对堆芯熔融物的措施分为两种类型： 一种为堆内 滞留 （In- Vesse l Ret ent ion, IVR ), 例如美国 AP1 000堆型， 在严重事故条件 下， 当堆芯熔化不可避免时， 可以通过淹没反应堆堆腔、 冷却压力容器外壁的 方式， 保持压力容器下封头完整性， 从而将熔融堆芯物质滞留在压力容器内。 通过非能动的方式对堆芯熔融物进行冷却， 优点是结构简单造价低（但是不适 用于高功率的核电站）， 而且可以:†巴熔融物限制在压力容器内， 防止了放射性物 质的泄漏， 也保证了安全壳的完整性。 但是由于目前对熔融物的冷却及层化现 象还未充分理解， 失效裕度难以确定， 因此还存在一定的风险。 而且 AP1000的 非能动系统仅适用于非能动安全系统核电厂， 对于能动型专设安全设施的核电 厂， 上述系统很难满足应对全厂断电事故的要求。
另外一种是堆外滞留 ( Ex-Ves sel Retent ion, EVR ), 例如 VVER-1000、 EPR, 法国的 EPR堆型的设计理念是在堆芯熔融物熔穿压力容器后， 引导至扩展空间， 再通过非能动的方式将冷却水引至扩展空间， 对摊薄的堆芯熔融物进行冷却， 其优点是安全性高， 熔融物固化快， 但是所需空间大 、 固化熔融物面积大、 熔 融物冷却时压力高； 而俄罗斯的 WWER型核电机組， 是通过专门的堆芯捕集器对 堆芯熔融物收集并冷却， 通过非能动的方式进行冷却。 由于其特殊的熔融物捕 集装置和冷却方式， 熔融物固化后结构紧凑， 利于后续的分解处理。 而且由于 熔融物一直被限制于热交换器中且与安全壳大气和冷却水的接触面积较小， 因 此减少了裂变产物的泄漏， 安全壳内压力也较低。 但是因为熔融物冷却速率较 低， 因此熔融物的固化时间也较长， 长达数月。 发明内容
本发明的目的在于针对核电站安全设计的需要， 提供一种能动与非能动 相结合的堆腔注水冷却系统， 在核电站发生严重事故工况时， 堆腔注水冷却系 统使含硼水流过堆腔， 带走堆芯熔融物释放出的热量， 降低反应堆压力容器的 温度， 以维持压力容器的完整性。 本发明的技术方案如下： 一种能动与非能动相结合的堆腔注水冷却系统， 包括非能动堆腔注水箱和堆腔注水冷却泵， 所述的非能动堆腔注水箱通过非能 动注入管线与反应堆堆腔连接， 所述的堆腔注水冷却泵设置在安全壳外部， 堆 腔注水冷却泵的入口管连接换料水箱， 堆腔注水冷却泵的出口管线贯穿安全壳 与反应堆堆腔连接。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 所 述的非能动堆腔注水箱设置在安全壳内部， 与非能动堆腔注水箱连接的非能动 注入管线包括高、 低两根不同管径的注入管线， 两根注入管线合并为一根母管 贯穿到堆腔内部与压力容器保温层相连接。
再进一步， 所述的高、低两根不同管径的注入管线中， 高位管线采用较大 管径，用于在系统投运初期提供大流量的堆腔淹没，低位管线采用较小管径， 用于维持较长时期的堆腔注入流量；每根注入管线上分別设有由蓄电池供电的 直流电动阀和逆止阀。 另外， 非能动堆腔注水箱亦可设置在安全壳外部， 所述的堆腔注水冷却泵 有两台， 与非能动堆腔注水箱连接的非能动注入管线分别与两台堆腔注水冷却 泵的出口管线连接。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 所 述的堆腔注水冷却泵有两台， 两台堆腔注水冷却泵的出口管线分别经过安全壳 隔离阀后贯穿安全壳， 然后合并为一奈母管与所述的非能动注入管线的母管相 连接。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 所 述的与堆腔注水冷却泵的入口管相连接的换料水箱设置在安全壳内部堆芯下方 地坑位置。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 所 述的堆腔注水冷却泵的入口管还与安全壳外消防水源系统相连接。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 当 换料水箱连接低压安注泵时， 所述的堆腔注水冷却泵的入口管与低压安注泵的 入口管相连接。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 所 述的非能动堆腔注水箱为封闭的钢筋混凝土结构， 并设有不锈钢衬里。 进一步， 如上所述的能动与非能动相结合的堆腔注水冷却系统， 其中， 系 统的管道及管件的材料均为奥氏体不锈钢。 本发明的有益效果如下： 本发明的能动部分主要是在恶劣的条件下， 可以 将冷却水强制注入堆腔， 实现强制堆芯熔融物的快速、 长期循环冷却； 非能动 部分在全厂断电的情况下， 依旧可以将冷却水导入堆腔， 实现长期冷却。 通过 本发明所提供的堆腔注水冷却系统， 可以在核电厂发生严重事故后， 防止堆芯 熔融物熔穿压力容器， 最终防止安全壳失效， 有效地降低 LERF值 。 本发明具 有冗余性、 多样性、 占用空间小、 熔融物固化时间短、 可靠性高等特点。 附图说明
图 1为堆腔注水冷却系统的非能动堆腔注水箱置于安全壳内部的实施例 结构示意图。 具体实施方式
本发明提供了一种能动与非能动相结合的方式将冷却水注入堆腔， 对压力 容器内的堆芯熔融物进行冷却， 既可以通过能动、 长期循环的方式将堆芯熔融 物的热量导出， 又可以在全厂断电的情况下， 以非能动的方式实现堆芯熔融物 的长期冷却。 从而防止堆芯熔融物熔穿安全壳底板， 造成核电站最后一道屏障 的失效
该能动与非能动相结合的堆腔注水冷却系统（ CIS )包含堆腔注水冷却泵、 非能动堆腔注水箱， 以及附属阀门和管道设施。 通常情况下， 堆腔注水冷却 泵设置两台， 但不局限于两台； 非能动堆腔注水箱设置一台， 可以设在安全 壳内或安全壳外。
C I S系统的非能动部分包括设在安全壳内 （或外）的非能动堆腔注水箱。 为满足初始的大流量淹没要求及后期的冷却水注入流量要求， 在非能动堆腔 注水箱内设置高、 低两个不同管径的注入管线， 高位管线采用较大管径， 用 于在系统投运初期提供大流量的堆腔淹没， 低位的较小管径的管线用于维持 较长时期的堆腔注入流量， 具体管径的大小可根据反应堆功率以及工程实际 情况进行设计。 为保证非能动堆腔注水的可靠性， 设置了四台并联的直流电 动阀和两台逆止阀作为隔离部件， 在经过上述阀门后， 两根非能动堆腔注水 管线再次合并为一根母管贯穿到堆腔内部与压力容器保温层相连接。 四台并 联的电动阀为由蓄电池供电的直流电机驱动的阀门。
C I S 系统的能动部分主要设备设置在安全壳外， 两台堆腔注水冷却泵的 入口管连接换料水箱。 当换料水箱连接低压安注泵时， 堆腔注水冷却泵的入口 管分別与两列低压安注泵的入口管相连， 以减少安全壳贯穿件的数量， 均从 内置〔或外置）换料水箱取水， 优选的方案中， 换料水箱设置在安全壳内部堆 芯下方地坑位置。 两台堆腔注水冷却泵出口管线在经过安全壳隔离阀后贯穿 安全壳， 再合并为一条母管与堆腔注水非能动部分母管相连接， 此种设计的 目的是减少堆腔混凝土结构的开洞数量， 以保证堆腔土建结构稳定。 每台堆 腔注水冷却泵的入口管还可以与安全壳外消防水源相连。
CI S系统的正常运行是指在发生核电站堆芯严重损毁事故时， CIS投入运行。 核电站正常运行时， C IS系统处在停运备用状态。 下面结合附图和实施例对本发明进行详细的描述。
实施例 1
如图 1 所示， 能动与非能动相结合的堆腔注水冷却系统（CIS ), 包括一台 非能动堆腔注水箱 1和两台堆腔注水冷却泵 3，所述的非能动堆腔注水箱 1通过 非能动注入管线与反应堆堆腔 2连接，所述的堆腔注水冷却泵 3设置在安全壳 5 外部， 堆腔注水冷却泵 3的入口管连接换料水箱 4 , 堆腔注水冷却泵 3的出口管 线贯穿安全壳 5与反应堆堆腔 2连接。 换料水箱 4可以设置在安全壳外或安全 壳内， 优选的方案是将换料水箱设置在堆芯下方地坑位置， 换料水箱位于最低 处， 方便汇集来自安全壳喷淋、 管道破口所带来的水源。
本实施例中， 所述的非能动堆腔注水箱设置在安全壳内部， 与非能动堆腔 注水箱连接的非能动注入管线包括高、 低两根不同管径的注入管线， 两根注入 管线合并为一根母管贯穿到堆腔内部与压力容器保温层相连接。 所述的高、 低 两根不同管径的注入管线中， 高位管线采用较大管径， 用于在系统投运初期提 供大流量的堆腔淹没， 低位管线采用较小管径， 用于维持较长时期的堆腔注 入流量； 每根注入管线上分别设有由蓄电池供电的直流电动阀和逆止阀。
两台堆腔注水冷却泵 3的出口管线分别经过安全壳隔离阀后贯穿安全壳 5 , 然后合并为一条母管与所述的非能动注入管线的母管相连接。 当换料水箱连接 低压安注泵时， 堆腔注水冷却泵的入口管分别与两列低压安注泵的入口管相 连， 以减少安全壳贯穿件的数量， 均从内置 （或外置）换料水箱取水。 堆腔 注水冷却泵 3的入口管同时与安全壳外消防水源系统 6相连接。
所述的非能动堆腔注水箱为封闭的钢筋混凝土结构， 并设有不锈钢衬里。 系统的管道及管件的材料均为奥氏体不锈钢。
在发生堆芯损毁事故后， 堆芯出口温度达到 65 (TC时接到报警， 需要 CIS系 统投入时， 先启动 CIS 系统能动部分， 启动两台堆腔注水冷却泵中的一台， 从 下部的内置（或外置） 换料水箱取水， 形成持续的堆腔注入冷却。 在内置（或 外置） 换料水箱水位暂时不可用时， 则通过临时接管与安全壳厂房内的消防水 管道相连， 作为 CI S 系统的冷却水源。 当内置换料水箱恢复使用时， 可以将与 消防管道的连接断开， 再恢复使用换料水箱内的水源。
在 CIS 系统能动部分投入后， 注入堆腔内的冷却剂流经压力容器表面， 带 走压力容器内堆芯熔融物产生的热量， 从主管道与堆腔之间缝隙流出， 最终汇 至换料水箱， 由堆腔注水冷却泵重新再将冷却剂注入堆腔， 形成可持续的循环 冷却。
如果 CIS系统能动部分不可用 （例如全厂断电， 应急柴油机也不可用）， 操 纵员可以在主控室或者安全壳外就地手动打开由蓄电池供电的直流电动阀， 非 能动堆腔注水箱将冷却水注入到保温层与压力容器之间， 根据堆芯熔融物释热 的变化， 依靠重力保持非能动的堆腔注入。 首先高位大管径管线和低位小管径 管线同时作用将堆腔淹没， 随后低位小管径管线对堆腔进行持续补水， 使压力 容器外壁始终保持淹没在冷却剂中， 防止堆芯熔融物熔穿压力容器。 随着緩解 事故的时间进展， 熔融物释热逐渐降低， 所需冷却水量也逐渐減小， 非能动水 箱液位不断下降， 能够提供的冷却水流量也在逐渐降低， 为满足冷却水流量和 堆腔内冷却水液位的要求， 可能需要为水箱提供额外补水。 由于发生严重事故 后， 安全壳非能动热量导出系统（PCS )也将启动将热量导出安全壳传到最终热 阱大气， 进行降温降压， PCS系统的结构可参见中国专利申请 201210090809. 9。 与此同时， PCS系统将安全壳大气中的蒸汽冷凝后，通过重力非能动地沿 PCS系 统安全壳内热交换器的壁面向下流动收集至非能动堆腔注水箱， 在全厂断电的 情况下可以为水箱非能动的提供补水。 同时维修人 应恢复 CIS 系统能动部分 和安喷系统， 以便形成堆芯熔融物的长期冷却和安全壳内环境的长期降压和冷 却。 CIS系统的能动部分恢复后， 由堆腔注水冷却泵继续将冷却水注入堆腔， 即 使由蓄电池供电的电动阀无法关闭， 但逆止阀可以保证非能动堆腔注水箱不会 被污染。
当严重事故得到緩解， 运行人 判断不再会发生压力容器下封头失效的危 险时 , 由运行人员将上述设备关闭和停运。 实施例 2
本发明还提供了另一种能动与非能动相结合的堆腔注水冷却系统（CIS )的 结构， 与实施例 1 的主要区别在于， 非能动堆腔注水箱设置在安全壳外部， 与 非能动堆腔注水箱连接的非能动注入管线分别与两台堆腔注水冷却泵的出口管 线连接。 作为冷却水源的换料水箱， 也可以采取外置于安全壳的形式。 实施例 1的 C I S系统的投运方式和工作过程与实施例 1中的 C I S系统类 似。 但是， 由于非能动堆腔注水箱置于安全壳外， 无法再通过 PCS系统的蒸汽 冷凝水对非能动堆腔注水箱进行补水， 因此， 可以考虑增加外部的补水管线。 显然， 本领域的技术人员可以对本发明进行各种改动和变型而不脱离本 发明的精神和范围。 这样， 倘若对本发明的这些修改和变型属于本发明权利 要求及其同等技术的范围之内， 则本发明也意图包含这些改动和变型在内。

Claims

权 利 要 求
1.一种能动与非能动相结合的堆腔注水冷却系统， 其特征在于： 包括非能 动堆腔注水箱 （1 )和堆腔注水冷却泵 （3 ), 所述的非能动堆腔注水箱 （1 )通 过非能动注入管线与反应堆堆腔（2 )连接， 所述的堆腔注水冷却泵（3 )设置 在安全壳 （5 )外部， 堆腔注水冷却泵 （ 3 ) 的入口管连接换料水箱 〔4 ), 堆腔 注水冷却泵（ 3 ) 的出口管线贯穿安全壳 （ 5 )与反应堆堆腔（ 2 )连接。
2. 如权利要求 1 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 所述的非能动堆腔注水箱 （1 )设置在安全壳 （5 ) 内部， 与非能动堆 腔注水箱 （1 )连接的非能动注入管线包括高、 低两根不同管径的注入管线， 两 根注入管线合并为一根母管贯穿到堆腔内部与压力容器保温层相连接。
3. 如权利要求 1 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 非能动堆腔注水箱设置在安全壳外部， 所述的堆腔注水冷却泵有两台， 与非能动堆腔注水箱连接的非能动注入管线分别与两台堆腔注水冷却泵的出口 管线连接。
4. 如权利要求 2 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 所述的高、 低两根不同管径的注入管线中， 高位管线采用较大管径， 用于在系统投运初期提供大流量的堆腔淹没， 低位管线采用较小管径， 用于 维持较长时期的堆腔注入流量， 每根注入管线上分别设有由蓄电池供电的直流 电动阀和逆止阀。
5. 如权利要求 2 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 所述的堆腔注水冷却泵（ 3 )有两台， 两台堆腔注水冷却泵的出口管线 分别经过安全壳隔离阀后贯穿安全壳， 然后合并为一条母管与所述的非能动注 入管线的母管相连接。
6. 如权利要求 1 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 所述的与堆腔注水冷却泵的入口管相连接的换料水箱设置在安全壳内 部堆芯下方地坑位置。
7. 如权利要求 1或 5所述的能动与非能动相结合的堆腔注水冷却系统， 其特征在于： 所述的堆腔注水冷却泵（3 ) 的入口管还与安全壳外消防水源系统
( 6 )相连接。
8. 如权利要求 7 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 当换料水箱连接低压安注泵时， 所述的堆腔注水冷却泵的入口管与低 压安注泵的入口管相连接。
9. 如权利要求 1 所述的能动与非能动相结合的堆腔注水冷却系统， 其特 征在于： 所述的非能动堆腔注水箱为封闭的钢筋混凝土结构， 并设有不锈钢衬 里。
10. 如权利要求 1所述的能动与非能动相结合的堆腔注水冷却系统， 其 特征在于： 系统的管道及管件的材料均为奥氏体不锈钢。
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