WO2014048289A1 - 一种能动与非能动相结合的二次侧堆芯热量导出装置 - Google Patents

一种能动与非能动相结合的二次侧堆芯热量导出装置 Download PDF

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Publication number
WO2014048289A1
WO2014048289A1 PCT/CN2013/084038 CN2013084038W WO2014048289A1 WO 2014048289 A1 WO2014048289 A1 WO 2014048289A1 CN 2013084038 W CN2013084038 W CN 2013084038W WO 2014048289 A1 WO2014048289 A1 WO 2014048289A1
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Prior art keywords
water supply
passive
steam
secondary side
main
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PCT/CN2013/084038
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English (en)
French (fr)
Inventor
李京彦
史海富
袁霞
于勇
李军
宋代勇
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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 MYPI2015700866A priority Critical patent/MY187908A/en
Application filed by China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to GB1504150.2A priority patent/GB2521549B/en
Publication of WO2014048289A1 publication Critical patent/WO2014048289A1/zh
Anticipated expiration legal-status Critical
Priority to ZA2015/02770A priority patent/ZA201502770B/en
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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 belongs to a reactor design technology, and particularly relates to a secondary side core heat export device combining active and passive. Background technique
  • the steam generator is usually replenished in a dynamic manner. That is, the active secondary side residual heat discharge system, the active secondary side residual heat discharge system is to force the circulation of the secondary side feed water of the steam generator by the auxiliary feed water pump to ensure the residual heat of the core, and Send to the final heat sink.
  • the movable secondary heat recovery system has high heat exchange efficiency.
  • the conventional active secondary side residual heat removal system adopts a combination of a steam pump and an electric pump.
  • the steam pump gradually shows its shortcomings and shortcomings. From the price analysis of equipment materials, the investment cost of steam feed pump is higher than that of electric feed pump. If the steam feed pump and its related system are considered to be about twice the area of the electric feed pump, the space is at least Three times the electric pump, the investment cost of the steam feed pump is more than one time higher than the investment cost of the electric feed pump; in addition, the maintenance cost of the electric feed pump is only 25°/ of the steam feed pump. .
  • Passive technology is a new technology developed in the 1980s. It is characterized by economy, singleness and high reliability, which greatly enhances the inherent safety of the reactor and is usually applied to third-generation nuclear power plants.
  • Typical representative stack types are AP1000, APR_1400. China's introduction of the third generation nuclear power plant AP1000 set up passive
  • the residual heat is discharged from the system.
  • the system extracts the heat of the core by cooling the primary coolant, as shown in Figure 1.
  • 1 is the steam generator
  • 2 is the reactor pressure vessel
  • 3 is the containment tank in the containment.
  • 4 is a passive residual heat removal heat exchanger
  • 5 is a voltage regulator. In the event of a non-L0CA event, the passive residual heat removal heat exchanger 4 will vent the core residual heat.
  • the heat exchanger consists of a set of C-tube bundles attached to the tubesheet and a header disposed at the upper (inlet) and bottom (outlet).
  • the inlet line of the heat exchanger is connected to the heat pipe section of the reactor coolant system, and the outlet line is connected to the lower head cold chamber of the steam generator 1, which forms a passive residual heat with the heat pipe section and the cold pipe section of the reactor coolant system.
  • the natural circulation loop that is discharged.
  • a secondary side core heat deriving device combining active and passive comprising an auxiliary water supply system and a secondary side passive residual heat removal system, wherein the auxiliary water supply system comprises two A redundant water supply series, one end of each water supply series is connected to the auxiliary feed water tank, and the other end is connected with the main water supply pipe of the steam generator; the secondary side passive residual heat removal system includes a plurality of passive residual heat discharge series.
  • Each passive residual heat removal series corresponds to a steam generator of a reactor loop, including a passive residual heat removal cooler, and the upstream steam line of the passive residual heat removal cooler is connected to the main steam line of the steam generator, downstream thereof
  • the condensate line is connected to the main water supply pipe of the steam generator, and the non-dynamic residual heat discharge cooler is placed in the accident cooling water tank, and the passive hydration is further provided between the upstream steam line and the downstream condensate line of the passive residual heat removal cooler. box.
  • the active side and the non-active combined secondary side core heat-extracting device as described above, Among the two water supply series of the auxiliary water supply system, one water supply series includes two parallel 50°/.
  • the capacity of the electric pump, the other water supply series includes two parallel 50% capacity steam pumps; two electric pumps are powered by the emergency power supply, and the two steam pumps are supplied by the main steam line upstream of the main steam isolation valve of the steam generator. Steam; After the two electric pumps and the discharge pipes of the two steam pumps are combined into one main pipe, they are respectively connected to the main water supply pipes of the steam generators.
  • the active side and the passive combined secondary side core heat deriving device wherein each of the auxiliary water supply system and the exhaust pipe of the steam pump are respectively provided with a check valve .
  • the active side and the passive side are combined with the secondary side core heat deriving device, wherein each of the two water supply series of the auxiliary water supply system includes two parallel 50°/.
  • the electric pump of the capacity four electric pumps are powered by the emergency power supply; after the discharge pipes of the four electric pumps are combined into one main pipe, they are respectively connected with the main water supply pipes of the steam generators; the discharge pipes of each electric pump are respectively provided There is a check valve.
  • the active side and the passive side are combined with the secondary side core heat deriving device, wherein the non-dynamic residual heat exhaust cooler is provided with a steam line connected to the main steam line of the steam generator.
  • the isolation valve has two parallel isolation valves connected to the main water supply pipe of the steam generator, and a check valve is arranged downstream of the two parallel isolation valves.
  • the active side and the non-active combined secondary side core heat-extracting device are provided on the pipeline connecting the non-operating water supply tank and the upstream steam line of the passive residual heat exhaust cooler.
  • An isolation valve is provided with two parallel isolation valves on the pipeline connected to the downstream condensate line of the passive residual heat removal cooler, and a check valve is arranged downstream of the two parallel isolation valves.
  • the system guarantees the dynamic and efficient discharge of core residual heat under accident conditions, and the long-term passive discharge of core residual heat in case of accident, improving the dependence of traditional active nuclear power plants on safety-grade power supply, and improving the safety of power plants. ;
  • FIG. 1 is a schematic structural view of a passive residual heat removal system of an AP 1 000 in the prior art
  • FIG. 2 is a schematic structural view of a secondary side core heat deriving device combining active and passive. detailed description
  • the secondary side core heat deriving device combined with the active and passive phases provided by the present invention, in the case of an accident in the nuclear power plant, when the main water supply facility cannot be used, by means of an active manner, relying on the auxiliary water supply system, the core is The heat is exported.
  • the passive secondary heat recovery system is automatically put into operation, and a stable two-phase natural circulation flow is established, and the primary coolant is also formed stably. The natural circulation flows, and finally the core heat is transferred to the accident cooling water tank as the final heat trap through the natural circulation flow of the primary circuit and the secondary circuit.
  • the active system is forced to export the residual heat of the core through the auxiliary feed water pump when the power supply is guaranteed.
  • the passive design is to use the difference between the density of the hot and cold working fluids of the secondary circuit and the cooling circuit, and the vertical difference between the hot and cold working fluids. To establish a natural cycle. Adopting a combination of active and passive solutions to deal with design basis accidents and In the event of a serious accident, the main feed water is lost, maintaining the long-term export of core heat.
  • the active auxiliary water supply system consists of two redundant water supply series, one end of each water supply series connected to the auxiliary water supply tank and the other end connected to the main water supply pipe of the steam generator.
  • the secondary side passive residual heat removal system includes a plurality of passive residual heat discharge series, each passive residual heat removal series corresponds to a reactor loop steam generator, including a passive residual heat removal cooler, and a passive residual heat discharge
  • the upstream steam line of the cooler is connected to the main steam pipe of the steam generator, the downstream condensate line is connected with the main water supply pipe of the steam generator, and the non-dynamic residual heat discharge cooler is placed in the accident cooling water tank, and the passive residual heat is discharged from the cooler.
  • Adopting the secondary side residual heat removal system combined with active and passive to improve the safety level of nuclear power plants is the trend of advanced nuclear power plant design, ensuring the long-term export of core heat in the event of accidents, ensuring the integrity of the core and alleviating the seriousness. The consequences of the accident.
  • the invention will now be described in detail in conjunction with the drawings and embodiments.
  • the auxiliary water supply system has two redundant water supply series.
  • the electric pump subsystem and the steam pump subsystem, and the valves related to the pump suction pipe and the discharge pipe may be included. Wait.
  • one water supply series includes two parallel 50% capacity electric pumps 7
  • the other water supply series includes two parallel 50% capacity steam pumps 8 , which are respectively arranged on the discharge pipes of each electric pump and steam pump.
  • the auxiliary feed water pump absorbs water from the auxiliary feed water tank. In the event of loss of the main feed water, the pump can provide sufficient flow to derivate the residual heat of the core, preventing the coolant from escaping through the regulator relief valve and the steam generator tube plate.
  • the auxiliary water supply system When an accident occurs in the main water supply system, the auxiliary water supply system is put into operation and supplies water to the steam generator.
  • the heat of the reactor coolant system is transferred to the secondary circuit system through the steam generator, and the secondary circuit is discharged into the condenser through the turbine bypass system or discharged to the atmosphere for cooling. This derives the residual heat of the core until the reactor coolant system reaches the operating condition in which the normal residual heat removal system can be put into operation.
  • each water supply series comprises two parallel 50°/.
  • the electric pump of the capacity the four electric pumps are powered by the emergency power supply, and the discharge pipes of each electric pump are respectively provided with check valves; after the discharge pipes of the four electric pumps are combined into one main pipe, respectively, it can occur with multiple steams respectively.
  • the main water supply pipe connection of the device significantly reduces equipment investment and maintenance costs and reduces system footprint.
  • the reason why the auxiliary water supply system can replace the steam pump with the electric pump to achieve the cost reduction is mainly because the combination of the secondary side passive residual heat removal system ensures the diversity of the system settings.
  • the secondary side passive residual heat removal system includes a plurality of passive residual heat removal series, and a passive residual heat removal series is arranged on the secondary side of the steam generator of each loop of the reactor, and each series includes a passive residual heat removal cooler. 14.
  • the upstream steam line of the passive residual heat exhaust cooler 14 is connected to the main steam line 11 of the steam generator 9, the downstream condensate line is connected to the main feed water line 10 of the steam generator 9, and the passive residual heat discharge cooler 14 is placed.
  • a passive water supply tank 12 is further disposed between the upstream steam line and the downstream condensing line of the passive residual heat removal cooler 14 .
  • the passive secondary side residual heat removal system is put into operation, without exceeding the specified fuel design limits and coolant pressure boundary design conditions. , to extract the residual heat of the core and the heat storage of the equipment in the reactor coolant system, and maintain the reactor in a safe shutdown state within 72 hours.
  • the steam line is connected to the inlet nozzle of the passive residual heat removal cooler 14, and the passive residual heat removal cooler 14 is disposed in the accident cooling water tank 13. During the entire operation, the passive residual heat removal cooler 14 is required to be immersed in the water, and no dew is allowed.
  • the condensate pipe is led out from the non-dynamic residual heat exhaust cooler outlet, and the condensate pipe outlet is connected to the main feed water pipe and the auxiliary feed water pipe of the steam generator.
  • Two parallel closed pneumatic isolation valves are arranged on the condensate pipe to achieve isolation during system standby and ensure that the system is in need
  • the condensate line can be smoothly connected when the system is put into operation, and a check valve is arranged downstream to prevent the steam generator from feeding water through the condensate pipe.
  • An electric isolation valve is arranged on the steam line connecting the passive residual heat exhaust cooler 14 and the main steam line 11 of the steam generator 9.
  • the electric isolation valve on the system steam line remains normally open.
  • the pneumatic isolation valve on the condensate line remains normally closed, and the non-dynamic residual heat is discharged from the side of the cooler tube filled with water.
  • the pneumatic isolation valve on the condensate line is opened, the system is put into operation, and the non-dynamic residual heat is discharged into the secondary side of the steam generator under the action of gravity, and is heated by the residual heat of the core. Steam, steam enters the passive residual heat and exits the cooler tube, and exchanges heat with the cooling water in the accident cooling water tank.
  • the steam transfers the heat to the cooling water and is condensed into water.
  • the condensed water returns to the steam generator twice under the action of gravity. Side, thus completing the natural circulation of the steam-condensation circuit.
  • the water in the accident cooling water tank is reduced by continuous heat evaporation, and its water volume ensures that the system can continue to operate for 72 hours.
  • Each series is provided with a passive water supply tank 12, the upper part of which is connected to the upstream steam line of the passive residual heat exhaust cooler 14 through an isolation valve, and the lower part is passed through two parallel arranged isolation valves and a check valve and passive The residual heat is discharged from the downstream condensate line of the cooler.
  • the water in the passive fill tank is injected into the secondary side of the steam generator to compensate for the loss of steam on the secondary side of the steam generator and the shrinkage of the water volume.
  • the passive secondary side residual heat removal system utilizes the temperature difference and height difference between the reactor part and the steam generator part.
  • a certain natural circulation capacity the heat of the reactor is transferred to the steam generator, the natural circulation of the reactor coolant circuit is completed, the residual heat of the core is derived, and the safety of the core is ensured.
  • the invention combines the active auxiliary water supply system and the passive secondary side residual heat removal system to improve the safety of the nuclear power plant under accident conditions.
  • the requirements for the diversity of the system settings can be met, and the auxiliary water supply system can be designed accordingly. It can save a lot of money in investment and maintenance costs, reduce the floor space, and provide system layout. More favorable conditions.

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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二次侧堆芯热量导出装置 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二次侧 堆芯热量导出装置。 背景技术
反应堆停堆后， 由于堆芯的剩余裂变以及裂变产物衰变产生的热量在很长 一段时间内仍需要排出， 否则会导致冷却剂沸腾甚至堆芯熔化的严重事故。 在 传统压水堆核电厂设计中， 通常采用能动的方式给蒸汽发生器补水。 即能动型 二次侧余热排出系统， 能动二次侧余热排出系统是在电源供给有保障的情况下， 通过辅助给水泵驱动蒸汽发生器二次侧给水进行强迫循环， 将堆芯余热导出， 并送至最终热阱。 能动二次侧余热排出系统换热效率高， 但在发生全厂断电时， 正常电源和可靠电源供电同时丧失， 系统就丧失排出堆芯余热的功能。 所以能 动二次侧余热排出系统受电源可靠性影响较大， 安全性差。
传统能动型二次侧余热排出系统采用汽动泵与电动泵相结合的方案， 随着 技术的不断进步， 汽动泵逐渐显现出它的缺点和不足。 单从设备材料价格分析， 汽动给水泵投资费用就高出电动给水泵投资费用 , 如果再考虑汽动给水泵及 其相关系统占地面积大约是电动给水泵的 2倍， 占用空间高度至少是电动泵的 3 倍， 汽动给水泵投资费用比电动给水泵投资费用高出 1 倍以上； 另外电动给水 泵的维修费用仅为汽动给水泵的 25°/。。
非能动技术是 20世纪 80年代发展起来的新技术， 其特点是经济、 筒单且 可靠性高， 使反应堆的固有安全性大大提高， 通常应用于第三代核电站。 典型 代表堆型是 AP1000、 APR_1400。 我国引进的第三代核电站 AP1000设置了非能动 余热排出系统， 该系统是通过冷却一回路冷却剂， 将堆芯的热量导出， 如图 1 所示， 图中， 1为蒸汽发生器， 2为反应堆压力容器， 3为安全壳内置换料水箱， 4为非能动余热排出热交换器， 5为稳压器。 在非 L0CA事件时， 非能动余热排 出热交换器 4将应急排出堆芯余热。 该热交换器由一组连接在管板上的 C型管 束和布置在上部 （入口）和底部 （出口的）封头组成。 热交换器的入口管线与 反应堆冷却剂系统热管段相连接， 出口管线与蒸汽发生器 1 的下封头冷腔室相 连接， 它们与反应堆冷却剂系统热管段和冷管段组成了一个非能动余热排出的 自然循环回路。 发明内容
本发明的目的是为了提高核电站的安全水平， 提供一种能动与非能动相结 合的二次侧堆芯热量导出装置， 保证在事故情况下堆芯热量的长期导出， 緩解 严重事故后果。 本发明的技术方案如下： 一种能动与非能动相结合的二次侧堆芯热量导出 装置， 包括辅助给水系统和二次侧非能动余热排出系统， 其中， 所述的辅助给 水系统包括两个冗余的供水系列， 每个供水系列的一端连接辅助给水箱， 另一 端与蒸汽发生器的主给水管道相连接； 所述的二次侧非能动余热排出系统包括 若干个非能动余热排出系列， 每个非能动余热排出系列与一个反应堆环路的蒸 汽发生器相对应， 包括一台非能动余热排出冷却器， 非能动余热排出冷却器的 上游蒸汽管线连接蒸汽发生器的主蒸汽管道， 其下游凝水管线与蒸汽发生器的 主给水管道连接， 非能动余热排出冷却器置于事故冷却水箱内， 在非能动余热 排出冷却器的上游蒸汽管线和下游凝水管线之间还设有非能动补水箱。 进一步， 如上所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其 中， 所述的辅助给水系统的两个供水系列中， 一个供水系列包括两台并联的 50°/。 容量的电动泵， 另一个供水系列包括两台并联的 50%容量的汽动泵； 两台电动泵 由应急电源供电， 两台汽动泵由蒸汽发生器主蒸汽隔离阀上游的主蒸汽管线供 汽； 两台电动泵和两台汽动泵的排出管合并成一条母管后， 分别与各蒸汽发生 器的主给水管道连接。
更进一步， 如上所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其中， 所述的辅助给水系统的每台电动泵和汽动泵的排出管上分别设有止回阀。 进一步， 如上所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其 中， 所述的辅助给水系统的两个供水系列中， 每个供水系列包括两台并联的 50°/。 容量的电动泵， 四台电动泵由应急电源供电； 四台电动泵的排出管合并成一条 母管后， 分别与各蒸汽发生器的主给水管道连接； 每台电动泵的排出管上分别 设有止回阀。 进一步， 如上所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其 中， 在所述的非能动余热排出冷却器与蒸汽发生器的主蒸汽管道连接的蒸汽管 线上设有一个隔离阀， 与蒸汽发生器的主给水管道连接的凝水管线上设有两个 并联的隔离阀， 两个并联的隔离阀下游设置一个止回阀。 进一步， 如上所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其 中， 在所述的非能动补水箱与非能动余热排出冷却器的上游蒸汽管线相连接的 管线上设有一个隔离阀， 与非能动余热排出冷却器的下游凝水管线相连接的管 线上设有两个并联的隔离阀， 两个并联的隔离阀下游设置一个止回阀。 本发明的有益效果如下: ( 1 )采用能动与非能动相结合的二次侧余热导出方案排出堆芯的热量， 提 高了反应堆的安全性；
( 2 )系统保证在事故工况下能动高效的排出堆芯余热， 以及在事故情况下 长期非能动的排出堆芯余热， 改进传统能动型核电厂对安全级电源的依赖， 提 高电厂的安全性；
( 3 )由于采用非能动系统， 可以满足系统设置多样性的要求， 从而可以采 用电动泵代替汽动泵， 不仅在投资费用和维修费用上节省大量资金， 另外也减 少的占地面积， 为布置提供了更有利的条件；
( 4 ) 大大降低了人因失误的可能性；
( 5 ) 可以显著降低堆芯损坏概率及大量放射性向环境释放概率。 附图说明
图 1为现有技术中 AP 1 000的非能动余热排出系统结构示意图；
图 2为能动与非能动相结合的二次侧堆芯热量导出装置的结构示意图。 具体实施方式
本发明所提供的能动与非能动相结合的二次侧堆芯热量导出装置， 在核电 站发生事故的情况下， 当主给水设施不能使用时， 通过能动的方式， 依靠辅助 给水系统， 将堆芯内的热量导出。 在发生全厂断电事故且辅助给水系统汽动泵 丧失的情况下， 非能动二次侧余热排出系统自动投入运行， 并建立稳定的两相 自然循环流动， 同时一回路冷却剂也形成稳定的自然循环流动， 最终通过一回 路和二回路的自然循环流动将堆芯热量传递到作为最终热阱的事故冷却水箱。
能动系统是在电源有保障的情况下， 通过辅助给水泵强迫将堆芯余热导出， 非能动设计是利用二回路和冷却回路冷热工质的密度差， 以及冷热工质竖直位 差， 来建立自然循环。 采用能动与非能动结合的方案能够应对设计基准事故和 严重事故下主给水丧失， 维持堆芯热量的长期导出。
能动的辅助给水系统包括两个冗余的供水系列， 每个供水系列的一端连接 辅助给水箱， 另一端与蒸汽发生器的主给水管道相连接。 二次侧非能动余热排 出系统包括若干个非能动余热排出系列， 每个非能动余热排出系列与一个反应 堆环路的蒸汽发生器相对应， 包括一台非能动余热排出冷却器， 非能动余热排 出冷却器的上游蒸汽管线连接蒸汽发生器的主蒸汽管道， 其下游凝水管线与蒸 汽发生器的主给水管道连接， 非能动余热排出冷却器置于事故冷却水箱内， 在 非能动余热排出冷却器的上游蒸汽管线和下游凝水管线之间还设有非能动补水 相。
采用能动与非能动相结合的二次侧余热排出系统来提高核电厂的安全水平 是先进核电站设计的趋势， 保证在事故情况下堆芯热量的长期导出， 保证了堆 芯的完整性， 緩解严重事故后果。 下面结合附图和实施例对本发明进行详细的描述。
实施例
如图 2所示， 辅助给水系统有两个冗余的供水系列， 一种具体的实施方式 中， 可以包括电动泵子系统和汽动泵子系统， 以及与泵吸入管和排出管有关的 阀门等。 其中， 一个供水系列包括两台并联的 50%容量的电动泵 7 , 另一个供水 系列包括两台并联的 50%容量的汽动泵 8 , 每台电动泵和汽动泵的排出管上分别 设有止回阀； 两台电动泵 7 由应急电源供电， 两台汽动泵 8 由蒸汽发生器主蒸 汽隔离阀上游的主蒸汽管线供汽； 两台电动泵 7和两台汽动泵 8的排出管合并 成一条母管后， 可以分别与多台蒸汽发生器的主给水管道连接。 辅助给水泵从 辅助给水箱中吸水。 在失去主给水的情况下， 水泵能够提供足够的流量， 以导 出堆芯余热， 防止冷却剂通过稳压器卸压阀泄出和蒸汽发生器管板棵露。
在主给水系统发生事故时， 辅助给水系统投入运行， 向蒸汽发生器供水， 反应堆冷却剂系统的热量通过蒸汽发生器传给二回路系统， 二回路系统通过汽 轮机旁通系统排入凝汽器或排向大气冷却。 这样导出堆芯余热， 直到反应堆冷 却剂系统达到正常余热排出系统可投入运行的工况。
在辅助给水系统的另一种实施方式中， 将两台汽动泵用电动泵替代， 即每 个供水系列包括两台并联的 50°/。容量的电动泵， 四台电动泵由应急电源供电， 每 台电动泵的排出管上分别设有止回阀； 四台电动泵的排出管合并成一条母管后， 可以分别与多台蒸汽发生器的主给水管道连接。 这种方式可以明显降低设备的 投资和维护成本， 并减少系统的占地面积。 辅助给水系统中之所以能采用电动 泵替代汽动泵， 实现成本的降低， 主要是因为二次侧非能动余热排出系统的结 合设置， 保证了系统设置多样性的要求。
二次侧非能动余热排出系统包括若干个非能动余热排出系列， 反应堆每个 环路的蒸汽发生器二次侧都设置一个非能动余热排出系列， 每个系列包括一台 非能动余热排出冷却器 14 ,非能动余热排出冷却器 14的上游蒸汽管线连接蒸汽 发生器 9的主蒸汽管道 11 ,其下游凝水管线与蒸汽发生器 9的主给水管道 10连 接， 非能动余热排出冷却器 14置于事故冷却水箱 1 3 内， 在非能动余热排出冷 却器 14的上游蒸汽管线和下游凝水管线之间还设有非能动补水箱 12。
在发生全厂断电事故且辅助给水系统汽动泵系列失效工况下， 非能动二次 侧余热排出系统投入运行， 在不超过规定的燃料设计限值和冷却剂压力边界设 计条件的前提下， 导出堆芯余热及反应堆冷却剂系统各设备的储热， 在 72小时 内将反应堆维持在安全的停堆状态。
蒸汽管线与非能动余热排出冷却器 14入口接管嘴相连， 非能动余热排出冷 却器 14布置在事故冷却水箱 1 3 中。 在整个运行期间， 要求非能动余热排出冷 却器 14浸泡在水中， 不允许棵露。 凝水管由非能动余热排出冷却器出口引出， 凝水管出口与蒸汽发生器的主给水管道和辅助给水管道相连。 凝水管道上设置 了两个并联的常关气动隔离阀， 实现系统备用期间的隔离， 同时保证在需要系 统投入时凝水管线能够顺利连通， 下游设置一个止回阀， 以防止蒸汽发生器给 水通过凝水管道旁流。
在所述的非能动余热排出冷却器 14与蒸汽发生器 9的主蒸汽管道 11连接 的蒸汽管线上设有一个电动隔离阀， 机组正常运行期间， 系统蒸汽管线上的电 动隔离阀保持常开， 凝水管线上的气动隔离阀保持常关， 非能动余热排出冷却 器管侧充满水。 在系统投入信号发出后， 凝水管线上的气动隔离阀开启， 系统 投入运行， 非能动余热排出冷却器管内的水在重力作用下注入蒸汽发生器二次 侧， 被堆芯余热加热后变成蒸汽， 蒸汽进入非能动余热排出冷却器管内， 与事 故冷却水箱里的冷却水进行热量交换， 蒸汽将热量传递给冷却水后被冷凝为水， 冷凝水在重力的作用下返回蒸汽发生器二次侧， 从而完成蒸汽 -凝水回路的自然 循环。 事故冷却水箱中的水由于持续受热蒸发而减少， 其水容积能够保证系统 持续运行 72小时。
每个系列设置一台非能动补水箱 12 , 其上部通过一个隔离阀与非能动余热 排出冷却器 14的上游蒸汽管线相连， 下部通过两个并联布置的隔离阀和一台止 回阀与非能动余热排出冷却器的下游凝水管线相连。 在系统投入运行时， 非能 动补水箱中的水注入蒸汽发生器二次侧， 以补偿蒸汽发生器二次侧蒸汽的丧失 和水体积的收缩。
在全厂断电事故叠加辅助给水系统汽动泵失效事故工况下， 由于主泵停 运， 非能动二次侧余热排出系统利用系统在反应堆部分及蒸汽发生器部分的温 差和高度差， 具有一定的自然循环能力， 将反应堆的热量向蒸汽发生器传递， 完成反应堆冷却剂回路的自然循环， 导出堆芯余热， 保障堆芯的安全。
本发明将能动的辅助给水系统和非能动的二次侧余热排出系统相结合， 从总体上提高了事故工况下核电站的安全性。 同时， 由于采用了非能动系统， 可以满足系统设置多样性的要求， 辅助给水系统可以进行相应的改进设计， 在 投资费用和维修费用上能够节省大量资金， 并减少占地面积， 为系统布置提供 了更加有利的条件。
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二次侧堆芯热量导出装置， 其特征在于： 包 括辅助给水系统和二次侧非能动余热排出系统， 所述的辅助给水系统包括两个 冗余的供水系列， 每个供水系列的一端连接辅助给水箱 （6 ), 另一端与蒸汽发 生器的主给水管道（10 )相连接； 所述的二次侧非能动余热排出系统包括若干 个非能动余热排出系列， 每个非能动余热排出系列与一个反应堆环路的蒸汽发 生器相对应，包括一台非能动余热排出冷却器（ 14 ) ,非能动余热排出冷却器（ 14 ) 的上游蒸汽管线连接蒸汽发生器（9 ) 的主蒸汽管道（1 1 ), 其下游凝水管线与 蒸汽发生器（ 9 ) 的主给水管道（ 10 )连接， 非能动余热排出冷却器（ 14 )置于 事故冷却水箱 （1 3 ) 内， 在非能动余热排出冷却器（14 ) 的上游蒸汽管线和下 游凝水管线之间还设有非能动补水箱 （12 )。
2. 如权利要求 1所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其特征在于： 所述的辅助给水系统的两个供水系列中， 一个供水系列包括两台 并联的 50%容量的电动泵（7 ), 另一个供水系列包括两台并联的 50%容量的汽动 泵（8 ); 两台电动泵（7 ) 由应急电源供电， 两台汽动泵（8 ) 由蒸汽发生器主 蒸汽隔离阀上游的主蒸汽管线供汽； 两台电动泵和两台汽动泵的排出管合并成 一条母管后， 分别与各蒸汽发生器的主给水管道连接。
3. 如权利要求 2所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其特征在于： 所述的辅助给水系统的每台电动泵和汽动泵的排出管上分别设有 止回阀。
4. 如权利要求 1所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其特征在于： 所述的辅助给水系统的两个供水系列中， 每个供水系列包括两台 并联的 50%容量的电动泵， 四台电动泵由应急电源供电； 四台电动泵的排出管合 并成一条母管后， 分别与各蒸汽发生器的主给水管道连接。
5. 如权利要求 4所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其特征在于： 所述的辅助给水系统的每台电动泵的排出管上分别设有止回阀。
6. 如权利要求 1所述的能动与非能动相结合的二次侧堆芯热量导出装置， 其特征在于： 在所述的非能动余热排出冷却器（14 ) 与蒸汽发生器的主蒸汽管 道（ 11 )连接的蒸汽管线上设有一个隔离阀， 与蒸汽发生器的主给水管道（ 10 ) 连接的凝水管线上设有两个并联的隔离阀， 两个并联的隔离阀下游设置一个止 回阀。
7. 如权利要求 1 所述的能动与非能动相结合的二次侧堆芯热量导出装 置，其特征在于：在所述的非能动补水箱（ 1 2 )与非能动余热排出冷却器（ 14 ) 的上游蒸汽管线相连接的管线上设有一个隔离阀， 与非能动余热排出冷却器 ( 14 ) 的下游凝水管线相连接的管线上设有两个并联的隔离阀， 两个并联的 隔离阀下游设置一个止回阀。
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