WO2014048293A1 - 一种能动与非能动相结合的安全壳排热装置 - Google Patents

一种能动与非能动相结合的安全壳排热装置 Download PDF

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Publication number
WO2014048293A1
WO2014048293A1 PCT/CN2013/084049 CN2013084049W WO2014048293A1 WO 2014048293 A1 WO2014048293 A1 WO 2014048293A1 CN 2013084049 W CN2013084049 W CN 2013084049W WO 2014048293 A1 WO2014048293 A1 WO 2014048293A1
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Prior art keywords
containment
heat
heat exchanger
passive
active
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English (en)
French (fr)
Inventor
赵侠
于勇
宋代勇
袁霞
赵光辉
李军
李伟
王志刚
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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 GB1504154.4A priority Critical patent/GB2520456B/en
Publication of WO2014048293A1 publication Critical patent/WO2014048293A1/zh
Anticipated expiration legal-status Critical
Priority to ZA2015/02773A priority patent/ZA201502773B/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
    • 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

  • Safety shell heat discharging device combining active and passive
  • the invention belongs to a reactor design technology, and particularly relates to a containment heat removal device combining active and passive. Background technique
  • the containment heat removal system of a traditional nuclear power plant uses a containment spray system to remove heat and radioactive materials entering the containment to control the environmental conditions of the containment.
  • the purpose of the containment spray system is to spray cold water from the top of the containment at the appropriate time, to cool the atmosphere of the containment, and to limit the peak pressure of the containment after L0CA or MSLB.
  • chemicals are added to the spray as necessary to remove suspended iodine and iodine vapor from the containment atmosphere.
  • the active safety shell spray system has the characteristics of strong cooling capacity and good thermal efficiency after accident, and has been widely used. However, this technology relies too much on AC power. When a plant-wide power failure stacking L0CA or MSLB accident occurs, long-term effective heat rejection of the containment cannot be achieved.
  • the representative of the passive containment heat removal device is the AP1 000 passive containment cooling system.
  • the passive containment cooling system passively dissipates heat from the containment to the final heat sink-atmosphere, as shown in Figure 1.
  • air enters from the top inlet 1 of the shield structure, flows through the descending passage and then passes through the ascending flow path, taking away the heat transferred from the wall of the steel containment vessel, and finally draining from the chimney to the environment, above the containment Set the gravity water tank 2.
  • the system After receiving the high pressure signal from the containment, the system automatically starts after the accident. Just turn on any of the three normally closed isolation valves and start the system without any other action. System startup can also be initiated manually by the operator in the main control room or remote shutdown station.
  • the purpose of the invention is to provide a safety shell heat removal device combining the active and passive phases for the defects of the safety shell heat removal system of the conventional nuclear power plant, improve the dependence of the traditional active safety system nuclear power plant on the safety level power supply, and improve the nuclear power plant safety shell row.
  • the inherent safety of the thermal system is to provide a safety shell heat removal device combining the active and passive phases for the defects of the safety shell heat removal system of the conventional nuclear power plant, improve the dependence of the traditional active safety system nuclear power plant on the safety level power supply, and improve the nuclear power plant safety shell row.
  • a movable shell heat removal device comprising a safety shell spray system and a passive containment heat release system, wherein one end of the pipeline of the safety shell spray system is connected a water tank, the other end of which is connected to a spray header at the top of the containment vessel via a spray pump and a heat exchanger;
  • the passive containment heat removal system includes a heat exchanger or a heat exchanger set disposed inside the containment vessel
  • the heat exchanger or the heat exchanger group is connected to the heat exchange water tank disposed outside the safety shell through the rising pipeline and the descending pipeline, and the height of the heat exchange water tank is higher than the height of the heat exchanger or the heat exchanger group.
  • the active and passive movable containment heat removal device wherein a chemical additive tank is connected to an upstream line of the containment spray system spray pump.
  • the active and passive combined containment heat removal device wherein the spray header of the containment spray system is disposed at different elevations on the top of the containment.
  • the active and passive combined containment heat removal device wherein the refueling water tank connected to the pipeline of the containment spray system is disposed at a pit position below the inner core of the containment vessel, The spray pump, heat exchanger and chemical additive tank are disposed outside the containment vessel.
  • the active and passive combined containment heat removal device wherein a steam-water separator is disposed in the heat exchange water tank outside the containment, and the passive containment heat-dissipating system
  • the riser line of the heat exchanger or heat exchanger group is connected to the steam separator.
  • an isolation valve is respectively disposed on the rising line and the descending line of the passive containment heat-dissipating system.
  • the active-shell heat-dissipating device combined with the active and the passive, as described above, wherein the heat exchange water tank is a closed reinforced concrete structure and is provided with a stainless steel village.
  • the beneficial effects of the present invention are as follows:
  • the containment heat removal device provided by the present invention can cope with design basis accidents by means of active and passive combination, and at the same time, can exceed the design default accident, serious accident or active in the whole plant power failure.
  • Continuously discharging the heat inside the containment under the failure or failure condition of the containment heat removal device improves the inherent safety of the system, improves the dependence of the traditional active safety system nuclear power plant on the safety-grade power supply, and improves the safety of the nuclear power plant. , can effectively maintain the integrity of the containment.
  • Figure 1 is a schematic view showing the structure of the AP1 000 passive containment cooling system
  • FIG. 2 is a schematic view showing the structure of the heat dissipation device of the containment combined with the active and the passive. detailed description
  • the containment heat removal device combines the active containment spray system with the passive containment heat release system.
  • One end of the pipeline of the containment spray system is connected to the refueling water tank, and the other end is connected to the spray header at the top of the containment through the spray pump and the heat exchanger; the passive containment heat removal system
  • a heat exchanger or a heat exchanger group disposed inside the containment vessel is connected, and the heat exchanger or heat exchanger group is connected to a heat exchange water tank disposed outside the containment vessel through an ascending pipeline and a descending pipeline.
  • the active containment spray system (cylinder called CSP system) is used to design the heat removal of the containment under standard accident conditions. Under accident conditions (L0CA or steam pipe rupture in the containment), when the pressure inside the containment is When the temperature rises to a certain value, the pressure and temperature of the containment are reduced to an acceptable level to maintain the integrity of the containment.
  • the passive containment heat removal system (PCS system) is used for long-term heat removal of containment under super-design basis accident conditions, including accidents related to plant-wide power outages and sprinkler system failures. The PCS system is also used for accident relief in severe accident conditions (if an overdesign basis accident develops into a serious accident where the core is significantly degraded).
  • the active and passive containment heat removal device includes a containment spray system (CSP system) and a passive containment heat removal system (PCS system), and the safety shell spray system
  • CSP system containment spray system
  • PCS system passive containment heat removal system
  • One end of the pipeline is connected to the refueling tank 2, and the other end is connected to the spray header 9 at the top of the containment through the spray pump 3 and the heat exchanger 4.
  • the spray header 9 is located at the top of the containment
  • a chemical additive tank 5 is connected to the upstream line of the spray pump 3, and the chemical additive tank is used for adding NaOH, which is used for adsorbing volatile iodine in the air; and increasing the pH of the spray water to avoid Structural material corrosion.
  • the refueling water tank 2 can be disposed outside the safety shell or in the safety shell. In a preferred solution, the refueling water tank 2 is disposed at a pit position below the core of the safety shell, and the refueling water tank is located at the lowest point. It is a collection of water from the safety shell spray and pipe breakage.
  • the spray pump 3, the heat exchanger 4, and the chemical additive tank 5 are all disposed outside the containment vessel.
  • the active safety shell heat removal device is a CSP system.
  • the CSP system pumps the spray water from the internal or external displacement water tank to the spray line through a spray pump (electric pump), and sprays cooling water into the safety shell to continuously reduce the safety shell.
  • the internal temperature rises and pressures caused by an accident.
  • the passive containment heat removal system includes a heat exchanger or heat exchanger group 6 disposed inside the containment vessel 1, and the heat exchanger or heat exchanger group 6 passes through an ascending pipeline and a descending pipeline. It is connected to the heat exchange water tank 7 provided outside the containment vessel, and the height of the heat exchange water tank 7 is higher than the height of the heat exchanger or the heat exchanger group 6.
  • a steam-water separator 8 is disposed in the heat exchange water tank 7, and the rising pipeline of the heat exchanger or the heat exchanger group 6 is connected with the steam-water separator 8, respectively, on the rising pipeline and the descending pipeline of the passive containment heat-releasing system Isolation valves 10, 11 are provided.
  • the PCS system adopts the passive design concept, which uses the heat exchanger or heat exchanger set in the containment to condense, convect and radiate heat with the high temperature air inside the containment.
  • the cooling water of the heat exchanger heat sink absorbs the inside of the containment.
  • the heat of the high temperature air is raised, the density is lowered, and the density of the water formed in the cold pipe section is poor.
  • the steam separator entering the heat exchange water tank through the rising pipeline is cooled by the heat exchange water tank, and then flows back to the heat exchanger through the descending pipeline to complete the natural circulation. .
  • the final heat sink of the heat exchange water tank installed outside the containment is the atmosphere, and the heat in the heat exchanger tube is continuously brought outside the containment through the flow of water in the heat exchanger tube to realize the super design basis accident and serious accident work. Under the condition, the passive containment heat is continuously discharged.
  • the PCS system is provided with three columns, each series including a set of heat exchangers, a steam-water separator, a heat exchange water tank, an electric isolation valve, and two parallel pneumatic valves (located in the descending line).
  • the heat exchanger is arranged on the circumference inside the containment;
  • the heat exchange water tank is a device in a reinforced concrete structure stainless steel village, and is arranged in a ring-shaped building with a double-layered containment shell.
  • the CSP system After the design basis accident safety shell pressure reaches the threshold, the CSP system automatically triggers the start, or is manually turned on by the operator to discharge the heat inside the containment.
  • the PCS system adopts passive technology. When the whole plant is powered off, the system is automatically put into operation without operator intervention, using natural circulation. Long-term heat rejection of the containment. The containment heat removal time is maintained for at least 72 hours without operator intervention, and other hydration methods can be considered after 72 hours.
  • the invention adopts the combination of active and passive to derive the heat in the safety shell, can maintain the integrity of the safety shell, and meets the integrity of the safety shell in the Nuclear Safety Plant Design Safety Regulations of China Nuclear Safety Regulations HAF102 (2004). And the requirements for heat removal from the containment.

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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安全壳排热装置
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安全壳 排热装置。 背景技术
传统核电站的安全壳排热系统是利用安全壳喷淋系统来排除进入安全壳的 热量和放射性物质， 以控制安全壳的环境条件。 设置安全壳喷淋系统的目的是 在适当时候从安全壳上部喷洒冷水， 冷却安全壳大气， 限制 L0CA或 MSLB后的 安全壳峰值压力。 此外， 必要时在喷淋液中添加化学药剂， 以除去安全壳大气 中的悬浮碘和碘蒸汽。 能动的安全壳喷淋系统具备冷却能力强， 事故后排热效 果好的特点， 得到广泛应用。 但该技术过分依赖交流电源， 当发生全厂断电叠 加 L0CA或 MSLB事故后， 无法实现安全壳的长期有效排热。
非能动安全壳排热装置的代表为美国 AP1 000的非能动安全壳冷却系统。 非 能动安全壳冷却系统采用非能动方式把安全壳内的热量散发到最终热阱-大 气， 如图 1所示。 正常运行工况下， 空气从屏蔽构筑物顶部入口 1进入， 流过 下降通道后又反向通过上升流道， 带走钢安全壳容器壁传递的热量， 最后从烟 囱排至环境， 在安全壳上方设置重力注水箱 2。 接到安全壳高压力信号后， 系统 的事故后运行自动启动， 只需开启三个常关隔离阀中的任何一个， 不需其他动 作即可启动系统。 系统的启动也可由操纵员在主控室或远程停堆工作站手动启 动。
由于单一的安全壳喷淋系统对安全级电源的依赖度过高， 因此， 利用能动 与非能动相结合的方式控制安全壳的环境条件， 是提高核电厂安全水平的大势 所趋。 非能动安全壳排热装置不依赖传统电源， 依靠自然循环完成事故后安全 功能。 在全厂断电或安全壳喷淋系统故障相关的事故时， 系统依然能够运行并 实现安全壳的完整性， 是能动安全壳排热装置的有效补充。 发明内容
本发明目的在于针对传统核电站的安全壳排热系统的缺陷， 提供一种能动 与非能动相结合的安全壳排热装置， 改进传统能动安全系统核电站对安全级电 源的依赖， 提高核电站安全壳排热系统的固有安全性。 本发明的技术方案如下： 一种能动与非能动相结合的安全壳排热装置， 包 括安全壳喷淋系统和非能动安全壳热量导出系统， 所述的安全壳喷淋系统的管 线一端连接换料水箱， 另一端经喷淋泵和热交换器后连接到安全壳顶部的喷淋 集管； 所述的非能动安全壳热量导出系统包括设置在安全壳内部的换热器或换 热器组， 所述的换热器或换热器组通过上升管线和下降管线与设置在安全壳外 部的换热水箱相连接， 换热水箱的高度高于换热器或换热器组的高度。 进一步， 如上所述的能动与非能动相结合的安全壳排热装置， 其中， 在所 述的安全壳喷淋系统喷淋泵的上游管线上连接有化学添加剂箱。 进一步， 如上所述的能动与非能动相结合的安全壳排热装置， 其中， 所述 的安全壳喷淋系统的喷淋集管设置在安全壳顶部不同标高处。 进一步， 如上所述的能动与非能动相结合的安全壳排热装置， 其中， 所述 的与安全壳喷淋系统的管线相连接的换料水箱设置在安全壳内部堆芯下方地坑 位置， 所述的喷淋泵、 热交换器和化学添加剂箱设置在安全壳外。 进一步， 如上所述的能动与非能动相结合的安全壳排热装置， 其中， 在所 述的安全壳外部的换热水箱内设有汽水分离器， 所述的非能动安全壳热量导出 系统的换热器或换热器组的上升管线与汽水分离器连接。 进一步， 如上所述的能动与非能动相结合的安全壳排热装置， 其中， 在所 述的非能动安全壳热量导出系统的上升管线和下降管线上分别设有隔离阀。 进一步， 如上所述的能动与非能动相结合的安全壳排热装置， 其中， 所述 的换热水箱为封闭的钢筋混凝土结构， 并设有不锈钢村里。 本发明的有益效果如下： 本发明所提供的安全壳排热装置通过能动与非能 动结合的方式既能应对设计基准事故， 同时又能在全厂断电等超设计基准事故、 严重事故或能动安全壳排热装置故障或失效的工况下持续排出安全壳内的热 量， 提高了系统的固有安全性， 改进了传统能动安全系统核电站对安全级电源 的依赖， 提高了核电站的安全性， 同时， 能够有效保持安全壳的完整性。 附图说明
图 1为 AP1 000的非能动安全壳冷却系统结构示意图；
图 2为能动与非能动相结合的安全壳排热装置结构示意图。 具体实施方式
本发明所提供的安全壳排热装置将能动的安全壳喷淋系统与非能动安全壳 热量导出系统相结合。 安全壳喷淋系统的管线一端连接换料水箱， 另一端经喷 淋泵和热交换器后连接到安全壳顶部的喷淋集管； 非能动安全壳热量导出系统 包括设置在安全壳内部的换热器或换热器组， 所述的换热器或换热器组通过上 升管线和下降管线与设置在安全壳外部的换热水箱相连接。
能动的安全壳喷淋系统（筒称 CSP 系统）用于设计基准事故工况下安全壳的 排热， 在事故工况下（L0CA或安全壳内蒸汽管道破裂）， 当安全壳内的压力和温 度升高到一定值时， 将安全壳的压力和温度降低至可接受的水平， 以保持安全 壳的完整性。 非能动安全壳热量导出系统（筒称 PCS 系统）用于在超设计基准 事故工况下安全壳的长期排热， 包括与全厂断电和喷淋系统故障相关的事故。 PCS系统也用于严重事故工况（如果超设计基准事故发展到堆芯明显恶化的严重 事故） 的事故緩解。 在核电站发生超设计基准事故（包括严重事故） 工况时， 将安全壳压力和温度降低至可接受的水平， 以保持安全壳的完整性。 安全壳喷 淋系统和安全壳热量导出系统均用于事故后安全壳排热， 因此将两系统组合起 来使用控制安全壳内的温度压力水平， 以保持安全壳完整性， 能够应对设计基 准事故到超设计基准事故直至严重事故。 此组合方案比单一的能动系统或非能 动系统覆盖的事故工况都要广， 且事故后两系统分别投入运行对安全壳环境条 件的限制效果更好。 下面结合附图和实施例对本发明进行详细的描述。
如图 2所示， 能动与非能动相结合的安全壳排热装置包括安全壳喷淋系统 ( CSP 系统）和非能动安全壳热量导出系统（PCS 系统）， 所述的安全壳喷淋系 统的管线一端连接换料水箱 2 ,另一端经喷淋泵 3和热交换器 4后连接到安全壳 顶部的喷淋集管 9 , 根据安全壳穹顶的结构特点， 喷淋集管 9位于安全壳顶部不 同标高处， 在喷淋泵 3的上游管线上连接有化学添加剂箱 5 , 化学添加剂箱用于 添加 NaOH, 作用是用于吸附空气中的挥发性碘； 以及提高喷淋水的 pH值， 避免 结构材料腐蚀。 换料水箱 2 可以设置在安全壳外或安全壳内， 优选的方案中， 换料水箱 2设置在安全壳内堆芯下方地坑位置， 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。 喷淋泵 3、 热交换器 4和化学添加 剂箱 5均设置在安全壳外。
能动安全壳排热装置为 CSP系统， CSP系统通过喷淋泵（电动泵 )将喷淋水 从内置或外置换料水箱抽至喷淋管线， 向安全壳内喷射冷却水， 以持续降低安 全壳内因发生事故而导致的升温和升压。
所述的非能动安全壳热量导出系统（PCS系统）包括设置在安全壳 1内部的 换热器或换热器组 6 ,所述的换热器或换热器组 6通过上升管线和下降管线与设 置在安全壳外部的换热水箱 7相连接， 换热水箱 7的高度高于换热器或换热器 组 6的高度。换热水箱 7内设有汽水分离器 8 , 所述的换热器或换热器组 6的上 升管线与汽水分离器 8 连接， 在非能动安全壳热量导出系统的上升管线和下降 管线上分别设有隔离阀 10、 11。
PCS系统采用非能动设计理念，利用安全壳内布置的换热器或换热器组与安 全壳内的高温空气进行冷凝、 对流和辐射传热， 热段换热器的冷却水吸收安全 壳内高温空气的热量升温， 密度降低， 与冷管段的水形成密度差， 通过上升管 线进入换热水箱内的汽水分离器， 经换热水箱冷却后， 通过下降管线流回换热 器， 完成自然循环。 在安全壳外设置的换热水箱的最终热阱为大气， 通过换热 器管内水的流动， 连续不断地将安全壳内的热量带到安全壳外， 以实现超设计 基准事故和严重事故工况下持续地非能动安全壳热量排出。
本实施例中 PCS系统设置三列， 每个系列包括一组换热器、 一台汽水分离 器、 一台换热水箱、 一个电动隔离阀、 二个并联的气动阀 （位于下降管线）。 换 热器布置在安全壳内的圓周上； 换热水箱是钢筋混凝土结构不锈钢村里的设备， 布置在双层安全壳外壳的环形建筑物内。
在发生设计基准事故安全壳压力达到阈值后， CSP系统自动触发启动， 或 由操纵员手动开启， 以排出安全壳内热量。 PCS系统采用非能动技术， 发生全厂 断电时， 在没有操纵员干预的情况下， 系统自动投入运行， 利用自然循环实现 安全壳的长期排热。 在无需操纵员操作的情况下， 安全壳非能动排热时间至少 维持 72小时， 72小时后可以考虑其它补水手段。
本发明采用能动与非能动相结合的方式导出安全壳内的热量， 能够保持安 全壳的完整性， 满足我国核安全法规 HAF102 ( 2004 )《核动力厂设计安全规定》 中对保持安全壳完整性和安全壳排热的要求。
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安全壳排热装置， 其特征在于： 包括安全壳 喷淋系统和非能动安全壳热量导出系统， 所述的安全壳喷淋系统的管线一端连 接换料水箱 （2), 另一端经喷淋泵（3)和热交换器（4)后连接到安全壳顶部 的喷淋集管 （9); 所述的非能动安全壳热量导出系统包括设置在安全壳（1) 内 部的换热器或换热器组（6), 所述的换热器或换热器组（6)通过上升管线和下 降管线与设置在安全壳外部的换热水箱 （7)相连接， 换热水箱 （7) 的高度高 于换热器或换热器组（ 6 ) 的高度。
2. 如权利要求 1所述的能动与非能动相结合的安全壳排热装置，其特征在 于：在所述的安全壳喷淋系统喷淋泵（ 3 )的上游管线上连接有化学添加剂箱（ 5 )。
3. 如权利要求 1或 2所述的能动与非能动相结合的安全壳排热装置，其特 征在于： 所述的安全壳喷淋系统的喷淋集 （9) 管设置在安全壳 （1)顶部不同 标高处。
4. 如权利要求 3所述的能动与非能动相结合的安全壳排热装置，其特征在 于： 所述的与安全壳喷淋系统的管线相连接的换料水箱 （2)设置在安全壳内部 堆芯下方地坑位置， 所述的喷淋泵（3)、 热交换器（4)和化学添加剂箱 （5) 设置在安全壳外。
5. 如权利要求 1所述的能动与非能动相结合的安全壳排热装置，其特征在 于： 在所述的安全壳外部的换热水箱 （7) 内设有汽水分离器（8), 所述的非能 动安全壳热量导出系统的换热器或换热器组（6)的上升管线与汽水分离器（8) 连接。
6. 如权利要求 1或 5所述的能动与非能动相结合的安全壳排热装置，其特 征在于： 在所述的非能动安全壳热量导出系统的上升管线和下降管线上分别设 有隔离阀 （10、 11 )。
7. 如权利要求 6 所述的能动与非能动相结合的安全壳排热装置， 其特 征在于： 所述的换热水箱（7 )为封闭的钢筋混凝土结构， 并设有不锈钢村里。
PCT/CN2013/084049 2012-09-27 2013-09-24 一种能动与非能动相结合的安全壳排热装置 Ceased WO2014048293A1 (zh)

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