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

Info

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
Authority
WO
WIPO (PCT)
Prior art keywords
containment
cooling
water
cooler
air
Prior art date
Application number
PCT/CN2014/001003
Other languages
English (en)
French (fr)
Chinese (zh)
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 KR1020167034756A priority Critical patent/KR102085983B1/ko
Priority to CA2954136A priority patent/CA2954136C/en
Priority to JP2017504086A priority patent/JP6277322B2/ja
Priority to CN201480075917.6A priority patent/CN106104701B/zh
Publication of WO2016011569A1 publication Critical patent/WO2016011569A1/zh

Links

Images

Classifications

    • 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 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.

Landscapes

  • 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)
PCT/CN2014/001003 2014-07-24 2014-11-13 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 WO2016011569A1 (zh)

Priority Applications (4)

Application Number Priority Date Filing Date Title
KR1020167034756A KR102085983B1 (ko) 2014-07-24 2014-11-13 격납용기 냉각 시스템 및 격납용기와 원자로 압력용기의 연합 냉각 시스템
CA2954136A CA2954136C (en) 2014-07-24 2014-11-13 Containment cooling system and containment and reactor pressure vessel joint cooling system
JP2017504086A JP6277322B2 (ja) 2014-07-24 2014-11-13 格納容器冷却系、及び格納容器・原子炉圧力容器共同冷却系
CN201480075917.6A CN106104701B (zh) 2014-07-24 2014-11-13 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

Applications Claiming Priority (4)

Application Number Priority Date Filing Date Title
CN201410353537.6 2014-07-24
CN201410353537.6A CN104103325B (zh) 2014-07-24 2014-07-24 一种长期非能动安全壳热量导出系统
CN201410353978.6 2014-07-24
CN201410353978.6A CN104091621B (zh) 2014-07-24 2014-07-24 非能动堆外冷却系统

Publications (1)

Publication Number Publication Date
WO2016011569A1 true WO2016011569A1 (zh) 2016-01-28

Family

ID=55162379

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CN2014/001003 WO2016011569A1 (zh) 2014-07-24 2014-11-13 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

Country Status (5)

Country Link
JP (1) JP6277322B2 (ja)
KR (1) KR102085983B1 (ja)
CN (1) CN106104701B (ja)
CA (1) CA2954136C (ja)
WO (1) WO2016011569A1 (ja)

Cited By (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106782698A (zh) * 2016-11-28 2017-05-31 哈尔滨工程大学 一种采用喷射技术的长期高效非能动安全壳冷却系统
CN108630327A (zh) * 2017-03-24 2018-10-09 国家电投集团科学技术研究院有限公司 非能动安全壳换热器系统
CN108630329A (zh) * 2017-03-24 2018-10-09 国家电投集团科学技术研究院有限公司 安全壳内置换热器
CN109341069A (zh) * 2018-10-26 2019-02-15 江苏永钢集团有限公司 一种新型热水箱补水控制系统
CN109765067A (zh) * 2017-11-10 2019-05-17 国核华清（北京）核电技术研发中心有限公司 大型先进压水堆核电站非能动堆芯冷却系统整体性能试验平台
CN110491529A (zh) * 2018-05-15 2019-11-22 华龙国际核电技术有限公司 一种冷却系统
CN110489796A (zh) * 2019-07-17 2019-11-22 哈尔滨工程大学 一种基于热管的核反应堆热量导出系统的有效性判断方法
CN110570957A (zh) * 2019-09-06 2019-12-13 长江勘测规划设计研究有限责任公司 地下核电站多级往复式非能动冷却系统
CN110580958A (zh) * 2019-09-06 2019-12-17 长江勘测规划设计研究有限责任公司 地下核电站钢制安全壳非能动外置管网冷却系统
CN111599498A (zh) * 2020-04-14 2020-08-28 中国核电工程有限公司 一种非能动安全壳空气-水长期冷却系统
CN112652413A (zh) * 2020-11-26 2021-04-13 中国核电工程有限公司 安全壳系统的布置方法以及安全壳系统布置结构
CN113035394A (zh) * 2021-03-05 2021-06-25 哈尔滨工程大学 一种采用储气隔间式的安全壳内置高效换热器
CN113488214A (zh) * 2021-07-22 2021-10-08 中国核动力研究设计院 一种核电厂压力容器上封头有汽时的自然循环冷却方法
CN113704959A (zh) * 2021-07-12 2021-11-26 中国核电工程有限公司 一种换热器式非能动安全壳冷却系统的模拟方法及系统
CN113865904A (zh) * 2021-09-24 2021-12-31 哈尔滨工程大学 一种多功能流动换热的试验装置
CN114068049A (zh) * 2021-11-22 2022-02-18 中国核动力研究设计院 一种缓冲装置及非能动余热排出系统
CN114220573A (zh) * 2021-11-02 2022-03-22 中国核电工程有限公司 一种基于二次蒸发冷却的增强型非能动安全壳热量排出系统
CN115240879A (zh) * 2022-07-05 2022-10-25 上海核工程研究设计院有限公司 一种双层安全壳反应堆安全系统及反应堆系统

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107958712A (zh) * 2017-11-23 2018-04-24 中国核电工程有限公司 一种热管换热式非能动安全壳热量导出系统
CN109841289A (zh) * 2017-11-29 2019-06-04 国家电投集团科学技术研究院有限公司 用于安全壳热量非能动导出系统的试验装置
JP6994967B2 (ja) 2018-02-01 2022-02-04 本田技研工業株式会社 軸受装置
CN108492892B (zh) * 2018-02-28 2020-04-07 哈尔滨工程大学 一种内置式安全壳过滤排放系统
CN109346196B (zh) * 2018-11-13 2022-04-15 中国核动力研究设计院 一种能动和非能动冷却相结合的熔融物堆内滞留系统
CN109585044B (zh) * 2018-12-18 2024-04-12 长江勘测规划设计研究有限责任公司 一种地下核电站洞室型安全壳非能动冷却系统
CN111599493B (zh) * 2020-05-09 2023-03-31 哈尔滨工程大学 一种抑压水池
KR102437395B1 (ko) 2020-08-19 2022-08-30 한국원자력연구원 원자로의 피동형 보호 계통
CN112053791B (zh) * 2020-09-15 2023-01-03 哈尔滨工程大学 一种具有集成释热阱的无时限非能动联合排热系统
CN113593733A (zh) * 2021-07-02 2021-11-02 中国核电工程有限公司 一种非能动钢制安全壳热量导出系统
CN113707347A (zh) * 2021-07-12 2021-11-26 中国核电工程有限公司 一种防止核电厂安全壳喷淋系统误加药的方法及判断模块
US20230395271A1 (en) * 2022-06-02 2023-12-07 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for reducing noncondensable gas buildup in coolant systems
CN116598028B (zh) * 2022-11-28 2024-01-19 上海核工程研究设计院股份有限公司 一体化核反应堆严重事故的预防缓解系统及其控制方法

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5694442A (en) * 1994-02-14 1997-12-02 Enel S.P.A. System for passively dissipating heat from the interior of a nuclear reactor containment structure
CN102737738A (zh) * 2012-06-25 2012-10-17 中国核电工程有限公司 双层混凝土安全壳非能动直接蒸发式冷却系统
CN102867550A (zh) * 2012-08-20 2013-01-09 中国核电工程有限公司 一种应对全厂断电事故的非能动排热装置
CN102097139B (zh) * 2010-10-27 2013-01-16 华北电力大学 一种基于纳米流体特性的核电站严重事故缓解系统
CN202855318U (zh) * 2012-09-04 2013-04-03 中科华核电技术研究院有限公司 一种用于核电站的非能动启动冷却系统及核电站系统
CN104103325A (zh) * 2014-07-24 2014-10-15 哈尔滨工程大学 一种长期非能动安全壳热量导出系统

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59193395A (ja) * 1983-04-18 1984-11-01 株式会社東芝 原子炉格納容器内雰囲気冷却装置
JPH02253192A (ja) * 1989-03-28 1990-10-11 Toshiba Corp 自然放熱型格納容器の冷却システム
US5049353A (en) * 1989-04-21 1991-09-17 Westinghouse Electric Corp. Passive containment cooling system
JP4834349B2 (ja) * 2005-08-18 2011-12-14 株式会社東芝 原子炉格納容器冷却設備
KR101297101B1 (ko) * 2011-11-01 2013-08-19 한국원자력연구원 원자로의 잔열 제거 장치
CN202615805U (zh) * 2012-05-02 2012-12-19 哈尔滨工程大学 一种非能动安全壳冷却系统
KR101480046B1 (ko) * 2013-05-08 2015-01-09 한국원자력연구원 비상냉각탱크 냉각설비 및 이를 구비하는 원전
CN104091621B (zh) * 2014-07-24 2016-08-03 哈尔滨工程大学 非能动堆外冷却系统
KR101742644B1 (ko) 2016-09-13 2017-06-07 한국원자력연구원 공냉 이중 격납건물을 갖는 피동보조급수 냉각계통

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5694442A (en) * 1994-02-14 1997-12-02 Enel S.P.A. System for passively dissipating heat from the interior of a nuclear reactor containment structure
CN102097139B (zh) * 2010-10-27 2013-01-16 华北电力大学 一种基于纳米流体特性的核电站严重事故缓解系统
CN102737738A (zh) * 2012-06-25 2012-10-17 中国核电工程有限公司 双层混凝土安全壳非能动直接蒸发式冷却系统
CN102867550A (zh) * 2012-08-20 2013-01-09 中国核电工程有限公司 一种应对全厂断电事故的非能动排热装置
CN202855318U (zh) * 2012-09-04 2013-04-03 中科华核电技术研究院有限公司 一种用于核电站的非能动启动冷却系统及核电站系统
CN104103325A (zh) * 2014-07-24 2014-10-15 哈尔滨工程大学 一种长期非能动安全壳热量导出系统

Cited By (28)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106782698A (zh) * 2016-11-28 2017-05-31 哈尔滨工程大学 一种采用喷射技术的长期高效非能动安全壳冷却系统
CN108630329B (zh) * 2017-03-24 2024-05-31 国家电投集团科学技术研究院有限公司 安全壳内置换热器
CN108630327A (zh) * 2017-03-24 2018-10-09 国家电投集团科学技术研究院有限公司 非能动安全壳换热器系统
CN108630329A (zh) * 2017-03-24 2018-10-09 国家电投集团科学技术研究院有限公司 安全壳内置换热器
CN108630327B (zh) * 2017-03-24 2023-08-25 国核示范电站有限责任公司 非能动安全壳换热器系统
CN109765067A (zh) * 2017-11-10 2019-05-17 国核华清（北京）核电技术研发中心有限公司 大型先进压水堆核电站非能动堆芯冷却系统整体性能试验平台
CN110491529A (zh) * 2018-05-15 2019-11-22 华龙国际核电技术有限公司 一种冷却系统
CN109341069A (zh) * 2018-10-26 2019-02-15 江苏永钢集团有限公司 一种新型热水箱补水控制系统
CN110489796A (zh) * 2019-07-17 2019-11-22 哈尔滨工程大学 一种基于热管的核反应堆热量导出系统的有效性判断方法
CN110489796B (zh) * 2019-07-17 2022-06-21 哈尔滨工程大学 一种基于热管的核反应堆热量导出系统的有效性判断方法
CN110580958A (zh) * 2019-09-06 2019-12-17 长江勘测规划设计研究有限责任公司 地下核电站钢制安全壳非能动外置管网冷却系统
CN110580958B (zh) * 2019-09-06 2024-04-12 长江勘测规划设计研究有限责任公司 地下核电站钢制安全壳非能动外置管网冷却系统
CN110570957B (zh) * 2019-09-06 2024-04-12 长江勘测规划设计研究有限责任公司 地下核电站多级往复式非能动冷却系统
CN110570957A (zh) * 2019-09-06 2019-12-13 长江勘测规划设计研究有限责任公司 地下核电站多级往复式非能动冷却系统
CN111599498A (zh) * 2020-04-14 2020-08-28 中国核电工程有限公司 一种非能动安全壳空气-水长期冷却系统
CN111599498B (zh) * 2020-04-14 2022-11-18 中国核电工程有限公司 一种非能动安全壳空气-水长期冷却系统
CN112652413A (zh) * 2020-11-26 2021-04-13 中国核电工程有限公司 安全壳系统的布置方法以及安全壳系统布置结构
CN112652413B (zh) * 2020-11-26 2024-01-23 中国核电工程有限公司 安全壳系统的布置方法以及安全壳系统布置结构
CN113035394B (zh) * 2021-03-05 2023-12-19 哈尔滨工程大学 一种采用储气隔间式的安全壳内置高效换热器
CN113035394A (zh) * 2021-03-05 2021-06-25 哈尔滨工程大学 一种采用储气隔间式的安全壳内置高效换热器
CN113704959B (zh) * 2021-07-12 2024-04-09 中国核电工程有限公司 一种换热器式非能动安全壳冷却系统的模拟方法及系统
CN113704959A (zh) * 2021-07-12 2021-11-26 中国核电工程有限公司 一种换热器式非能动安全壳冷却系统的模拟方法及系统
CN113488214B (zh) * 2021-07-22 2024-01-23 中国核动力研究设计院 一种核电厂压力容器上封头有汽时的自然循环冷却方法
CN113488214A (zh) * 2021-07-22 2021-10-08 中国核动力研究设计院 一种核电厂压力容器上封头有汽时的自然循环冷却方法
CN113865904A (zh) * 2021-09-24 2021-12-31 哈尔滨工程大学 一种多功能流动换热的试验装置
CN114220573A (zh) * 2021-11-02 2022-03-22 中国核电工程有限公司 一种基于二次蒸发冷却的增强型非能动安全壳热量排出系统
CN114068049A (zh) * 2021-11-22 2022-02-18 中国核动力研究设计院 一种缓冲装置及非能动余热排出系统
CN115240879A (zh) * 2022-07-05 2022-10-25 上海核工程研究设计院有限公司 一种双层安全壳反应堆安全系统及反应堆系统

Also Published As

Publication number Publication date
KR20170039083A (ko) 2017-04-10
CA2954136C (en) 2018-02-13
JP2017521674A (ja) 2017-08-03
KR102085983B1 (ko) 2020-03-06
JP6277322B2 (ja) 2018-02-07
CA2954136A1 (en) 2016-01-28
CN106104701A (zh) 2016-11-09
CN106104701B (zh) 2018-06-08

Similar Documents

Publication Publication Date Title
WO2016011569A1 (zh) 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
CN103903659B (zh) 浮动核电站非能动余热排出系统
JP2642763B2 (ja) 原子炉系
JP4675926B2 (ja) 沸騰水型原子炉
CN104103325B (zh) 一种长期非能动安全壳热量导出系统
WO2016078421A1 (zh) 非能动安全冷却系统
CN102637465B (zh) 一种非能动安全壳冷却系统
GB2531190A (en) Passive concrete containment cooling system
CN103617815A (zh) 压水堆核电站非能动余热排出系统
CN108461163A (zh) 应急堆芯冷却系统和使用该应急堆芯冷却系统的沸水反应堆装置
KR101250479B1 (ko) 안전보호용기를 구비한 피동형 비상노심냉각설비 및 이를 이용한 열 전달량 증가 방법
CN104916334A (zh) 压水堆核电站分离式热管式非能动余热排出系统
WO2017045159A1 (zh) 核电站反应堆压力容器与屏蔽墙的组合结构
CN109273112B (zh) 一种反重力方向流动的直接冷却非能动余热排出系统
RU152416U1 (ru) Система аварийного отвода тепла
CN205656860U (zh) 低温核供热堆堆芯余热非能动排出系统
KR101559017B1 (ko) 중대사고방지 무인사고대처 원자로 및 그 동작 방법
US20040240601A1 (en) Forced cooling circular deep & minus; water pond type heat supply nuclear reactor with natural circulation
CN204178729U (zh) 一种长期非能动安全壳热量导出系统
CN210271804U (zh) 一种注水式铅铋快堆应急余热排出系统
CN103531256B (zh) 压水堆预应力混凝土安全壳非能动冷却系统
CN204680390U (zh) 压水堆核电站分离式热管式非能动余热排出系统
JP6359318B2 (ja) 静的原子炉格納容器冷却系および原子力発電プラント
CN203931516U (zh) 一种应用相变传热的非能动安全壳冷却系统
KR101473378B1 (ko) 피동안전설비 및 이를 구비하는 원전

Legal Events

Date Code Title Description
121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 14898264

Country of ref document: EP

Kind code of ref document: A1

ENP Entry into the national phase

Ref document number: 20167034756

Country of ref document: KR

Kind code of ref document: A

ENP Entry into the national phase

Ref document number: 2954136

Country of ref document: CA

ENP Entry into the national phase

Ref document number: 2017504086

Country of ref document: JP

Kind code of ref document: A

NENP Non-entry into the national phase

Ref country code: DE

122 Ep: pct application non-entry in european phase

Ref document number: 14898264

Country of ref document: EP

Kind code of ref document: A1