WO2014048292A1 - 一种能动与非能动相结合的堆芯注水热量导出装置 - Google Patents

一种能动与非能动相结合的堆芯注水热量导出装置 Download PDF

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Publication number
WO2014048292A1
WO2014048292A1 PCT/CN2013/084046 CN2013084046W WO2014048292A1 WO 2014048292 A1 WO2014048292 A1 WO 2014048292A1 CN 2013084046 W CN2013084046 W CN 2013084046W WO 2014048292 A1 WO2014048292 A1 WO 2014048292A1
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Prior art keywords
injection
core
tank
safety
active
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English (en)
French (fr)
Inventor
于勇
袁霞
赵侠
蒋慧黠
张雪霜
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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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
    • 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

  • the invention belongs to a reactor design technology, and particularly relates to a core water injection heat export device combining active and passive. Background technique
  • a dynamic safety injection system provides continuous cooling of the core in the event of a design basis accident, and the heat in the core is derived by long-term cycling.
  • the high-pressure injection pump automatically starts after receiving the injection signal, and absorbs water from the refueling tank to inject the boron-containing water into the reactor coolant system.
  • the low-pressure injection pump absorbs water from the pit. Achieve long-term recycling injection.
  • the structure of the existing reactor safety injection system is shown in Figure 1.
  • the refueling water tank 1 is placed outside the containment vessel, and the cold and hot pipe sections of the primary circuit are connected through the pipeline.
  • the high pressure injection pump 2 and the low pressure injection pump 3 are arranged on the pipeline.
  • the low pressure injection pump 3 is also connected to the containment pit 4 through a pipeline.
  • a passive injection box system is also included. After the accident, when the pressure of the reactor coolant system drops below the pressure of the injection tank, the boron in the injection tank Water is automatically injected into the reactor coolant system under the pressure of nitrogen to provide emergency cooling for the core. As shown in Figure 2, 1 is the refueling tank and 5 is the injection tank.
  • a passive core water supply tank is used in addition to the injection tank, and the inlet and the outlet are respectively connected to the primary circuit cold pipe section and the pressure vessel direct injection pipe.
  • boron-containing water is injected into the primary circuit through the natural circulation mode to maintain the water volume of the primary circuit and alleviate the reactive transients.
  • the inlet of the core water supply tank 6 is connected to the primary circuit cold pipe section, and the outlet thereof is connected to the direct injection pipe of the pressure vessel 7, and in the figure, 5 is an injection tank.
  • the object of the present invention is to provide a core water injection heat deriving device which is advanced in technology, high in safety, and capable of coping with a variety of accident conditions.
  • the heat in the core can be derived by means of active and long-term circulation, and the long-term cooling of the core can be realized in a passive manner in the case of power failure in the whole plant.
  • a core injection water heat transfer device combining active and passive, comprising a safety injection pipeline respectively connected with a refueling water tank and a cold and heat pipe section of a circuit, and a safety injection pipeline is provided
  • An injection pump wherein the refueling water tank is disposed at a pit position below the core of the containment, and the pump is disposed outside the safety shell; and a passive safety tank is disposed above the reactor in the safety shell and a core filling tank, wherein the tank is connected to a cold pipe section of a circuit through a pipe provided with a control valve, and the core water tank is connected to a heat pipe section and a cold circuit of a circuit through a pipe provided with a control valve Between the pipe segments.
  • the active and passive combined core water injection heat derivation device as described above, wherein the injection pump comprises two independent medium pressure injection pumps and two independent low pressure injection pumps. Four injection pumps are placed in parallel on the safety injection line.
  • the active and passive combined core water injection heat derivation device as described above, wherein the medium pressure injection pump has an injection head range of 600 mWC to 1100 mWC, and the injection head range of the low pressure injection pump It is 90mWC ⁇ 180mWC.
  • the active and passive combined core water injection heat exporting device wherein There are three safety injection boxes, which are arranged independently of each other; each of the safety injection boxes and the cold pipe sections of the first circuit are provided with isolation valves and check valves.
  • the active and passive combined core water injection heat derivation device wherein the core replenishing tank has three sets, which are independently arranged; the inlet of each core replenishing tank passes the normally open pressure
  • the balance line is connected to the heat pipe section of the first circuit, and the outlet is connected to the cold pipe section of the circuit through the isolation valve and the check valve.
  • the inner displacement water tank is located at the lowest point inside the containment, which reduces the impact of external disasters on the safety of the refueling tank and improves the reliability of the emergency water source after the accident.
  • the injection pump reduces the injection pressure head (from high pressure to medium pressure), which can effectively reduce the consequences of high-voltage safety injection accidents, avoid excessive pressure in the primary circuit, and reduce or avoid the heat exchanger tube rupture accident of the steam generator.
  • the loop pressure is too high and may cause the steam generator to overflow, thereby reducing the possibility of radioactive materials being discharged into the environment under the accident.
  • FIG. 1 is a schematic view of a high pressure and low pressure safety injection system in the prior art
  • FIG. 2 is a schematic view of an injection molding system in the prior art
  • FIG. 3 is a schematic view showing a setting manner of a core water supply tank in the prior art
  • FIG. 4 is a schematic view of a core water injection heat deriving device combining active and passive phases of the present invention. detailed description
  • the active and passive combined core water injection heat derivation device adopts a movable medium pressure injection pump and a low pressure injection pump, a passive safety injection tank and a core water supply tank, and a containment replacement. Water tank.
  • the active part of the core water injection heat export device can be provided with two independent medium pressure injection pumps and two independent low pressure injection pumps. Both the medium pressure injection pump and the low pressure injection pump are connected between the inner displacement water tank and the cold/heat pipe section of the primary circuit through a pipe provided with a control valve. The injection pump is injected into the reactor at the beginning of the process. The cold section is injected until the long-term cooling, and the hot and cold sections are simultaneously injected.
  • the M310 stack type upper charge pump also serves as a high pressure injection pump.
  • the present invention separates the upper charge and the safety injection function, cancels the high pressure injection pump, and adds a medium pressure injection pump.
  • the pump switches from the upper charging mode to the safety injection mode. This switching process requires a large number of valves to be operated, which will affect the reliability of the system.
  • the special medium-pressure injection pump is set according to the invention, the single function is performed, and the reliability of the system can be improved.
  • the injection pump reduces the injection head (from high pressure to medium pressure, and the injection head range is 600mWC ⁇ 1100mWC), which can effectively reduce the consequences of high-voltage safety injection accidents, avoid excessive pressure in the primary circuit, and reduce or avoid steam.
  • the generator heat transfer tube rupture accident is too high and the steam generator may overflow, which may reduce the possibility of radioactive substances discharging to the environment under the accident.
  • the inner displacement water tank is located at the lowest pit inside the containment and the pit below the core, which reduces the impact of external disasters on the safety of the refueling tank, improves the reliability of the emergency water source after the accident, and improves the safety of the nuclear power plant.
  • the safety system needs to be switched with the level gauge.
  • the refueling water tank After the refueling water tank is built in, it is convenient to collect the water source from the safety shell spray and pipeline breakage, and combine with the pit of the reactor to play the role of the cylinder equipment, no need to switch operation. Because the internal displacement tank will be the only source of active water injection after the accident, it can reduce the operation after the accident, avoid the possible errors, reduce the potential risk of the system operation mode switching failure, thereby improving the reliability and enhancement of the system. The safety of the power plant.
  • the active and passive combined core water injection heat exporting device comprises a refueling water tank 8 disposed at a pit position below the inner core of the containment, a refueling water tank 8 and a cold and hot pipe section of the first circuit.
  • the safety injection line is connected by two independent medium pressure injection pumps 9 and two independent low pressure injection pumps 10, and four injection pumps are arranged in parallel on the safety injection line. , located outside the containment.
  • the number of the medium pressure injection pump 9 and the low pressure injection pump 10 is not limited to two.
  • the injection pressure head of the medium pressure injection pump ranges from 600mWC to 11 00mWC, and the injection pressure head of the low pressure injection pump ranges from 90mWC to 180mWC.
  • the system immediately starts the medium pressure injection pump 9 and the pressure injection pump 10 when receiving the safety signal.
  • the injection pump was initially started with a small flow line, and when the reactor coolant system pressure dropped below the closed injection pressure of the medium pressure injection pump, the medium pressure injection pump began to provide injection to the reactor coolant system. When the reactor coolant system pressure drops below the closing head of the low pressure injection pump, the low pressure injection pump begins to provide injection to the reactor coolant system.
  • a safety injection tank 1 1 and a core water supply tank 12 are also arranged in the safety shell, and the safety injection tank 11 is connected to the cold pipe section 15 of the first circuit through a pipe provided with a control valve, and each safety injection box An isolation valve and a check valve are disposed on the pipeline connecting the tank 11 and the cold pipe section 15 of the primary circuit, and the core water supply tank 12 is connected to the heat pipe section 16 and the cold pipe section 15 of the first circuit through a pipe provided with a control valve. between.
  • 14 is a steam generator.
  • three independent injection tanks 11 and three independent core water supply tanks 12 can be provided, and only one series is shown in Fig. 4.
  • the injection tank 11 is connected to the cold pipe section of the three loops of the first loop through the pipes provided with the control valves, and the check valves are automatically opened when the pressure of the primary circuit system is ⁇ , and water is injected into the core.
  • Most of the space in the tank is occupied by boron water and pressurized by nitrogen. The pressure is supplied by compressed nitrogen. When the pressure in the primary circuit is low, high-flow boron water can be injected into the reactor pressure vessel to rapidly cool the core.
  • the core water supply tank 12 is higher than the core setting, and the inlet is connected to the hot section of the primary circuit section through the normally open pressure balance line, thereby maintaining the pressure of the core water supply tank in the primary circuit to prevent the core water supply tank from being injected. Water hammer phenomenon occurs, and the core filling tank outlet is connected to the cold circuit through the isolation valve and the check valve. On the pipe section. The temperature of the boron water in the core make-up tank is the same as the ambient temperature of the containment.
  • the isolation valve is opened, and the core replenishing tank injects the coolant into the pressure vessel along the cold section of the primary circuit by means of the gravity indenter generated by the height difference, compensating for the water level drop of the primary circuit, and maintaining the immersion and residual heat of the core.
  • the passive core water supply tank can maintain a certain driving pressure by using the connection function of the pressure balance pipeline, thus ensuring the safe injection of the primary circuit under high pressure conditions.
  • the core fill tank can be operated in two modes: water cycle mode and steam replacement mode.
  • water circulation mode the hot water from the heat pipe section enters the core water supply tank, and the cold water in the tank enters the primary circuit, which will boil the primary circuit and increase its water capacity.
  • steam replacement mode steam enters the core make-up tank through the pressure line, compensating for the water injected into the primary circuit.
  • the operating mode of the core fill tank depends on the condition of the primary circuit.

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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芯注水热量导出装置
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芯注 水热量导出装置。 背景技术
作为压水堆核电厂的专设安全设施， 在发生设计基准事故时， 能动的安全 注入系统能为堆芯提供持续的冷却， 通过长期循环的方式将堆芯内的热量导出。 在发生事故时， 高压安注泵接到安注信号后自动启动， 从换料水箱吸水， 将含 硼水注入反应堆冷却剂系统； 在再循环注入阶段， 低压安注泵从地坑吸水， 从 而实现长期的再循环注入。 现有的反应堆安全注入系统的结构如图 1 所示， 换 料水箱 1 置于安全壳外部， 通过管线连接一回路的冷、 热管段， 管线上设置高 压安注泵 2和低压安注泵 3 , 低压安注泵 3还通过管线连接安全壳地坑 4。
在传统的压水堆核电厂的安全注入系统中还包括了非能动的安注箱子系 统， 在事故发生后当反应堆冷却剂系统的压力降到安注箱压力以下时， 安注箱 内的硼水在氮气压力的作用下自动注入到反应堆冷却剂系统， 为堆芯提供应急 冷却。 如图 2所示， 图中 1为换料水箱， 5为安注箱。
在第三代核电机组 AP1000的非能动堆芯冷却系统中除安注箱之外还使用了 非能动的堆芯补水箱， 其入口和出口分别与一回路冷管段和压力容器直接注入 管相连， 在事故后通过自然循环模式向一回路注入含硼水， 以维持一回路的水 装量并緩解反应性瞬变。 如图 3所示， 堆芯补水箱 6的入口连接一回路冷管段， 其出口连接压力容器 7的直接注入管， 图中 5为安注箱。
传统压水堆核电厂的安全注入系统以及非能动的堆芯补水箱都无法充分保 证多种事故工况下核电站的安全可靠， 因此， 需要对这些系统进行合理的整合， 结合新的设计要点， 进一步提高系统的安全冗余性。 发明内容
本发明的目的在于针对现有技术的不足， 提供一种技术先进、 安全性高、 能应对多种事故工况的能动与非能动相结合的堆芯注水热量导出装置。 既可以 通过能动、 长期循环的方式将堆芯内的热量导出， 又可以在全厂断电的情况下， 以非能动的方式实现对堆芯的长期冷却。 本发明的技术方案如下： 一种能动与非能动相结合的堆芯注水热量导出装 置， 包括分别与换料水箱和一回路的冷、 热管段相连接的安全注入管线， 安全 注入管线上设有安注泵， 其中， 所述的换料水箱设置在安全壳内部堆芯下方地 坑位置， 安注泵设置在安全壳外部； 在安全壳内反应堆的上方还设有非能动的 安注箱和堆芯补水箱， 所述的安注箱通过设有控制阀门的管道与一回路的冷管 段相连接， 所述的堆芯补水箱通过设有控制阀门的管道连接在一回路的热管段 和冷管段之间。 进一步，如上所述的能动与非能动相结合的堆芯注水热量导出装置，其中， 所述的安注泵包括两台相互独立的中压安注泵和两台相互独立的低压安注泵， 四台安注泵在安全注入管线上并联设置。
更进一步， 如上所述的能动与非能动相结合的堆芯注水热量导出装置， 其 中， 所述的中压安注泵的注入压头范围为 600mWC~1100mWC, 低压安注泵的注入 压头范围为 90mWC~180mWC。 进一步，如上所述的能动与非能动相结合的堆芯注水热量导出装置，其中， 所述的安注箱共有三台， 相互独立设置； 每台安注箱与一回路的冷管段相连接 的管道上设有隔离阀及止回阀。 进一步，如上所述的能动与非能动相结合的堆芯注水热量导出装置，其中， 所述的堆芯补水箱共有三台， 相互独立设置； 每台堆芯补水箱的入口通过常开 的压力平衡管线与一回路的热管段相连， 其出口通过隔离阀及止回阀连接在一 回路冷管段上。 本发明的有益效果如下： 本发明所提供的堆芯注水热量导出装置采用能 动与非能动相结合的方式， 可以在事故后使用多种手段向堆芯注水导出热量： 安注箱可以在短时间内提供高流量的安注迅速淹没堆芯， 保证快速冷却堆芯； 动的安注泵可以维持堆芯淹没， 并通过长期循环的方式不断导出堆芯热量。 内 置换料水箱位于安全壳内部最低处， 减少了外部灾害对换料水箱安全性的影响， 提高了事故后应急水源的可靠性。 安注泵降低了注入压头 （由高压变为中压）， 可以有效降低高压安注误启动事故后果， 避免一回路压力过高， 也可以减轻或 避免蒸汽发生器传热管破裂事故下一回路压力过高而可能导致的蒸汽发生器满 溢， 从而降低该事故下放射性物质向环境排放的可能性。 附图说明
图 1为现有技术中的高压和低压安注系统示意图；
图 2为现有技术中的安注箱注入系统示意图；
图 3为现有技术中的堆芯补水箱设置方式示意图；
图 4为本发明的能动与非能动相结合的堆芯注水热量导出装置示意图。 具体实施方式
本发明所提供的能动与非能动相结合的堆芯注水热量导出装置采用了能动 的中压安注泵和低压安注泵， 非能动的安注箱和堆芯补水箱， 以及安全壳内置 换料水箱。
堆芯注水热量导出装置的能动部分具体可设置两台相互独立的中压安注泵 和两台相互独立的低压安注泵。 中压安注泵和低压安注泵均通过设置有控制阀 门的管道连接在内置换料水箱和一回路的冷 /热管段之间。 安注泵向反应堆一回 路注水的开始阶段是冷段注入， 直到长期冷却后， 才开始冷热段同时注入。
原来 M310堆型的上充泵同时兼作高压安注泵， 本发明将上充和安注功能分 离， 取消高压安注泵， 增设了中压安注泵。 原 M310堆型在安注信号出现时， 泵 从上充模式切换到安注模式， 此切换过程需操作大量阀门， 将影响到系统的可 靠性。 本发明设置专用的中压安注泵之后， 执行功能单一， 可以提高系统的可 靠性。 安注泵降低了注入压头 （ 由高压变为中压， 注入压头范围为 600mWC~1100mWC ), 可以有效降低高压安注误启动事故后果， 避免一回路压力过 高， 也可以减轻或避免蒸汽发生器传热管破裂事故下一回路压力过高而可能导 致的蒸汽发生器满溢， 从而降低该事故下放射性物质向环境排放的可能性。
内置换料水箱位于安全壳内部最低处一堆芯下方地坑位置， 减少了外部灾 害对换料水箱安全性的影响， 提高了事故后应急水源的可靠性， 提高了核电厂 安全性。 在核电站发生事故的情况下， 如果采用外置的换料水箱， 安注系统需 要在液位计配合下进行切换操作。 换料水箱内置后方便汇集来自安全壳喷淋、 管道破口所带来的水源， 与反应堆的地坑结合起来， 起到了筒化设备的作用， 不再需要进行切换操作。 因为内置换料水箱将作为事故后的唯一能动安注水来 源， 可以减少事故后的操作， 避免了可能发生的错误， 降低了系统运行模式切 换失效的潜在风险， 从而提高了系统的可靠性， 增强了电厂的安全性。
下面结合附图和实施例对本发明进行详细的描述。 如图 4 所示， 能动与非能动相结合的堆芯注水热量导出装置， 包括设置在 安全壳内部堆芯下方地坑位置的换料水箱 8 , 换料水箱 8和一回路的冷、 热管段 之间通过安全注入管线相连接， 安全注入管线上设有两台相互独立的中压安注 泵 9和两台相互独立的低压安注泵 10 ,四台安注泵在安全注入管线上并联设置， 位于安全壳外部。 当然， 中压安注泵 9和低压安注泵 10的数量并不局限于两台。 中压安注泵的注入压头范围为 600mWC~11 00mWC , 低压安注泵的注入压头范围为 90mWC~180mWC
事故发生后， 系统接收到安注信号就立即启动中压安注泵 9 和氐压安注泵 10。 安注泵最初利用小流量管线启动， 当反应堆冷却剂系统压力下降到中压安 注泵的关闭注入压力之下时， 中压安注泵开始向反应堆冷却剂系统提供注入。 当反应堆冷却剂系统压力降到低于低压安注泵的关闭扬程时， 低压安注泵开始 向反应堆冷却剂系统提供注入。
在安全壳内还设有非能动的安注箱 1 1和堆芯补水箱 12 , 所述的安注箱 11 通过设有控制阀门的管道与一回路的冷管段 15相连接， 每台安注箱 11与一回 路的冷管段 15相连接的管道上设有隔离阀及止回阀， 所述的堆芯补水箱 12通 过设有控制阀门的管道连接在一回路的热管段 16和冷管段 15之间。 图中 14为 蒸汽发生器。 本实施例可设置三台相互独立的安注箱 11和三台相互独立的堆芯 补水箱 12 , 图 4中只画出了一个系列。
安注箱 11通过设置有控制阀门的管道分别连接在一回路三个环路的冷管段 上， 在一回路系统压力^ 时自动开启止回阀， 将水注入堆芯。 安注箱大部分空 间由硼水占据并由氮气加压， 靠压缩氮气提供驱动压力， 在一回路压力低时， 可以向反应堆压力容器注入高流量的硼水， 从而迅速冷却堆芯。
堆芯补水箱 12高于堆芯设置， 其入口通过常开的压力平衡管线与一回路主 管段热段相连， 从而维持堆芯补水箱处于一回路的压力， 以防止堆芯补水箱开 始注入时发生水锤现象， 堆芯补水箱出口通过隔离阀及止回阀连接在一回路冷 管段上。 堆芯补水箱中的硼水温度和安全壳环境温度相同。 事故工况下隔离阀 开启， 堆芯补水箱借助高度差产生的重力压头， 将冷却剂沿一回路冷段注入压 力容器， 补偿一回路的水位下降， 维持堆芯的浸没和余热导出。 事故工况下如 果一回路难以顺利卸压， 非能动的堆芯补水箱利用压力平衡管线的连通作用， 总能保持一定的驱动压头， 从而保证了高压工况下对一回路的安全注入。
堆芯补水箱可以有两种运行模式： 水循环模式和蒸汽替代模式。 在水循环 模式下， 来自热管段的热水进入堆芯补水箱， 箱中的冷水进入一回路， 这将使 一回路硼化并增加其水装量。 在蒸汽替代模式下， 蒸汽通过压力管线进入堆芯 补水箱， 补偿注入一回路的水。 堆芯补水箱的运行模式取决于一回路的情况。
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芯注水热量导出装置， 包括分别与换料水箱 ( 8 )和一回路的冷、 热管段相连接的安全注入管线， 安全注入管线上设有安 注泵， 其特征在于： 所述的换料水箱（ 8 )设置在安全壳内部堆芯下方地坑位 置， 安注泵设置在安全壳外部； 在安全壳内反应堆的上方还设有非能动的安 注箱 （11 ) 和堆芯补水箱 （I2 ) , 所述的安注箱 （11 ) 通过设有控制阀门的 管道与一回路的冷管段（15 )相连接， 所述的堆芯补水箱 （12 ) 通过设有控 制阀门的管道连接在一回路的热管段（ 16 ) 和冷管段（15 )之间。
2. 如权利要求 1 所述的能动与非能动相结合的堆芯注水热量导出装置， 其特征在于： 所述的安注泵包括两台相互独立的中压安注泵（9)和两台相互独 立的低压安注泵（10), 四台安注泵在安全注入管线上并联设置。
3. 如权利要求 2 所述的能动与非能动相结合的堆芯注水热量导出装置， 其特征在于： 所述的中压安注泵的注入压头范围为 600mWC~1100mWC, 低压安注 泵的注入压头范围为 90mWC~180mWC。
4. 如权利要求 1-3中任意一项所述的能动与非能动相结合的堆芯注水热 量导出装置， 其特征在于： 所述的安注箱 （11 )共有三台， 相互独立设置。
5. 如权利要求 4 所述的能动与非能动相结合的堆芯注水热量导出装置， 其特征在于： 每台安注箱 （11 ) 与一回路的冷管段（15 )相连接的管道上设有 隔离阀及止回阀。
6. 如权利要求 1-3 中任意一项所述的能动与非能动相结合的堆芯注水 热量导出装置， 其特征在于： 所述的堆芯补水箱 （12 )共有三台， 相互独立 设置。
7. 如权利要求 6所述的能动与非能动相结合的堆芯注水热量导出装置， 其特征在于： 每台堆芯补水箱 （12 ) 的入口通过常开的压力平衡管线与一回 路的热管段（ 16 )相连，其出口通过隔离阀及止回阀连接在一回路冷管段（ 15 ) 上。
PCT/CN2013/084046 2012-09-27 2013-09-24 一种能动与非能动相结合的堆芯注水热量导出装置 Ceased WO2014048292A1 (zh)

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