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WO2016011569A1 - 安全壳冷却系统及安全壳与反应堆压力容器联合冷却系统 - Google Patents

安全壳冷却系统及安全壳与反应堆压力容器联合冷却系统 Download PDF

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Publication number
WO2016011569A1
WO2016011569A1 PCT/CN2014/001003 CN2014001003W WO2016011569A1 WO 2016011569 A1 WO2016011569 A1 WO 2016011569A1 CN 2014001003 W CN2014001003 W CN 2014001003W WO 2016011569 A1 WO2016011569 A1 WO 2016011569A1
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WO
WIPO (PCT)
Prior art keywords
containment
cooling
water
cooler
air
Prior art date
Application number
PCT/CN2014/001003
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English (en)
French (fr)
Inventor
孙中宁
范广铭
丁铭
阎昌琪
王建军
曹夏昕
谷海峰
张楠
Original Assignee
哈尔滨工程大学
孙中宁
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from CN201410353537.6A external-priority patent/CN104103325B/zh
Priority claimed from CN201410353978.6A external-priority patent/CN104091621B/zh
Application filed by 哈尔滨工程大学, 孙中宁 filed Critical 哈尔滨工程大学
Priority to JP2017504086A priority Critical patent/JP6277322B2/ja
Priority to CA2954136A priority patent/CA2954136C/en
Priority to CN201480075917.6A priority patent/CN106104701B/zh
Priority to KR1020167034756A priority patent/KR102085983B1/ko
Publication of WO2016011569A1 publication Critical patent/WO2016011569A1/zh

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • the invention relates to a containment cooling system, and the invention also relates to a combined cooling system of a safety shell and a reactor pressure vessel, belonging to the technical field of nuclear safety and thermal hydraulics.
  • Both the containment and the reactor pressure vessel are important safety barriers against the leakage of radioactive materials in the event of an accident at the nuclear power plant.
  • LOCA LOCA
  • MSLB the containment will rapidly increase the temperature and pressure in the shell due to the rapid filling of a large amount of steam.
  • the containment may be damaged and the radioactive material may be leaked.
  • the core has a significant drop in cooling capacity due to severe water loss.
  • the melt may collapse to the lower head of the pressure vessel. If the lower head is melted through excessive heat load, it will be a serious threat.
  • the integrity of the containment causes leakage of the core melt. Therefore, in order to ensure the safety of nuclear power plants, it is necessary to set up a special system for cooling the containment and reactor pressure vessels.
  • the solution proposed for the concrete containment is mainly to internally set up the heat exchanger.
  • the height difference between the external water tank and the internal heat exchanger is used to derive heat in a natural circulation manner, but at the same time, the water in the water tank is largely evaporated.
  • the external cooling system proposed for the reactor pressure vessel adopts both active and passive water injection methods.
  • the technical solutions disclosed in the patent documents such as CN201681637, CN203366760U, CN202887747U, CN103632736A, CN102163469A, CN103310856A, etc. are disclosed.
  • the above-described external cooling system has a common disadvantage, that is, the utilization rate of cooling water is relatively low. When the water in the pit is filled, if no one is turning off the pump or passive In the control valve in the system, the water injection system will continue to inject water (whether large or small), causing water to overflow the heap and causing waste.
  • the tank of the above-mentioned passive cooling system needs to provide a large amount of water storage without human intervention, which will greatly increase the volume of the water tank. If the water injection flow is small, it may cause the water level in the heap to drop, or even completely inundate the reactor pressure vessel, so that the reactor pressure vessel cannot be sufficiently cooled, thereby threatening the integrity of the reactor pressure vessel. Therefore, if you do not want to cause additional loss of cooling water and provide continuous cooling for the pressure vessel, you need to manually adjust or start the cooling system (whether the active system or the passive system), causing the actual operation of the system. Very difficult.
  • An object of the present invention is to provide a containment cooling system which can achieve long-term cooling in a containment without requiring external power to be supplied and which consumes less cooling water. It is also an object of the present invention to provide a cofferdam and reactor pressure vessel combined cooling system that can provide long-term effective cooling for containment and reactor pressure vessels under accident conditions, keeping the reactor containment and pressure vessels in a safe state at all times. .
  • the containment cooling system of the present invention comprises an internal heat exchanger, an ascending pipeline, a descending pipeline, an isolation valve, a cooling water tank and an air-cooled condensing-cooler, and the internal heat exchanger is located in the upper space of the inner concrete containment close to the side wall
  • the cooling water tank is located outside the outer concrete containment, the relative position of the cooling water tank is higher than the internal heat exchanger, and the cooling water tank and the internal heat exchanger are connected by the rising pipeline and the descending pipeline to form a closed loop, and the air cooling condensing-cooling
  • the device is a shellless heat exchanger, located inside the cooling water tank, and the air-cooled condensing-cooler is arranged obliquely.
  • the heat transfer tube of the air-cooled condensing-cooler is partially placed in the water space, and the other part is placed in the steam space, and the condensing-cooler air side
  • the inlet is opened at the side of the tank side near the bottom surface, and the lower atmosphere of the air-cooling condensing-cooler is connected through the pipeline.
  • the condensing-cooler air side outlet is opened at the position of the side wall of the tank near the upper surface, and the air-cooled condensation is communicated through the pipeline. - an upper space of the cooler and an annular space formed by the inner concrete containment and the outer concrete containment.
  • the containment cooling system of the present invention may further comprise:
  • the side wall of the cooling water tank is connected with a water sealing device, and the upper connecting pipe of the water sealing device is connected with the gas space of the cooling water tank, and the lower connecting pipe of the water sealing device is connected with the water space of the cooling water tank, and the upper and lower connecting pipes are connected Pipeline bridging.
  • the containment and reactor pressure vessel combined cooling system of the present invention comprises a containment cooling system and a reactor pressure vessel cooling system;
  • the containment cooling system includes an internal heat exchanger, an ascending pipeline, a descending pipeline, an isolation valve, and a cooling water tank And an air-cooled condensing-cooler, the internal heat exchanger is located in the upper space of the inner concrete containment close to the side wall, and the cooling water tank is located outside the outer concrete containment, the relative position of the cooling water tank is higher than the internal heat exchanger, the cooling water tank It is connected with the internal heat exchanger through the rising pipeline and the descending pipeline to form a closed loop.
  • the air-cooled condensing-cooler is a shellless heat exchanger, located inside the cooling water tank, the air-cooling condensing-cooler is arranged obliquely, and the air-cooling condensation-cooling One part of the heat transfer tube is placed in the water space, and the other part is placed in the steam space.
  • the air inlet of the condensing-cooler is opened at the side of the tank side near the bottom surface, and the lower atmosphere of the air-cooling condensing-cooler is connected through the pipeline.
  • the reactor pressure vessel cooling system includes a water storage tank, a pressure equalization pipe, a water injection pipe, an isolation pool, a control valve, a communication pipe, and a condensate collection.
  • the water storage tank is located above the isolation pool, and the water storage tank and the isolation pool are connected by a pressure balance pipe and a water injection pipe, and the separation pool and the reactor pit are connected by a communication pipe, the reactor
  • the pressure vessel is located in the reactor pit, and the condensate collection tank is located below the internal heat exchanger, and the condensate collection tank is connected to the water storage tank, the regulating valve and the isolation pool through the pipeline.
  • the containment and reactor pressure vessel combined cooling system of the present invention may further comprise:
  • the upper end of the pressure balance pipe is located in the gas space of the water storage tank, and the lower end is relatively higher than the upper edge of the reactor pressure vessel.
  • the upper end of the water injection pipe is connected with the lowest point of the water storage tank, and the lower end is opposite to the lower edge of the pressure balance pipe.
  • the water outlet at the lower end of the water injection pipe is "S" shaped.
  • the upper part of the water storage tank is connected to the condensate collecting pool through the exhaust pipe, and the lower part of the water storage tank is provided with a sewage discharge valve.
  • the invention has the beneficial effects of providing long-term cooling for the containment vessel and the reactor pressure vessel in the event of a serious accident such as LOCA, MSLB, etc., so that the reactor containment vessel and the pressure vessel are always in a safe state.
  • the system can realize: (1) Under accident conditions, the internal heat exchanger and the water tank can directly generate natural circulation through the density difference between the single-phase water and the steam-water mixture without human intervention; (2) air-cooled condensation - The natural circulation of air between the cooler and the external atmosphere can be realized, and the heat in the water tank can be drained in time, which greatly prolongs the running time of the heat exporting system.
  • Air-cooled condensing-cooler can simultaneously cool the water and steam in the cooling water tank, significantly reduce the consumption of cooling water, increase the utilization rate of cooling water, and greatly reduce the water capacity of the cooling water tank.
  • Air-cooled condensing-cooler can cool the water in the cooling water tank to lower the water temperature, thereby increasing the density difference between the descending pipeline and the rising pipeline, increasing the driving force of the natural circulation, and cooling the internal heat exchanger. The water flow increases and the heat exchange power of the heat exchanger increases, which can more effectively derive the heat inside the containment.
  • the water seal device can be installed to prevent the cooling water tank from being polluted by the external environment. It can also be automatically opened when the pressure in the water tank is high to avoid overpressure damage of the cooling water tank.
  • the external cooling system can realize complete passive operation to flood the pressure vessel, and the water supply can be automatically adjusted by the pressure balance tube without human intervention and adjustment.
  • "S" shape design can effectively prevent two phases of soda Reverse flow occurs to avoid flow oscillations and the water injection flow is stable.
  • the passive non-external cooling system has high utilization rate of cooling water, and there is no waste and waste. Compared with the existing passive technology, the cooling water consumption is significantly reduced under the same cooling time, and the storage is greatly reduced. Water tank capacity.
  • the design of the isolation pool effectively prevents the steam generated by boiling in the pit from flowing back into the water storage tank, ensuring reliable and smooth operation of the system.
  • Figure 1 is a schematic illustration of a containment cooling system of the present invention.
  • FIG. 2 is a schematic view of a combined cooling system of a containment vessel and a reactor pressure vessel of the present invention.
  • the containment cooling system of the present invention is mainly composed of an internal heat exchanger 1, an ascending pipeline 2, a descending pipeline 3, an isolation valve 4, an isolation valve 5, a cooling water tank 6, and an air-cooling condensing-cooler 7.
  • the internal heat exchanger is located in the upper space of the inner concrete containment 12 adjacent to the side wall;
  • the cooling water tank is located outside the outer concrete containment vessel 13, the relative position is higher than the internal heat exchanger, and the internal heat exchanger is respectively raised
  • the pipeline and the descending pipeline are connected to form a closed loop;
  • the air-cooled condensing-cooler is a shellless heat exchanger, which is located inside the cooling water tank, is arranged obliquely, and a part of the heat pipe is placed in the water space, and the other part is placed in the steam space.
  • the water and steam in the cooling water tank significantly reduce the consumption of cooling water, greatly extend the continuous running time of the heat-extracting system, and achieve long-term cooling of the containment;
  • the condensing-cooler air side inlet 9 opens to the bottom side of the tank Position, through the pipeline to communicate the external atmosphere and the lower head of the air-cooled condensing-cooler;
  • the condensing-cooler air side outlet 10 is opened at the position of the side wall of the tank near the upper surface, and the upper head of the air-cooled condensing-cooler is connected through the pipeline And an annular space formed by the inner concrete containment and the outer concrete containment.
  • the internal heat exchanger uses highly efficient heat transfer tubes, such as outer fin tubes and integral pin fin tubes, to improve heat transfer efficiency; external air condensing-coolers use highly efficient heat transfer tubes, such as inner fin tubes and inner ribs. Pipes, etc., to improve heat transfer efficiency and reduce heat exchanger volume.
  • Internal and external isolation valve sets 4, 5 are provided on the ascending and descending lines to prevent leakage of radioactive materials from the passive heat transfer system due to pipeline damage.
  • a water seal device 8 is connected to the side wall of the cooling water tank to isolate the cooling water tank from the external environment during non-operating conditions, thereby preventing the water in the water tank from being contaminated, thereby causing blockage of the pipeline; in the case of an accident, the cooling water tank is working.
  • the mass is heated and the pressure rises, thereby breaking the water seal and allowing the cooling water tank to communicate with the outside atmosphere via the water sealing device.
  • the upper connecting pipe of the water sealing device is in communication with the gas space of the cooling water tank, the lower connecting pipe is connected with the water space of the cooling water tank, and the upper and lower connecting pipes are connected by pipes.
  • An air outlet 11 is provided above the middle of the outer concrete containment dome to guide the air flow between the double containment chambers, allowing air to flow from the condensing-cooler inlet through the air-cooled condensing-cooler and the air-cooling condensing-cooler outlet After that, it flows out from the air outlet to form a natural circulation of air with the external atmospheric environment, providing sufficient air flow for the air-cooled condensate-cooler.
  • the containment cooling system of the present invention is a passive containment heat removal system, and its working principle when operating alone is as follows: when the main pipe of the reactor breaks or the main steam pipe is broken, a large amount of steam is released into the containment, and Mix with the air inside the containment to raise the temperature and pressure inside the containment. When the pressure in the containment reaches a certain threshold, the pressure sensor in the containment sends a high voltage signal to the main control room of the power station to activate the containment heat removal system.
  • the water in the cooling water tank flows into the internal heat exchanger 1 from the descending pipeline 3, and is gradually heated and heated, and the water in the descending pipeline and the rising pipeline is naturally circulated depending on the density difference, and The heat inside the containment is introduced into the cooling water tank, so that the temperature in the cooling water tank 6 rises, and the air-cooled condensing-cooler starts to operate, and the air enters the air-cooling condensing-cooler 7 from the condensing-cooler air side inlet 9 to be fully heat-exchanged.
  • the condensate-cooler air side outlet 10 flows out through the annular space of the inner concrete containment 12 and the outer concrete containment 13 and is finally discharged into the atmosphere by the air outlet 11 to achieve natural circulation of air and take away heat in the cooling water tank. .
  • the temperature inside the containment rises rapidly, and the heat introduced from the internal heat exchanger into the cooling water tank may be higher than the heat transfer power of the air-cooled condensate-cooler 7.
  • the steam is generated in the cooling water tank 6, and the pressure in the water tank rises.
  • the water sealing device is automatically opened, the cooling water tank 6 is directly discharged to the air, and the water seal is re-established after the pressure is released. , isolating the cooling water tank 6 and the external environment.
  • the amount of steam discharged into the containment gradually stabilizes or decreases with time.
  • the heat of the internal heat exchanger introduced into the cooling water tank will be less than or equal to the heat exchange capacity of the air-cooled condensing-cooler 7, and the air-cooling condensing-cooler 7 effectively cools and condenses the remaining water and the upper steam in the cooling water tank 6. Avoid the loss of cooling water, and thus achieve long-term cooling inside the containment, greatly improving the safety of the containment.
  • the combined containment and reactor pressure vessel cooling system of the present invention mainly comprises a containment cooling system and a reactor pressure vessel cooling system.
  • the structure of the containment cooling system is the same as that of the first embodiment.
  • the reactor pressure vessel cooling system mainly comprises a water storage tank 14, a pressure equalization pipe 15, a water injection pipe 16, an isolation water tank 17, control valves 18 and 24, a communication pipe 19, a reactor pit 20, a reactor pressure vessel 21, and a condensate.
  • the pool 22, the water storage tank 23, the exhaust pipe 25, and the drain valve 25 are collected.
  • the water storage tank is located above the isolation pool, and the two are connected by a pressure balance tube and a water injection pipe, and the isolation pool and the reactor pit are connected by a communication pipe, and the reactor pressure vessel is located in the reactor pit, the condensate collection pool Located under the internal heat exchanger, the water storage tank, regulating valve and isolation pool are connected in turn through the pipeline.
  • the upper end of the pressure equalization tube is located in the gas space of the water storage tank, and the lower end is relatively higher than the upper edge of the reactor pressure vessel.
  • the reactor pressure vessel is always submerged below the water surface.
  • the upper end of the water injection pipe is connected to the lowest point of the water storage tank, and the lower end is opposite to the lower edge of the pressure balance pipe.
  • the water outlet at the lower end of the water injection pipe adopts an "S" shape to prevent air from entering the water storage tank from the water injection pipe when the water outlet is exposed to the water surface, thereby causing a gas-liquid two-phase reverse flow state in the pipe, increasing water injection resistance, and causing flow vibration.
  • the isolation pool is a small pool, and the water in the pool is always kept cold to prevent steam generated from boiling in the reactor pit from entering the storage tank during accident conditions.
  • the control pipe is provided with a control valve.
  • the control valve When the system is in the standby state, the control valve is closed, and the isolation pool is in a waterless state.
  • the control valve When an accident occurs, the control valve is opened, water is injected into the isolation pool from the water storage tank, and enters the reactor through the communication pipe. Pile pits, flooding the reactor pressure vessel.
  • the upper part of the water storage tank is connected with the condensate collecting pool through the exhaust pipe, so that the water in the condensate collecting pool can smoothly flow into the water storage tank to avoid the phenomenon of two-phase reverse flow in the pipeline;
  • the lower part of the water storage tank is provided with a sewage valve.
  • the water can be periodically injected into the condensate collecting pool to flush the condensate collecting pool, the water storage tank and related pipelines, and the water is discharged by the drain valve to ensure smooth circuit and prevent blockage.
  • the containment cooling system of the present embodiment is a passive containment heat removal system
  • the reactor pressure vessel cooling system is a passive external stack cooling system.
  • the passive containment heat removal system and the passive off-site cooling system can be operated in combination or independently.
  • the control valve is closed, and the condensate generated by the internal heat exchanger is collected by the condensate collection tank and injected into the storage tank for storage.
  • the control valve is opened, and the condensate flows into the isolation pool from the storage tank to participate in the cooling of the reactor pressure vessel, thereby saving the amount of water in the water storage tank. Effectively reduce the volume of the water storage tank.
  • the working principle of the passive containment heat removal system and the passive external cooling system is as follows: When the reactor main pipe breaks or the main steam pipe breaks, a large amount of steam is released into the containment and the containment The internal air mixes to increase the temperature and pressure inside the containment; at the same time, the core melt may collapse to the lower end of the pressure vessel due to the large amount of water loss in the core, and the lower seal The head is melted through excessive heat loading and may threaten the integrity of the containment. In order to prevent the core melt from passing through the lower head of the pressure vessel, it is necessary to fill the reactor pit 20 with water. At this time, it is necessary to simultaneously activate the passive containment heat removal system and the passive off-site cooling system.
  • the water in the cooling water tank flows into the internal heat exchanger 1 from the descending pipeline 3, and is gradually heated and heated, and the water in the descending pipeline and the rising pipeline is naturally circulated by the density difference, and the inside of the safety shell is
  • the heat is introduced into the cooling water tank, so that the temperature in the cooling water tank 6 rises, and the air-cooled condensing-cooler starts to operate, and the air enters the air-cooling condensing-cooler 7 from the condensing-cooler air side inlet 9 to be fully condensed and cooled by heat exchange.
  • the air side outlet 10 flows out through the annular space of the inner concrete containment 12 and the outer concrete containment 13 and is finally discharged into the atmosphere by the air outlet 11, thereby achieving natural circulation of the air and taking away the heat in the cooling water tank.
  • the condensed water generated on the surface of the internal heat exchanger 1 is collected by the condensate collecting tank 22 and flows through the water storage tank 23, the control valve 24, and into the isolation pool 17, and the water flowing in from the water storage tank 14 through the water injection pipe 16 is in the isolation pool. 17 is mixed and used together as cooling water for the reactor pressure vessel 21.
  • the water level in the isolation pool 17 is higher than the horizontal position of the communication tube 19 at the bottom, the water flows into the reactor pit 20 via the communication tube 19 via the isolation pool 17, and rapidly floods the reactor pressure vessel 21. Since the isolation pool 17 and the reactor pit 20 are of a communicating structure, the water level between the two is balanced. When the water level in the isolation pool 17 has not passed the lower end of the pressure balance pipe 15, the cooling water injected into the isolation pool 17 by the water storage tank 14 is rapidly reduced until it stops.
  • the surface of the reactor pressure vessel 21 in the high temperature state continues to heat the cooling water in the reactor pit 20, so that the water in the reactor pit 20 is heated until boiling evaporation occurs.
  • steam is still injected into the containment at the break of the main pipe.
  • the condensed water is collected by the condensate collecting tank 22 and continuously injected into the reactor pit 20 to cool the surface of the reactor pressure vessel 21, if the amount of condensed water on the surface of the internal heat exchanger 1 is larger than the water storage tank 23, the amount of water injected into the isolation pool 17, the condensed water is stored in the water storage tank 23.
  • the temperature inside the containment rises rapidly, and the heat introduced from the internal heat exchanger into the cooling water tank may be higher than the heat transfer power of the air-cooled condensate-cooler 7.
  • the steam is generated in the cooling water tank 6, and the pressure in the water tank rises.
  • the water sealing device is automatically opened, the cooling water tank 6 is directly discharged to the air, and the water seal is re-established after the pressure is released. , isolating the cooling water tank 6 and the external environment.
  • the condensed water is continuously injected into the isolation pool 17, ensuring the lower end of the pressure balance pipe 15. It is always submerged, and therefore, the water consumed in the water storage tank 14 is hardly consumed except for being initially injected into the isolation pool 17.
  • the amount of steam discharged into the containment gradually stabilizes or decreases with time.
  • the heat of the internal heat exchanger introduced into the cooling water tank will be less than or equal to the heat exchange capacity of the air-cooled condensing-cooler 7, and the air-cooling condensing-cooler 7 effectively cools and condenses the remaining water and the upper steam in the cooling water tank 6. Avoid the loss of cooling water, and thus achieve long-term cooling inside the containment, greatly improving the safety of the containment.

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Abstract

一种安全壳冷却系统及安全壳与反应堆压力容器联合冷却系统,其中,所述安全壳冷却系统主要由内部换热器(1)、上升管路(2)、下降管路(3)、隔离阀(4,5)、冷却水箱(6)和空冷冷凝-冷却器(7)连接构成。所述安全壳与反应堆压力容器联合冷却系统包括所述安全壳冷却系统和反应堆压力容器冷却系统。所述冷却系统不需要提供外部动力,可以在事故工况下同时为安全壳和反应堆压力容器提供长期的有效冷却,从而保证发生事故时,在无人为干预和其它外部冷却措施投入的条件下,反应堆安全壳和压力容器始终处于安全状态。

Description

安全壳冷却系统及安全壳与反应堆压力容器联合冷却系统 技术领域
本发明涉及一种的是安全壳冷却系统,本发明也涉及一种安全壳与反应堆压力容器联合冷却系统,属于核安全和热工水力技术领域。
背景技术
安全壳和反应堆压力容器都是核电站发生事故时,防止放射性物质外泄的重要安全屏障。在发生LOCA、MSLB等严重事故时,安全壳会因迅速充入大量蒸汽使得壳内温度和压力急剧上升,一旦温度、压力超过设计许用范围则可能造成安全壳损坏,使得放射性物质外泄;与此同时,堆芯因为严重失水使冷却能力大幅下降,一旦堆芯熔毁,熔融物可能坍塌至压力容器下封头,若下封头因受到过量热载荷而被熔穿,将严重威胁安全壳的完整性,造成堆芯熔融物外泄。因此,为保证核电站的安全,有必要设置专门系统用于冷却安全壳和反应堆压力容器。
目前,针对双层混凝土安全壳和反应堆压力容器都提出了一些冷却系统的设计方案。
针对混凝土安全壳提出的方案主要是内部设置换热器,依靠外部水箱与内部换热器间的高度差,以自然循环的方式导出热量,但同时也将使水箱内的水大量蒸发。(C S Byun,D W Jerng,N E Todreas,et al.Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment.Nuclear Engineering and Design,2000,199:227-242;S J Cho,B S Kim,M G Kang,et al.The development of passive design features for the Korean Next Generation Reactor.Nuclear Engineering and Design,2000,201:259-271;S W Lee,W P Baek,S H Chang.Assessment of passive containment cooling concepts for advanced pressurized water reactors.Ann.Nucl.Energy,1997,24(6):467-475)。可见,上述安全壳热量导出系统的设计中都存在一个主要的问题,就是只能在一段时间内保证安全壳的温度和压力不超过设计基准,提供冷却的时间最长为72小时,超过这个时限则系统会因为水箱内的水被耗尽而失效。72小时后需依靠外部动力重新给水箱注水后才能使系统重新发挥作用,要想在无人为干预的前提下延长冷却时间,则只能靠进一步增加水箱的容积来实现,但水箱容积的增大又会使发生地震时带来的影响大幅增加。
针对反应堆压力容器提出的堆外冷却系统几乎同时采用了能动和非能动两种注水方式。如公开号为:CN201681637、CN203366760U、CN202887747U;CN103632736A、CN102163469A、CN103310856A等专利文件中公开的技术方案。然而,上述设计的堆外冷却系统都存在一个共同的缺点,就是冷却水的利用率比较低。当堆坑内的水注满后,如无人为关闭水泵或非能动 系统中的控制阀门,则注水系统仍然会持续注水(无论大流量还是小流量),使水溢出堆坑造成浪费。所以,为了保证充足的冷却时间,在无人为干预的情况下,上述非能动冷却系统的水箱需要提供很大的储水量,这就会使水箱的体积大幅增加。而如果注水流量偏小,则有可能导致堆坑内的水位下降,甚至不能完全淹没反应堆压力容器,使反应堆压力容器不能得到充分的冷却,进而威胁反应堆压力容器的完整性。因此,如果既不想造成冷却水的额外流失,又能为压力容器提供持续冷却,则需要人为的对冷却系统(无论是能动系统还是非能动系统)持续调节或启停,给系统的实际运行造成很大困难。
此外,上述方案都是仅针对双层混凝土安全壳或反应堆压力容器提出的,二者之间是相互独立的。然而,在严重事故时往往需要同时提供安全壳和反应堆压力容器的冷却,如果两套系统独立运行则会使内部换热器产生的凝结水白白损失。
发明内容
本发明的目的在于提供一种不需要提供外部动力,冷却水的消耗少,可实现对安全壳内的长期冷却的安全壳冷却系统。本发明的目的还在于提供一种可以在事故工况下同时为安全壳和反应堆压力容器提供长期的有效冷却,使反应堆安全壳和压力容器始终处于安全状态的安全壳与反应堆压力容器联合冷却系统。
本发明的安全壳冷却系统包括内部换热器、上升管路、下降管路、隔离阀、冷却水箱和空冷冷凝-冷却器,内部换热器位于内层混凝土安全壳内靠近侧壁的上部空间,冷却水箱位于外层混凝土安全壳的外侧,冷却水箱的相对位置高于内部换热器,冷却水箱与内部换热器之间通过上升管路和下降管路相连构成闭合回路,空冷冷凝-冷却器为无壳换热器、位于冷却水箱的内部,空冷冷凝-冷却器倾斜布置,空冷冷凝-冷却器的传热管一部分置于水空间、另一部分置于汽空间,冷凝-冷却器空气侧入口开于水箱侧壁靠近底面位置、通过管道联通外部大气环境与空冷冷凝-冷却器的下封头,冷凝-冷却器空气侧出口开于水箱侧壁靠近上表面的位置、通过管道联通空冷冷凝-冷却器的上封头和内层混凝土安全壳与外层混凝土安全壳构成的环形空间。
本发明的安全壳冷却系统还可以包括:
1、冷却水箱的侧壁连接有水封装置,水封装置的上部连接管与冷却水箱的气空间联通,水封装置的下部连接管与冷却水箱的水空间联通,上、下部连接管间有管道跨接。
2、在上升管路和下降管路上均设有内部和外部隔离阀组。
本发明的安全壳与反应堆压力容器联合冷却系统包括安全壳冷却系统和反应堆压力容器冷却系统;所述安全壳冷却系统包括内部换热器、上升管路、下降管路、隔离阀、冷却水箱 和空冷冷凝-冷却器,内部换热器位于内层混凝土安全壳内靠近侧壁的上部空间,冷却水箱位于外层混凝土安全壳的外侧,冷却水箱的相对位置高于内部换热器,冷却水箱与内部换热器之间通过上升管路和下降管路相连构成闭合回路,空冷冷凝-冷却器为无壳换热器、位于冷却水箱的内部,空冷冷凝-冷却器倾斜布置,空冷冷凝-冷却器的传热管一部分置于水空间、另一部分置于汽空间,冷凝-冷却器空气侧入口开于水箱侧壁靠近底面位置、通过管道联通外部大气环境与空冷冷凝-冷却器的下封头,冷凝-冷却器空气侧出口开于水箱侧壁靠近上表面的位置、通过管道联通空冷冷凝-冷却器的上封头和内层混凝土安全壳与外层混凝土安全壳构成的环形空间;所述反应堆压力容器冷却系统包括储水罐、压力平衡管、注水管、隔离水池、控制阀、连通管、凝液收集水池、蓄水箱和排气管,储水罐位于隔离水池的上方,储水罐与隔离水池之间通过压力平衡管和注水管连接,隔离水池与反应堆堆坑之间通过连通管连接,反应堆压力容器位于反应堆堆坑中,凝液收集水池位于内部换热器下方,凝液收集水池经管线依次连接蓄水箱、调节阀和隔离水池。
本发明的安全壳与反应堆压力容器联合冷却系统还可以包括:
1、压力平衡管上端位于储水罐的气空间内,下端相对位置高于反应堆压力容器的上边缘。
2、注水管上端与储水罐的最低点连接,下端相对位置低于压力平衡管的下边缘。
3、注水管下端出水口呈“S”形。
4、注水管上设有控制阀。
5、蓄水箱上部通过排气管与凝液收集水池联通,蓄水箱下部设有排污阀。
本发明的有益效果是:在发生LOCA、MSLB等严重事故时,能够同时为安全壳和反应堆压力容器提供长期冷却,使反应堆安全壳和压力容器始终处于安全状态。该系统可实现:(1)在事故工况下,内部换热器与水箱之间可以直接通过单相水和汽水混合物之间的密度差产生自然循环,不需要人为干预;(2)空冷冷凝-冷却器与外部大气之间可实现空气自然循环,及时排走水箱内的热量,大大延长热量导出系统的运行时间,当水箱内热量的增加值小于等于空冷冷凝-冷却器的换热功率时,则系统可实现对安全壳内的长期冷却。(3)空冷冷凝-冷却器可以同时对冷却水箱内的水和蒸汽进行冷却,显著减少冷却水的消耗,提高冷却水的利用率,大幅减小冷却水箱的水装量。(4)空冷冷凝-冷却器可以对冷却水箱内的水进行冷却,使水温下降,从而使下降管路和上升管路内的密度差增加,自然循环驱动力加大,内部换热器的冷却水流量增加,换热器换热功率提高,可以更有效的导出安全壳内的热量。(5)水封装置的设置可以避免冷却水箱受到外部环境的污染,也可以在水箱内压力较高时自动打开,避免冷却水箱超压破坏。(6)堆外冷却系统可实现完全非能动运行来淹没压力容器,补水量可利用压力平衡管实现自动调节,无需人为干预和调节。(7)“S”形设计可有效防止汽水两相 逆向流动出现,避免流量振荡,注水流量稳定。(8)非能动堆外冷却系统对冷却水的利用率高,不存在流失浪费,与现有非能动技术相比,在冷却时间相同的情况下显著减少冷却水消耗量,大幅度减小储水罐容积。(9)隔离水池的设计有效防止了堆坑中沸腾产生的蒸汽倒流进入储水罐,保证系统能够可靠平稳运行。
附图说明
图1是本发明的安全壳冷却系统示意图。
图2是本发明的安全壳与反应堆压力容器联合冷却系统示意图。
具体实施方式
下面结合附图举例对本发明做更详细的描述。
具体实施方式一:
结合图1,本发明的安全壳冷却系统主要由内部换热器1、上升管路2、下降管路3、隔离阀4、隔离阀5、冷却水箱6、空冷冷凝-冷却器7连接组成。内部换热器位于内层混凝土安全壳12内靠近侧壁的上部空间;冷却水箱位于外层混凝土安全壳13的外侧,相对位置高于内部换热器,与内部换热器之间分别通过上升管路和下降管路相连,构成闭合回路;空冷冷凝-冷却器为无壳换热器,位于冷却水箱的内部,倾斜布置,传其热管一部分置于水空间,另一部分置于汽空间,用于冷却水箱内的水和蒸汽,显著减少冷却水的消耗量,大幅延长热量导出系统的连续运行时间,实现对安全壳的长期冷却;冷凝-冷却器空气侧入口9开于水箱侧壁靠近底面位置,通过管道联通外部大气环境与空冷冷凝-冷却器的下封头;冷凝-冷却器空气侧出口10开于水箱侧壁靠近上表面的位置,通过管道联通空冷冷凝-冷却器的上封头和内层混凝土安全壳与外层混凝土安全壳构成的环形空间。
内部换热器使用高效强化传热管,如外翅片管、整体针翅管等,来提高传热效率;外部空气冷凝-冷却器使用高效强化传热管,如内翅片管、内肋管等,来提高传热效率,减小换热器体积。
在上升管路和下降管路上,均设有内部和外部隔离阀组4、5,防止非能动热量导出系统因管路破损带来的放射性物质外泄。
冷却水箱的侧壁连接有水封装置8,在非运行工况时将冷却水箱与外部环境隔离,避免水箱中的水受到污染,进而导致管道发生阻塞;在事故工况时,冷却水箱由于工质被加热而压力上升,从而打破水封,使冷却水箱经由水封装置与外部大气联通。水封装置的上部连接管与冷却水箱的气空间联通,下部连接管与冷却水箱的水空间联通,上、下连接管间有管道跨接。
在外层混凝土安全壳穹顶中部的上方设有空气出口11,起到引导双层安全壳间空气流动的作用,使空气由冷凝-冷却器入口流经空冷冷凝-冷却器和空冷冷凝-冷却器出口后,由空气出口流出,从而与外部大气环境构成空气自然循环,为空冷冷凝-冷却器提供足够的空气流量。
本发明的安全壳冷却系统为非能动安全壳热量导出系统,它单独运行时的工作原理如下:当反应堆主管道发生断裂或主蒸汽管道发生破裂时,会有大量蒸汽被释放进入安全壳,并与安全壳内的空气混合,使安全壳内的温度和压力升高。当安全壳内的压力达到某一阈值时,安全壳内的压力传感器会将高压信号发送至电站主控制室,启动安全壳热量导出系统。当安全壳热量导出系统启动后,冷却水箱内的水由下降管路3流入内部换热器1,并逐步被加热升温,下降管路和上升管路内的水依靠密度差产生自然循环,将安全壳内的热量导入冷却水箱,使冷却水箱6内的温度上升,空冷冷凝-冷却器随之启动运行,空气由冷凝-冷却器空气侧入口9进入空冷冷凝-冷却器7,充分换热后由冷凝-冷却器空气侧出口10流出,经内层混凝土安全壳12和外层混凝土安全壳13的环形空间,最终由空气出口11排入大气,实现空气自然循环,带走冷却水箱内的热量。
在事故发生的初期,由于排入安全壳内的蒸汽量较大,使得安全壳内温度上升很快,由内部换热器导入冷却水箱的热量可能高于空冷冷凝-冷却器7的换热功率,使得冷却水箱6内产生蒸汽,水箱内压力升高,当水箱压力高于水封装置8的开启压力时,水封装置自动打开,冷却水箱6直接对空排放,泄压后水封重新建立,隔离冷却水箱6和外部环境。
在事故中后期,排入安全壳内的蒸汽量逐渐趋于稳定或随着时间的增加而减少。此时,内部换热器导入冷却水箱的热量将小于等于空冷冷凝-冷却器7的换热能力,空冷冷凝-冷却器7对冷却水箱6内的剩余水和上部蒸汽进行有效的冷却和冷凝,避免冷却水的损耗,进而实现对安全壳内的长期冷却,大大提高了安全壳的安全性。
具体实施方式二:
结合图2,本发明的安全壳与反应堆压力容器联合冷却系统主要包括安全壳冷却系统和反应堆压力容器冷却系统两部分。安全壳冷却系统的结构与具体实施方式一相同。
所述的反应堆压力容器冷却系统主要包括储水罐14、压力平衡管15、注水管16、隔离水池17、控制阀18和24、连通管19、反应堆堆坑20、反应堆压力容器21、凝液收集水池22、蓄水箱23、排气管25和排污阀25。其中,储水罐位于隔离水池的上方,两者之间通过压力平衡管和注水管连接,隔离水池与反应堆堆坑之间通过连通管连接,反应堆压力容器位于反应堆堆坑中,凝液收集水池位于内部换热器下方,经管线依次连接蓄水箱、调节阀和隔离水池。
压力平衡管上端位于储水罐的气空间内,下端相对位置高于反应堆压力容器的上边缘, 当系统处于备用状态时,管内无水,当发生事故时,保证反应堆压力容器始终淹没在水面以下。
注水管上端与储水罐的最低点连接,下端相对位置低于压力平衡管的下边缘。
注水管下端出水口采用“S”形设计,防止出水口露出水面时空气从注水管进入储水罐,从而造成管内出现气-液两相逆向流动状态,增加注水阻力,并引起流动振动。
隔离水池为一小型水池,池中的水始终保持冷态,防止事故工况时反应堆堆坑中沸腾产生的蒸汽进入储水罐。
注水管上设有控制阀,当系统处于备用状态时,控制阀关闭,隔离水池处于无水状态,当发生事故时,控制阀开启,水由储水罐注入隔离水池,并经由连通管进入反应堆堆坑,淹没反应堆压力容器。
蓄水箱上部通过排气管与凝液收集水池联通,使凝液收集水池中的水可以顺利流入蓄水箱中,避免管路中出现两相逆流现象;蓄水箱下部设有排污阀,可定期向凝液收集水池中注水来冲洗凝液收集水池、蓄水箱及相关管路,水由排污阀排出,保证回路畅通,防止堵塞。
本实施方式安全壳冷却系统为非能动安全壳热量导出系统,反应堆压力容器冷却系统属于非能动堆外冷却系统。非能动安全壳热量导出系统和非能动堆外冷却系统可联合运行也可独立运行。当非能动安全壳热量导出系统独立运行时,控制阀处于关闭状态,内部换热器产生的凝液由凝液收集水池收集并注入蓄水箱中储存。当非能动安全壳热量导出系统和非能动堆外冷却系统联合运行时,控制阀打开,则凝液由蓄水箱流入隔离水池参与对反应堆压力容器的冷却,可节约储水罐中的水量,有效减小储水罐的容积。
非能动安全壳热量导出系统和非能动堆外冷却系统联合运行时的工作原理如下:当反应堆主管道发生断裂或主蒸汽管道发生破裂时,会有大量蒸汽被释放进入安全壳,并与安全壳内的空气混合,使安全壳内的温度和压力升高;与此同时,由于堆芯大量失水可能造成堆芯熔毁,堆芯熔融物有可能坍塌至压力容器下封头,若下封头因受到过量热载荷而被熔穿,将可能威胁安全壳的完整性。为了防止堆芯熔融物熔穿压力容器下封头,需要向反应堆堆坑20中注水。此时,需同时启动非能动安全壳热量导出系统和非能动堆外冷却系统。
当系统启动后,冷却水箱内的水由下降管路3流入内部换热器1,并逐步被加热升温,下降管路和上升管路内的水依靠密度差产生自然循环,将安全壳内的热量导入冷却水箱,使冷却水箱6内的温度上升,空冷冷凝-冷却器随之启动运行,空气由冷凝-冷却器空气侧入口9进入空冷冷凝-冷却器7,充分换热后由冷凝-冷却器空气侧出口10流出,经内层混凝土安全壳12和外层混凝土安全壳13的环形空间,最终由空气出口11排入大气,实现空气自然循环,带走冷却水箱内的热量。
内部换热器1表面产生的凝结水由凝液收集水池22收集并流经蓄水箱23、控制阀24进入隔离水池17中,与由储水罐14经注水管16流入的水在隔离水池17中混合,共同作为反应堆压力容器21的冷却水。当隔离水池17中的水位高于底部的连通管19所在水平位置后,水经由隔离水池17经连通管19流入反应堆堆坑20中,快速淹没反应堆压力容器21。由于隔离水池17与反应堆堆坑20为连通器结构,因此,两者之间的水位是平衡的。当隔离水池17中的水位没过压力平衡管15的下端后,则由储水罐14注入隔离水池17中的冷却水快速减少直至停止。
随着反应堆堆芯衰变热的大量释放,处于高温状态的反应堆压力容器21表面持续对反应堆堆坑20中的冷却水进行加热,使得反应堆堆坑20中的水升温,直至发生沸腾蒸发。而此时,主管道破口处也仍然向安全壳内注入蒸汽。蒸汽在内部换热器1表面凝结后,凝结水由凝液收集水池22收集并持续注入反应堆堆坑20中对反应堆压力容器21表面进行冷却,若内部换热器1表面凝结水量大于蓄水箱23向隔离水池17的注水量,则凝水储存于蓄水箱23中。
在事故发生的初期,由于排入安全壳内的蒸汽量较大,使得安全壳内温度上升很快,由内部换热器导入冷却水箱的热量可能高于空冷冷凝-冷却器7的换热功率,使得冷却水箱6内产生蒸汽,水箱内压力升高,当水箱压力高于水封装置8的开启压力时,水封装置自动打开,冷却水箱6直接对空排放,泄压后水封重新建立,隔离冷却水箱6和外部环境。此外,由于内部换热器1表面的凝结水量很大(凝结水主要来自地坑蒸发和破口喷出蒸汽的大量冷凝),且凝结水会持续注入隔离水池17,保证压力平衡管15的下端始终淹没,因此,储水罐14中消耗的水除初始注入隔离水池17中以外几乎不需消耗。
在事故中后期,排入安全壳内的蒸汽量逐渐趋于稳定或随着时间的增加而减少。此时,内部换热器导入冷却水箱的热量将小于等于空冷冷凝-冷却器7的换热能力,空冷冷凝-冷却器7对冷却水箱6内的剩余水和上部蒸汽进行有效的冷却和冷凝,避免冷却水的损耗,进而实现对安全壳内的长期冷却,大大提高了安全壳的安全性。此外,由于内部换热器1表面的凝结水量减小,若反应堆堆坑20中水的蒸发量大于凝液收集量时,水位会因蒸发而下降至低于压力平衡管15的下端,储水罐14恢复注水,直至再次淹没压力平衡管15的下端。如此反复,始终保证反应堆压力容器21处于淹没状态,无需人为干预。
以上所述的仅是本发明的优选实施方式,应当指出,对于本技术领域的普通技术人员来说,在不脱离本发明原理的前提下,还可以作出若干改进和润饰,这些改进和润饰也应视为本发明的保护范围。

Claims (9)

  1. 一种安全壳冷却系统,包括内部换热器、上升管路、下降管路、隔离阀、冷却水箱和空冷冷凝-冷却器,其特征是:内部换热器位于内层混凝土安全壳内靠近侧壁的上部空间,冷却水箱位于外层混凝土安全壳的外侧,冷却水箱的相对位置高于内部换热器,冷却水箱与内部换热器之间通过上升管路和下降管路相连构成闭合回路,空冷冷凝-冷却器为无壳换热器、位于冷却水箱的内部,空冷冷凝-冷却器倾斜布置,空冷冷凝-冷却器的传热管一部分置于水空间、另一部分置于汽空间,冷凝-冷却器空气侧入口开于水箱侧壁靠近底面位置、通过管道联通外部大气环境与空冷冷凝-冷却器的下封头,冷凝-冷却器空气侧出口开于水箱侧壁靠近上表面的位置、通过管道联通空冷冷凝-冷却器的上封头和内层混凝土安全壳与外层混凝土安全壳构成的环形空间。
  2. 根据权利要求1所述的安全壳冷却系统,其特征是:冷却水箱的侧壁连接有水封装置,水封装置的上部连接管与冷却水箱的气空间联通,水封装置的下部连接管与冷却水箱的水空间联通,上、下部连接管间有管道跨接。
  3. 根据权利要求1或2所述的安全壳冷却系统,其特征是:在上升管路和下降管路上均设有内部和外部隔离阀组。
  4. 一种安全壳与反应堆压力容器联合冷却系统,其特征是:包括安全壳冷却系统和反应堆压力容器冷却系统;所述安全壳冷却系统包括内部换热器、上升管路、下降管路、隔离阀、冷却水箱和空冷冷凝-冷却器,内部换热器位于内层混凝土安全壳内靠近侧壁的上部空间,冷却水箱位于外层混凝土安全壳的外侧,冷却水箱的相对位置高于内部换热器,冷却水箱与内部换热器之间通过上升管路和下降管路相连构成闭合回路,空冷冷凝-冷却器为无壳换热器、位于冷却水箱的内部,空冷冷凝-冷却器倾斜布置,空冷冷凝-冷却器的传热管一部分置于水空间、另一部分置于汽空间,冷凝-冷却器空气侧入口开于水箱侧壁靠近底面位置、通过管道联通外部大气环境与空冷冷凝-冷却器的下封头,冷凝-冷却器空气侧出口开于水箱侧壁靠近上表面的位置、通过管道联通空冷冷凝-冷却器的上封头和内层混凝土安全壳与外层混凝土安全壳构成的环形空间;所述反应堆压力容器冷却系统包括储水罐、压力平衡管、注水管、隔离水池、控制阀、连通管、凝液收集水池、蓄水箱和排气管,储水罐位于隔离水池的上方,储水罐与隔离水池之间通过压力平衡管和注水管连接,隔离水池与反应堆堆坑之间通过连通管连接,反应堆压力容器位于反应堆堆坑中,凝液收集水池位于内部换热器下方,凝液收集水池经管线依次连接蓄水箱、调节阀和隔离水池。
  5. 根据权利要求4所述的安全壳与反应堆压力容器联合冷却系统,其特征是:压力平衡管上端位于储水罐的气空间内,下端相对位置高于反应堆压力容器的上边缘。
  6. 根据权利要求4所述的安全壳与反应堆压力容器联合冷却系统,其特征是:注水管上端与储水罐的最低点连接,下端相对位置低于压力平衡管的下边缘。
  7. 根据权利要求4所述的安全壳与反应堆压力容器联合冷却系统,其特征是:注水管下端出水口呈“S”形。
  8. 根据权利要求4所述的安全壳与反应堆压力容器联合冷却系统,其特征是:注水管上设有控制阀。
  9. 根据权利要求4所述的安全壳与反应堆压力容器联合冷却系统,其特征是:蓄水箱上部通过排气管与凝液收集水池联通,蓄水箱下部设有排污阀。
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