WO2015014046A1 - 核电站蒸汽发生器辅助给水系统 - Google Patents

核电站蒸汽发生器辅助给水系统 Download PDF

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Publication number
WO2015014046A1
WO2015014046A1 PCT/CN2013/087740 CN2013087740W WO2015014046A1 WO 2015014046 A1 WO2015014046 A1 WO 2015014046A1 CN 2013087740 W CN2013087740 W CN 2013087740W WO 2015014046 A1 WO2015014046 A1 WO 2015014046A1
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Prior art keywords
steam generator
water supply
pump
nuclear power
steam
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PCT/CN2013/087740
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English (en)
French (fr)
Inventor
咸春宇
施金冯
唐辉
王茹
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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Publication of WO2015014046A1 publication Critical patent/WO2015014046A1/zh
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K5/00—Plants characterised by use of means for storing steam in an alkali to increase steam pressure, e.g. of Honigmann or Koenemann type
    • F01K5/02—Plants characterised by use of means for storing steam in an alkali to increase steam pressure, e.g. of Honigmann or Koenemann type used in regenerative installation
    • 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

Definitions

  • the present invention relates to the safety design of an active type pressurized water reactor nuclear power plant, and more particularly to a nuclear power plant steam generator auxiliary water supply system.
  • auxiliary water supply also called emergency water supply
  • auxiliary water supply also called emergency water supply
  • a more mature solution is to use an active device (pump) to take water from a preliminary water source (such as a water tank) and then inject it into the steam generator.
  • a preliminary water source such as a water tank
  • the auxiliary steam supply system of the steam generator of the nuclear power plant is a special safety system, the configuration of the system needs to consider the failure of a single equipment, the complete loss of power (such as power supply), the rupture of the water supply pipeline, etc., which is reasonable for the system configuration scheme. Reliability has raised high demands.
  • a known technology auxiliary water supply system includes a shared water tank, two 50% capacity electric pumps, two 50% capacity steam pumps, valves, pipes and meters, etc.
  • the system also has two deaerators shared by the units.
  • two electric pumps and two steam pumps are connected to the three loop steam generators by the mother pipe distribution method, the feed water flow is injected into the steam generator through the main water supply pipe, and the steam generator is designed by the system configuration.
  • the water supply flow requirement is designed to meet the water supply flow requirements of the steam generator under accident conditions through pumps, flow restricting orifices and feed water flow regulating valves.
  • the above auxiliary water supply system has the following disadvantages: 1) Due to the injection mode of the mother pipe distribution, when a steam generator has a water supply pipe rupture accident, the injection flow rate to the three steam generators may be mismatched, that is, a large amount of water supply From the break, the effective injection flow is reduced; 2) the water quality is high, the deaerator is required, and the operation and maintenance cost is high; 3) only one water tank is used as the water source, and the reliability is low; 4) each There is only one isolation valve on the injection line, and if the isolation fails, the steam generator may be at risk of overflow.
  • Another known technology auxiliary water supply system includes four independent emergency water supply series, each series consisting of a pool, a 50% capacity electric pump, valves, pipes and meters, four series of electric pump suction side and The outlet sides are connected by a header.
  • the emergency feed water is injected into the steam generator through the emergency water supply line independent of the main water supply system, and is designed to meet the water supply flow requirement of the steam generator under the accident condition through the pump, the power limiting valve and the steam generator liquid level regulating valve.
  • the object of the present invention is to provide a highly reliable nuclear power plant steam generator auxiliary water supply system.
  • the present invention provides a nuclear power plant steam generator auxiliary water supply system comprising at least three independent series of electric pumps and at least two series of steam pumps connected to the steam generator in a mother pipe distribution manner.
  • each of the series of electric pump series includes a water storage tank, an electric pump, a flow regulating valve, a steam generator water level regulating valve, a safety outer electric isolation valve and a safety shell.
  • Internal check valves each of which is connected to a steam generator via a separate line.
  • the suction side of the plurality of electric pumps is connected through the mother pipe, and the outlet side is also connected through the mother pipe.
  • the steam pump of each column The series of steam pumps are connected in parallel with the electric pump.
  • the suction side of the steam pump is connected to the suction side of the electric pump, and the outlet side of the steam pump is connected to the outlet side of the electric pump by the mother pipe distribution. After the injection line.
  • a demineralized replenishing line connected to the suction side of the electric pump suction side is also included.
  • the water storage tank and the water replenishing line connected to the main pipe of the suction side of the electric pump are also included.
  • the water storage tank has two additional water supply lines, and each of the water storage tanks and the water replenishing pipeline are provided with a replenishing water pump.
  • each of the series of steam pump includes a steam pump and a water storage tank shared with the electric pump series, a steam generator water level regulating valve, and a safety shell electric motor. Isolation valve and a containment check valve.
  • the steam pump of each of the series of steam pump pumps relies on steam generated by the steam generator itself as a driving force.
  • the auxiliary steam water supply system of the nuclear power plant of the present invention improves the reliability of the system through the independent electric pump series and the series of the steam pump, and significantly enhances the water supply of the secondary side of the steam generator.
  • FIG. 1 is a schematic structural view of an auxiliary water supply system for a steam generator of a nuclear power plant according to the present invention. detailed description
  • the nuclear power plant steam generator auxiliary water supply system of the present invention comprises three independent electric pump series, two columns of steam pump series, one desalin supply line 40 and two water storage tanks and water replenishing line 42.
  • Each row of electric pump series includes a water storage tank 50, an electric pump 52, a flow regulating valve 54, a steam generator water level regulating valve 56, a containment electric isolation valve 57 and a containment check valve 58.
  • Each electric pump 52 is connected to a steam generator 70 through a separate injection line 59. Further, the suction port sides of the three electric pumps 52 are connected by the mother pipe 62, and the outlet side is connected by the mother pipe 64.
  • the demineralized replenishing line 40 and the water storage tank refilling line 42 are respectively connected to the mother pipe 62 of the suction port side of the electric pump 52, and each column of the water storage tank refilling line 42 is provided with a replenishing water pump 44.
  • Each series of steam pump includes a steam pump 60 and a water storage tank 50 shared with the electric pump series, a steam generator water level regulating valve 56, a safety outer electric isolation valve 57 and a safety enclosure inner check.
  • Valve 58 both of the steam pumps 60 are connected in parallel with the electric pump 52, and the suction port side of the steam pump 60 is connected to the mother pipe 62 on the suction port side of the electric pump 52, and the outlet side of the steam pump 60 passes through the mother.
  • the tube 61 is connected to an injection line 59 after the outlet side of the electric pump 52. Since the steam pump 60 relies on the steam generated by the steam generator 70 itself as a driving force, the series of the steam pump can supply the steam to the steam generator 70 when the power source is completely lost, and derive the heat of the reactor.
  • the number of steam generators 70 exceeds three, the number of steam pump and independent electric pump series can be increased according to actual conditions.
  • Each column of injection injection line 59 has two isolation valves 57, 58, which can reliably achieve water supply isolation, effectively preventing steam generator 70 from overflowing;
  • the nuclear power plant steam generator auxiliary water supply system of the invention has higher system reliability, and greatly enhances the deep defense means of the secondary side water supply of the steam generator 70.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Mechanical Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

一种核电站蒸汽发生器辅助给水系统，其包括至少三列独立的电动泵（52）系列和至少两列以母管（62）分配方式连接至蒸汽发生器（70）的汽动泵（60）系列。上述核电站蒸汽发生器辅助给水系统通过独立的电动泵系列和汽动泵系列相配合的方式，提高了系统的可靠性，显著增强了蒸汽发生器二次侧给水的纵深防御手段。

Description

核电站蒸汽发生器辅助给水系统 技术领域
本发明涉及能动型压水堆核电站安全设计， 更具体地说， 本发明涉及一种 核电站蒸汽发生器辅助给水系统。
说
背景技术
对于能动型压水堆核电站技术， 在发生事故或主给水 /启停给水不可用的情 书
况下， 需要向蒸汽发生器提供辅助给水 (又称应急给水)， 维持蒸汽发生器水位， 通过蒸汽发生器导出一回路的堆芯热量。 为实现蒸汽发生器的辅助给水， 较为 成熟的方案是使用能动装置 (泵)从预备水源 (如水箱 )取水后，注入蒸汽发生器中。 由于核电站蒸汽发生器辅助给水系统是专设安全系统， 其配置方案中， 需要考 虑单一设备的故障、 完全失去动力 (如电源）、 给水管道破裂等事故的发生， 这对 于系统配置方案的合理性、 可靠性提出了很高的要求。
一种已知技术的辅助给水系统包括一个共用水箱、 两台 50%容量电动泵、 两台 50%容量汽动泵、 阀门、 管道和仪表等， 系统内还设置有两个机组共用的 除氧装置， 以便为水箱提供除氧水。 其中， 两台电动泵和两台汽动泵分别采用 母管分配方式连接至三个环路的蒸汽发生器， 给水流量通过主给水管道注入蒸 汽发生器， 并通过系统配置设计满足蒸汽发生器的给水流量要求， 通过泵、 限 流孔板和给水流量调节阀等设计满足事故工况下蒸汽发生器的给水流量要求。 但是， 上述辅助给水系统存在以下不足： 1)由于采用了母管分配的注入方式， 当 一个蒸汽发生器发生给水管道破裂事故， 向三个蒸汽发生器的注入流量会发生 失配， 即大量给水从破口流出， 有效注入流量减少； 2)对水质要求高， 需要除氧 配套装置， 运行维护费用较高； 3)只有一个水箱作为水源， 可靠性较低； 4)每个 注入管线上只有一个隔离阀， 如果隔离失败， 蒸汽发生器可能有满溢风险。 另一种已知技术的辅助给水系统包括四个独立的应急给水系列， 每系列由 一个水池、 一台 50%容量电动泵、 阀门、 管道和仪表等组成， 四个系列的电动 泵吸入侧及出口侧均通过集管方式连接。 应急给水通过与主给水系统相独立的 应急给水管线注入蒸汽发生器， 并通过泵、 功率限制阀和蒸汽发生器液位调节 阀等设计满足事故工况下蒸汽发生器的给水流量要求。 但是， 由于四台泵都是 电动泵， 不仅无法完全满足美国核电用户要求文件和中华人民共和国能源行业 标准-《压水堆核电厂应急给水系统设计准则》（征求意见稿）中关于泵的驱动方 式多样性的要求， 而且当发生完全丧失电源 (类似福岛事件)的极端情况下， 辅助 给水系统将失效。
有鉴于此， 确有必要提供一种可靠性较高的核电站蒸汽发生器辅助给水系 统。 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蒸汽发生器辅助给水系 统。
为了实现上述发明目的， 本发明提供了一种核电站蒸汽发生器辅助给水系 统， 其包括至少三列独立的电动泵系列和至少两列以母管分配方式连接至蒸汽 发生器的汽动泵系列。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 所述每列电动泵 系列都包括储水箱、 电动泵、 流量调节阀、 蒸汽发生器水位调节阀、 安全壳外 电动隔离阀和安全壳内止回阀， 其中每台电动泵都通过独立的管线连接至一台 蒸汽发生器。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 所述多台电动泵 的吸入口侧都通过母管连接， 出口侧也都通过母管连接。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 所述每列汽动泵 系列的汽动泵都以与电动泵并联的方式接入， 汽动泵的吸入口侧连接至电动泵 吸入口侧母管， 汽动泵的出口侧采用母管分配方式连接至电动泵出口侧后的注 入管线。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 还包括连接至电 动泵吸入口侧母管的除盐水补给管线。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 还包括连接至电 动泵吸入口侧母管的储水箱再补水管线。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 所述储水箱再补 水管线为两条， 每条储水箱再补水管线都设有再补水泵。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 所述每列汽动泵 系列都包括汽动泵以及与电动泵系列共用的储水箱、 蒸汽发生器水位调节阀、 一个安全壳外电动隔离阀和一个安全壳内止回阀。
作为本发明核电站蒸汽发生器辅助给水系统的一种改进， 所述每列汽动泵 系列的汽动泵都是依靠蒸汽发生器自身产生的蒸汽作为驱动力。
与现有技术相比， 本发明核电站蒸汽发生器辅助给水系统通过独立的电动 泵系列与汽动泵系列相配合的方式， 提高了系统的可靠性， 显著增强了蒸汽发 生器二次侧给水的纵深防御手段。 附图说明
下面结合附图和具体实施方式， 对本发明核电站蒸汽发生器辅助给水系统 及其有益效果进行详细说明， 其中：
图 1为本发明核电站蒸汽发生器辅助给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， 本发明核电站蒸汽发生器辅助给水系统包括三列独立的 电动泵系列、 两列汽动泵系列、 一条除盐水补给管线 40和两条储水箱再补水管 线 42。
每列电动泵系列都包括一个储水箱 50、一台电动泵 52、一个流量调节阀 54、 一个蒸汽发生器水位调节阀 56、一个安全壳外电动隔离阀 57和一个安全壳内止 回阀 58 , 每台电动泵 52都通过独立的注入管线 59连接至一台蒸汽发生器 70。 另夕卜， 三个电动泵 52的吸入口侧通过母管 62连接， 出口侧通过母管 64连接。
除盐水补给管线 40和储水箱再补水管线 42分别连接至电动泵 52吸入口侧 的母管 62, 每列储水箱再补水管线 42都设有再补水泵 44。
每列汽动泵系列都包括一台汽动泵 60以及与电动泵系列共用的一个储水箱 50、 一个蒸汽发生器水位调节阀 56、一个安全壳外电动隔离阀 57和一个安全壳 内止回阀 58。 换言之， 两台汽动泵 60都以与电动泵 52并联的方式接入， 汽动 泵 60的吸入口侧连接至电动泵 52吸入口侧的母管 62,汽动泵 60的出口侧通过 母管 61连接至电动泵 52出口侧后的注入管线 59。由于汽动泵 60是依靠蒸汽发 生器 70自身产生的蒸汽作为驱动力， 因此汽动泵系列可在完全丧失电源时向蒸 汽发生器 70提供给水， 导出反应堆热量。
在本发明的其他实施方式中， 如果蒸汽发生器 70的数量超过三个时， 可以 根据实际情况增加汽动泵和独立电动泵系列的数量。
本发明核电站蒸汽发生器辅助给水系统通过独立的电动泵系列与汽动泵系 列相配合的方式， 取得了以下有益效果：
1) 克服了给水管道破裂带来的不利影响： 使用三列电动泵系列为蒸汽发生 器 70补水时， 由于三列电动泵系列是独立的注入管线， 因此发生给水管道破裂 事故而隔离其中一列后， 并不会影响其他两列的给水流量；
2)解决了完全失去电源情况下的供水问题：由于汽动泵 60的驱动力来自蒸 汽发生器 70产生的蒸汽， 因此， 不依赖于外部电源就可以为蒸汽发生器 70提 供给水， 有效解决了完全失去电源情况下的供水问题；
3) 采用三个独立的储水箱 50, 增强了水源的可靠性；
4) 防止了蒸汽发生器 70满溢：每列注入注入管线 59上都有两个隔离阀 57、 58, 能够可靠地实现给水隔离， 有效防止蒸汽发生器 70满溢；
5)增强了系统的纵深防御能力： 电动泵 52和汽动泵 60组合配置， 符合驱 动方式多样性的要求， 增强了系统的纵深防御能力。
可见， 与现有技术相比， 本发明核电站蒸汽发生器辅助给水系统具有更高 的系统可靠性， 大大增强了蒸汽发生器 70二次侧给水的纵深防御手段。
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. 一种核电站蒸汽发生器辅助给水系统， 其特征在于： 所述核电站蒸汽发 生器辅助给水系统包括至少三列独立的电动泵系列和至少两列以母管分配方式 连接至蒸汽发生器的汽动泵系列。
2. 根据权利要求 1所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 所述每列电动泵系列都包括储水箱、 电动泵、 流量调节阀、 蒸汽发生器水位调 节阀、 安全壳外电动隔离阀和安全壳内止回阀， 其中， 每台电动泵都通过独立 的管线连接至一台蒸汽发生器。
3. 根据权利要求 2所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 所述多台电动泵的吸入口侧都通过母管连接， 出口侧也都通过母管连接。
4. 根据权利要求 3所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 所述每列汽动泵系列的汽动泵都以与电动泵并联的方式接入， 汽动泵的吸入口 侧连接至电动泵吸入口侧母管， 汽动泵的出口侧采用母管分配方式连接至电动 泵出口侧后的注入管线。
5. 根据权利要求 3所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 还包括连接至电动泵吸入口侧母管的除盐水补给管线。
6. 根据权利要求 3所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 还包括连接至电动泵吸入口侧母管的储水箱再补水管线。
7. 根据权利要求 6所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 所述储水箱再补水管线为两条， 每条储水箱再补水管线都设有再补水泵。
8. 根据权利要求 1至 7中任一项所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 所述每列汽动泵系列都包括汽动泵以及与电动泵系列共用的储水 箱、 蒸汽发生器水位调节阀、 一个安全壳外电动隔离阀和一个安全壳内止回阀。
9. 根据权利要求 1至 7中任一项所述的核电站蒸汽发生器辅助给水系统， 其特征在于： 所述每列汽动泵系列的汽动泵都是依靠蒸汽发生器自身产生的 汽作为驱动力。
PCT/CN2013/087740 2013-07-30 2013-11-24 核电站蒸汽发生器辅助给水系统 Ceased WO2015014046A1 (zh)

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CN104965410A (zh) * 2015-04-17 2015-10-07 华南理工大学 一种蒸汽发生器水位系统的动态滑模变结构控制器与方法
CN109799142B (zh) * 2018-12-20 2021-11-09 中广核核电运营有限公司 核电站水压试验循环加热系统及循环加热方法
CN111486438B (zh) * 2020-03-18 2023-05-12 中国核电工程有限公司 防止辅助给水系统造成蒸汽发生器满溢的控制方法
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