WO2022233141A1 - 核电厂非能动专设安全系统及供水系统 - Google Patents

核电厂非能动专设安全系统及供水系统 Download PDF

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Publication number
WO2022233141A1
WO2022233141A1 PCT/CN2021/139860 CN2021139860W WO2022233141A1 WO 2022233141 A1 WO2022233141 A1 WO 2022233141A1 CN 2021139860 W CN2021139860 W CN 2021139860W WO 2022233141 A1 WO2022233141 A1 WO 2022233141A1
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WO
WIPO (PCT)
Prior art keywords
steam
water
passive
nuclear power
power plant
Prior art date
Application number
PCT/CN2021/139860
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English (en)
French (fr)
Inventor
吴震华
吴广君
唐琪
许俊俊
刘洁
孔凡润
Original Assignee
苏州热工研究院有限公司
大亚湾核电运营管理有限责任公司
中国广核集团有限公司
中国广核电力股份有限公司
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Application filed by 苏州热工研究院有限公司, 大亚湾核电运营管理有限责任公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 苏州热工研究院有限公司
Priority to EP21939785.8A priority Critical patent/EP4273886A4/en
Publication of WO2022233141A1 publication Critical patent/WO2022233141A1/zh

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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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • 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 the field of nuclear power, more particularly, to a passive special safety system and a water supply system for a nuclear power plant.
  • the main role of engineered safety systems is to mitigate the consequences of accidents.
  • an accident such as the loss of water in the primary circuit, the rupture of the steam/water supply pipeline in the secondary circuit, the rupture of the heat transfer pipe of the steam generator, the loss of power and the low-pressure fusion reactor
  • the corresponding special safety system is activated to limit and mitigate the consequences of the accident, ensuring that Nuclear Safety Features:
  • Reactivity control that is, the chain fission reaction can be terminated
  • the third-generation nuclear power unit represented by AP1000 usually adopts the structure of a steel containment and a water tank at the top of the containment, as well as a passive cooling system on the secondary side. , and passive cooling of the secondary circuit.
  • the design is difficult to apply on the second-generation nuclear power unit, the transformation is difficult, and the cost is high.
  • AP1000 is equipped with a containment cooling system (PCS), whose main function is to extract the heat of the containment and reduce the pressure and temperature of the containment under the design basis accident that causes the increase of the pressure and temperature of the containment.
  • PCS containment cooling system
  • CNNC's Hualong No. 1 has added a high-level containment tank (about 3,000 tons of stored water), a passive containment heat transfer system (PCS) immersed in the water tank, a passive residual heat removal system (PRS) on the secondary side, and water injection into the reactor cavity.
  • PCS passive containment heat transfer system
  • PRS passive residual heat removal system
  • Passive safety systems such as cooling systems that transfer energy from the steam generator 50 or the containment atmosphere to the high-level water tank through closed-circuit piping.
  • a large number of pipelines are located at high elevations of the containment, and the mechanical analysis, pipeline anti-shake and embedded parts design are complicated, which brings a lot of trouble to building construction and equipment installation.
  • CGN's Hualong No. 1 also newly added a high-level water tank for the containment (with a storage water of 3,100 tons) and a secondary-side passive residual heat removal system (PRS) immersed in the water tank.
  • the passive containment heat export system is not designed. This part of the function is determined by (EHR) Two pumps and heat exchanger implementation of the containment heat removal system.
  • the water injection function of the pile pit is realized by the EHR system water pump, and the passive water injection is realized by the pile water injection tank set in the containment.
  • the invention discloses a passive special safety system for a nuclear power plant.
  • the system includes a secondary side passive waste heat discharge heat exchanger, a steam condensate water tank, a passive reactor cavity water injection system, a passive high pressure core replenishment tank and related valves. with pipes.
  • a series of passive and active safety facilities are invested in a step-by-step manner to effectively cool the primary loop and core of the reactor in a timely and rapid manner, so that the nuclear power plant can smoothly enter a safe cooling system.
  • the shutdown state can suppress or alleviate the consequences of serious reactor accidents, reduce accident hazards, and improve the safety of nuclear power plants.
  • a passive special safety facility for a nuclear power plant CN201610297360.1
  • the invention provides a passive special safety facility for a nuclear power plant, which includes: a discharge line; a heat exchanger; a diffuser; a quick pressure relief valve and an injection General Manager.
  • the passive special safety facility of the nuclear power plant provided by the invention is different from the special safety facility of the traditional nuclear power plant.
  • the connection of the passive special safety facility is centrally arranged on the pressure vessel, and the core is directly cooled through the passive special safety facility. and water injection, which increases the natural circulation capacity and makes the safety protection system more secure and reliable.
  • the technical problem to be solved by the present invention is to provide an improved passive special safety system and water supply system of a nuclear power plant.
  • the technical solution adopted by the present invention to solve the technical problem is to construct a water supply system for the passive special safety system of the nuclear power plant, which is combined with the passive containment cooling system, Secondary side passive cooling system, spray system and/or core assembly connection, including at least one steam pressurized water tank, steam pressurized line, make-up water line and drain line;
  • the steam pressurized pipeline is connected with the steam pressurized water tank and the steam generator in the passive special safety system of the nuclear power plant and/or an external steam system;
  • the water supply pipeline is connected with the steam pressurized water tank and an external water source;
  • the drain line is connected to the steam pressurized water tank, and is connected to the passive containment cooling system, the secondary passive cooling system, the spray system and/or the core assembly.
  • the steam pressurized water tank includes a tank body, and a plurality of partitions disposed in the tank body to divide the space in the tank body into a plurality of water chambers.
  • the box body is a horizontal box body, and a plurality of the partition plates are arranged at intervals along the length direction of the box body.
  • the box body includes a bottom wall and a top wall opposite to the bottom wall;
  • the bottom wall is provided with a plurality of the partitions extending toward the top wall;
  • the top wall is provided with a plurality of the partitions extending toward the bottom wall;
  • the plurality of the partition plates on the top wall and the plurality of the partition plates on the bottom wall are arranged in a staggered manner so that the plurality of water chambers communicate with each other.
  • each of the water chambers is provided with an exhaust line, and an exhaust valve is provided on the exhaust line.
  • the multiple steam pressurized water tanks there are multiple steam pressurized water tanks, and the multiple steam pressurized water tanks are connected in sequence;
  • the water supply system also includes a series pipeline arranged between the two adjacently arranged steam pressurized water tanks to connect the two adjacently arranged steam pressurized water tanks; the series pipeline is provided with communication or isolation A series valve of two adjacent steam pressurized water tanks;
  • the series pipeline is connected with the drainage pipeline; the end of the series pipeline connected with the drainage pipeline is provided with an outlet valve.
  • the multiple water supply lines are connected to the multiple steam pressurized water tanks in one-to-one correspondence.
  • a steam pressurization valve is provided on the steam pressurization line.
  • a water supplement valve is provided on the water supplement line.
  • the present invention also constructs a passive special safety system for a nuclear power plant, including a passive containment cooling system, a secondary side passive cooling system, a core assembly, a steam generator, a spray system, and the Water supply systems for passive engineered safety systems in nuclear power plants;
  • the passive containment cooling system is disposed opposite to the core assembly
  • the core assembly is connected to the steam generator
  • the secondary side passive cooling system is connected to the steam generator and/or the passive containment cooling system
  • the steam pressurization pipeline of the water supply system is connected to the steam generator, and the drainage pipeline of the water supply system is connected to the passive containment cooling system, the secondary passive cooling system, the spray system and/or the core Component connection.
  • the passive special safety system and water supply system of the nuclear power plant implemented in the present invention have the following beneficial effects: the water supply system is provided with at least one steam pressurized water tank, and is connected to the nuclear power plant through the steam pressurized pipeline connected with the steam pressurized water tank.
  • the steam generator in the passive special safety system is connected, the drain line is connected with the steam pressurized water tank, and with the passive containment cooling system, the secondary side passive cooling system and/or the core assembly, thereby It can be used as a backup means to supply water to the passive containment cooling system, secondary passive cooling system and/or core components in the event of failure of the active special safety system, so as to provide timely and rapid cooling of the primary loop and core of the reactor. Carry out effective cooling, so that the nuclear power plant can smoothly enter a safe cold shutdown state, suppress or alleviate the consequences of serious reactor accidents, reduce accident hazards, and improve the safety of nuclear power plants.
  • FIG. 1 is a schematic structural diagram of a passive special safety system of a nuclear power plant in some embodiments of the present invention.
  • FIG. 1 shows some preferred embodiments of the passive engineered safety system for a nuclear power plant of the present invention.
  • the passive engineered safety system of the nuclear power plant is used as a backup passive engineered safety system in the event of failure of the active engineered safety system after an accident in the reactor to establish the core cooling capacity, ensure radioactive containment, and limit and mitigate the accident. consequences, ensuring nuclear safety.
  • it can replace the high-level water tank of the existing third-generation nuclear power unit containment, reduce the load of the containment, and improve the safety of the containment.
  • the passive engineered safety system of the nuclear power plant may include a containment 10 , a core assembly 20 , a passive containment cooling system 30 , a secondary side passive cooling system 40 , a steam Generator 50 , spray system 70 and water supply system 60 .
  • the containment vessel 10 can be used to accommodate the core assembly 20 , the passive containment vessel cooling system 30 , and the steam generator 50 .
  • the core assembly 20 can be disposed in the mounting shell 10 and can be connected with the steam generator 40 .
  • the passive containment cooling system 30 can be disposed in the upper space of the installation shell 10 and disposed opposite to the core assembly 20 , and can be used for cooling the core assembly 20 .
  • the secondary side passive cooling system 40 may be disposed on the upper portion of the containment vessel 10 and may be connected to the steam generator 40 and the passive safety cooling system 30 .
  • the secondary side passive cooling systems 40 may be two groups, one of which may be connected to the steam generator 40 , and the other group may be connected to the passive safety cooling system 30 .
  • the steam generator 50 may be connected to the core assembly 20 and the steam generator 40 .
  • the spraying system 70 may be disposed in the upper space of the containment vessel 10, may be disposed opposite the core assembly 20, and the core assembly 20 may be cooled by spraying.
  • the water supply system may be connected to the passive containment cooling system 30 , the secondary side passive cooling system 40 , the spray system 70 and the core assembly 20 , and may supply the passive containment cooling system 30 , the secondary side passive cooling system 40 , the spray system 70 and the core assembly 20 for water supply.
  • the passive containment cooling system 30 the secondary side passive cooling system 40 , the spray system 70 or the core assembly 20 may be connected.
  • the core assembly 20 may be disposed at the lower portion of the containment vessel 10, and may include a pressure vessel 21, and the pressure vessel 21 may be a nuclear fuel reaction vessel.
  • the pressure vessel 21 can be placed in the pile pit, the coolant input end of the pressure vessel 21 can be connected with the low pressure safety injection system 23 , and the pile pit can be connected with the pile pit water injection system 22 .
  • the coolant output of the pressure vessel 21 can be connected to a steam generator 50 .
  • the passive containment cooling system 30 may include a helical coil, which may be disposed in the dome area of the containment 10 , and may be connected with the secondary side passive cooling system 40 . Connections, specifically, in some embodiments, the helical coil may be connected to the heat exchanger 42 of the secondary side passive cooling system 40 .
  • the secondary side passive cooling system 40 may include a water tank 41 and a heat exchanger 42 disposed in the water tank 41 .
  • the water tank 41 can be connected to the water supply system 60 , and the water supply system 60 can supply water to the water tank 41 .
  • the heat exchanger 42 can be disposed in the water tank 41 to perform heat exchange with the water body in the water tank 41 .
  • the outlet end of the heat exchanger 42 of one of the secondary side passive cooling systems 40 may be connected to the inlet end of the passive containment cooling system 30, and the inlet end of the heat exchanger 42 may be connected to the passive safety vessel.
  • the outlet end of the shell cooling system 30 is connected to transmit the cooled water body to the passive containment shell cooling system and receive the high temperature water body formed after the passive containment cooling system 30 cools the containment shell 10.
  • the inlet end of the heat exchanger 42 of the secondary side passive cooling system 40 of the group can be connected to the steam outlet of the steam generator 50, and the outlet end of the heat exchanger 42 can be connected to the water supply system 60, and the output end of the steam generator 50 can be connected.
  • the steam is cooled, and the water body formed after cooling is transported to the water supply system 60 for recycling.
  • the number of the steam generators 50 may be three. Of course, it is understood that in other embodiments, the number of the steam generators 50 may not be limited to three.
  • the steam outlet lines 51 of the three steam generators 50 can be connected to each other.
  • Each steam generator 50 may include a casing and heat exchange tubes disposed in the casing.
  • the inlet end of the housing can be connected to the water supply system 60, and the water supply system 60 can deliver water to the inlet end of the housing.
  • the steam outlet end of the casing can be connected to a steam outlet line 51, and the steam outlet line 51 can be connected to a steam output line 53 to deliver the steam to the steam turbine to drive the steam turbine to do work.
  • a pressure relief line 52 may be provided on the steam outlet line 51 , and an atmospheric relief valve 521 may be arranged on the pressure relief line 52 , and the atmospheric relief valve 521 may be opened to release pressure to the steam outlet line 51 in time.
  • the steam output line 53 can be connected to one end of the steam pressurized main pipe 54, and the other end of the steam pressurized main pipe 54 can be connected to the water supply system 60 to deliver steam to the water supply system 60 to supply water to the water supply The system 60 is pressurized so that the water supply system 60 outputs a body of water.
  • a main steam isolation valve 541 may be provided on the steam pressurization main pipe 54 , and the main steam isolation valve 541 may be opened to supply steam to the water supply system 60 .
  • the spray system 70 may be disposed below the passive containment cooling system 30, may be located above the core assembly 20, and may spray the core assembly 20 to cool the stack Core assembly 20 .
  • the sprinkler system 70 may be connected to the water supply system 60 , and water may be supplied from the water supply system 60 .
  • the water supply system 60 may include at least one steam pressurized water tank 61 , a steam pressurized line 62 , a make-up water line 63 and a drain line 64 .
  • the steam pressurized water tank 61 can be connected to the steam generated by the steam generator 50, and the steam is pressurized to drive the water body placed in the steam pressurized water tank 61 to be transported out.
  • the steam pressurization line 62 may be connected to the steam pressurization water tank 61 and the steam generator 50, specifically, in some embodiments, the steam pressurization line 62 may be the steam pressurization main pipe 54 and the steam pressurization The pressurized steam inlet of the water tank 61 is connected.
  • the water supply line 63 can be connected with the steam pressurized water tank 61 and an external water source, and can timely supply water to the steam pressurized water tank 61 .
  • the drain line 64 can be connected to the steam pressurized water tank 61 , and can be connected to the passive containment cooling system 30 , the secondary passive cooling system 40 , the spray system 70 and the core assembly 20 connect.
  • the drain line 64 may also only be connected to the passive containment cooling system 30 , the secondary side passive cooling system 40 , the spray system 70 or the core assembly 20 .
  • the steam pressurized water tank 61 may include a tank body 611 and a plurality of partitions 612 .
  • the box body 611 may be a horizontal box body, and the plurality of partitions 612 may be disposed in the box body 611 , and may be arranged at intervals along the length direction of the box body 611 , and may be arranged with the bottom wall of the box body 611 at intervals.
  • the included angle is set to conduct flow diversion, and the space in the box body 611 is divided into a plurality of water chambers 613 .
  • the box body 611 may include a bottom wall and a top wall opposite to the bottom wall.
  • the bottom wall is provided with a plurality of partitions 612
  • the top wall is also provided with a plurality of partitions 612.
  • the plurality of partitions 612 on the bottom wall can extend toward the top wall, and can be perpendicular to the bottom wall , to form a vertical diversion design
  • a plurality of partitions 612 on the top wall can be extended toward the bottom wall, and can be perpendicular to the top wall to form a vertical diversion design.
  • the height of the partition plate 612 can be smaller than the height of the box body 611, and the plurality of partition plates 612 on the top wall and the plurality of partition plates 612 on the lower wall can be staggered, so that the plurality of water chambers 613 communicate with each other,
  • the advantage of the vertical diversion design is to avoid excessive contact between hot steam and cold water and reduce steam consumption. The higher the temperature of the water, the lower the density of the water, the steam or hot water is always above the cold water, thereby limiting the contact area between the steam and the cold water, reducing the steam consumption and reducing the water temperature rise.
  • the upper part of the water chamber 613 at the left end of the box body 611 can be provided with a pressurized steam inlet, the pressurized steam inlet can be connected with the steam pressurization line 62, and the lower part of the water chamber 613 at the right end of the box body 611 can be provided A drain, which can be connected to the drain line 64 .
  • an exhaust line 614 may be provided on each water chamber 613 , and the exhaust line 614 may be used to exhaust the steam in each water chamber 613 .
  • an exhaust valve 6141 may be provided on the exhaust line 614 , and the exhaust valve 6141 may be opened to allow the steam in the water chamber 613 to be discharged from the exhaust line 614 . After the tank body 611 is emptied, the exhaust valve 6141 can be opened to discharge the high pressure steam of the tank body 611 to relieve the pressure of the water tank.
  • the steam pressurization line 62 can be provided in a one-to-one correspondence with the steam pressurized water tank 61, and can be connected to the pressurized steam inlet on the upper part of the water chamber 613 of the steam pressurized water tank 61, so as to make High pressure steam can enter from the upper part of each water chamber 613, press the water down, and inject from the drain line 64 into the passive containment cooling system 30, the secondary passive cooling system 40, the spray system 70 and the core assembly 20, it can also enter the next-stage steam pressurized water tank 61 through the series pipeline 65.
  • a bypass valve 621 may be provided on the steam pressurization line 62, and the bypass valve 621 may be opened to allow the steam in the steam pressurization parent pipe 54 to be output to the steam pressurization line 62 and input to the steam Pressurized water tank 61 .
  • the steam pressurization line 62 may also be connected to an external steam system.
  • the external steam system can be the SVA auxiliary steam system and the main steam system of the adjacent unit.
  • the steam pressurization line 62 can be selected from the steam generator 50 of the passive special safety system of the nuclear power plant for gas supply, or from an external steam system for gas supply.
  • the atmospheric discharge valve 521 can be opened to reduce the steam pressure to 15 bar.G. When the SVA assists the steam supply, the pressure is not reduced.
  • the water replenishment line 63 may be provided in a one-to-one correspondence with the steam pressurized water tank 61.
  • the water replenishment line 63 may not be limited to the steam pressurized water tank 61.
  • the water tanks 61 are arranged in a one-to-one correspondence. One end of the water supply line 63 can be connected to the water inlet at the lower part of the water chamber 613 at the left end of the box 611 , and the other end can be connected to an external water source.
  • one end of the water replenishment pipeline 63 can be connected to the high-level water tank on the top of the mountain and/or the demineralized water tank in the factory, so that water can be replenished to the steam pressurized water tank 61 in time.
  • a water supplement valve 631 may be provided on the water supplement line 61 , the water supplement valve 631 is opened, and the water supplement line 63 can supply water to the steam pressurized water tank 61 . Since the steam pressurized water tank 61 is installed at the height of the ground, the water level of the demineralized water tank in the factory is relatively high. Generally, there are water tanks on the mountains of the factory area, and the location is higher.
  • the water replenishment valve 631 can be opened to replenish water by gravity. After the water replenishment is completed, the water replenishment valve 631 is closed, and the steam pressurized water tank 61 can be put into operation again, or placed in a standby state.
  • one end of the drain line 64 can be connected to the water outlet at the lower part of the water chamber at the right end of the steam pressurized water tank 61, and a plurality of branch pipes can be arranged on the drain line 64, which are respectively connected to the passive The containment cooling system 30 , the secondary side passive cooling system 40 , the spray system 70 and the core assembly 20 are connected.
  • a drain valve 641 may be provided on the drain line 64 , and the drain valve 641 may be opened to supply the flow to the passive containment cooling system 30 , the secondary side passive cooling system 40 , the spray system 70 and the core assembly 20 drains.
  • a drain valve 641 may also be correspondingly provided on the branch line of the drain line 64 .
  • the steam pressurized water tanks 61 may be multiple, and the multiple steam pressurized water tanks 61 may be connected in sequence to form a multi-stage water tank group. Specifically, in some embodiments, the number of the steam pressurized water tanks 61 may be four. Of course, it is understood that in some other embodiments, the number of the steam pressurized water tanks 61 may not be limited to four, but may be one or more than four indivual. Further, in some embodiments, the water supply system further includes a series line 65 .
  • the series pipeline 65 can be arranged between two adjacently arranged steam pressurized water tanks 61, and can be used to connect the two adjacently arranged steam pressurized water tanks 61, so that the two adjacently arranged steam pressurized water tanks 61 can be connected. Connected.
  • a series valve 651 can be provided on the series pipeline 65, and the series valve 651 can be used to connect or isolate two adjacent steam pressurized water tanks 61.
  • the series valve 651 can be opened to make the plurality of steam
  • the pressurized water tank 61 forms a multi-stage water tank, the series valve 651 is closed, and each steam pressurized water tank 61 is an independent water tank.
  • the series line 65 can also be connected with the drain line 64 , and in some embodiments, an outlet valve 652 can be provided at the end of the series line 65 connecting with the drain line 64 . Opening of the outlet valve 652 allows the series line 65 to communicate with the drain line 64 .
  • the series valve 651 and the outlet valve 652 the series operation of the steam pressurized water tank can be realized, and the removal/isolation and commissioning of the steam pressurized water tank can also be realized.
  • the outlet valve 652 and the series valve 651 of the steam pressurized water tank 61 can be used to operate the steam pressurized water tank 61 independently or in parallel, or to empty the steam pressurized water tank 61 or Cut-off/isolation of water-deficient steam pressurized water tank 61 .
  • the passive special safety system of the nuclear power plant uses the high temperature and high pressure steam generated by the external steam system and/or the steam generator to inject the water in the steam pressurized water tank 61 into the passive containment for cooling in a passive way.
  • System 30 secondary passive cooling system 40 , spray system 70 and core assembly 20 .
  • the commissioning of the passive special safety system of the nuclear power plant may include three steps, namely, separation and decompression of the steam generator, pressurization of the steam pressurized water tank 61 to supply water to users, and refilling of the steam pressurized water tank.
  • the specific operations are:
  • the steam generator is separated and decompressed.
  • the separation of the steam generators 50 refers to the implementation of main steam isolation, and the main steam isolation valves 541 of the three steam generators 50 are closed. And open the atmospheric vent valve 521 to reduce the steam pressure to 15 bar.G.
  • the auxiliary steam is supplied by SVA, the pressure is not reduced;
  • the steam pressurized water tank 61 pressurizes water to the passive containment cooling system 30 , the secondary side passive cooling system 40 , the spray system 70 and the core assembly 20 .
  • the steam pressurization valve 621 of the steam pressurized water tank 61 is opened, and the steam pressurized water tank 61 is boosted to the operating pressure.
  • the outlet valve 652 of the steam pressurized water tank 61 is then opened, and the water stored in the steam pressurized water tank 61 is output from the drain line 64 to the passive containment cooling system 30, the secondary side passive cooling system 40, the spray system 70 and the core. component 20 water supply;
  • the steam pressurized water tank 61 is refilled with water. After the steam pressurized water tank 61 is emptied, the interior is filled with high pressure steam. Isolate the empty steam pressurized water tank 61 from other steam pressurized water tanks 61 , open the exhaust line 614 corresponding to each water chamber 613 to relieve pressure, and then open the water replenishment valve 631 to replenish water to the corresponding steam pressurized water tank 61 .
  • the passive special safety systems include "safety injection mode”, “containment spray mode”, “containment cooling mode”, “secondary side water replenishment mode”, “secondary side passive cooling mode”
  • safety injection mode "containment spray mode”
  • containment cooling mode "containment cooling mode”
  • secondary side water replenishment mode secondary side passive cooling mode
  • the water supply system 60 of the present invention can be used to inject water into the core assembly 20 .
  • the water temperature at the outlet of the water tank is about 30°C
  • the pressure is 15bar.G or 12bar.G
  • the pressure head is the same as the pressure head of the low pressure safety injection pump outlet
  • the outlet water temperature is close to the water temperature of the refueling water tank, so it can be used as a A row of low pressure safety injections are used.
  • the containment pressure will decrease. If the containment spray system fails due to equipment or external disasters, etc., the water supply system 60 of the present invention can be used to spray the containment.
  • the water temperature at the outlet of the water tank is about 30°C
  • the pressure is 15bar.G or 12bar.G
  • the pressure head is the same as the outlet pressure head of the containment spray pump
  • the outlet water temperature is close to the water temperature of the refueling water tank, so it can be Used as a line of containment sprays.
  • the containment high-level water tank can be eliminated in design, and only the heat exchanger 42 and the water tank 41 immersing the heat exchanger 42 can be retained.
  • a steam pressurized water tank 61 or an active water pump fills the water tank 41 immersing the heat exchanger 42, thereby reducing the containment load.
  • the passive special system can be used as a mitigation method for the accident of losing all water supply to the unit.
  • the pressurized water tank 61 replaces the main water supply system (ARE) or the auxiliary water supply system (ASG) to supply water to the SG, and withdraws the primary circuit back to the connection state of the waste heat discharge system, thereby avoiding the input of "charge-discharge mode".
  • ARE main water supply system
  • ASG auxiliary water supply system
  • the heat exchanger 42 and the water tank 41 immersing the heat exchanger 42 can be retained, and the water tank 41 with a smaller volume can be replaced for several hours.
  • the steam pressurized water tank 61 provides continuous water supply, or directly replaces the secondary side passive cooling system.
  • the reactor cavity water injection system can fill the reactor cavity with water within half an hour in the high flow (greater than 360m3/h) stage.
  • the height of the reactor cavity is -3.5m ⁇ 7.7m, and the space volume is about 180m3, and then it is transferred to the small flow (about 40m3/h) water replenishment stage to compensate for the evaporation loss. This stage lasts for about 24 hours.
  • JPD fire water distribution system
  • the safety injection system and the spray system are automatically activated according to the temperature and pressure of the primary circuit and the pressure of the containment vessel 10 and other parameters.
  • the level water tank provided on the containment vessel 10 through the steel-walled containment vessel 10 or heat exchanger, can realize the control of the containment vessel 10. Atmospheric cooling. If the equipment of the safety injection system fails or cannot be operated due to external disasters, the water charge of the primary circuit cannot be recovered, which will lead to the exposure of the core. If the equipment sprayed by the containment vessel 10 fails or cannot be operated due to external disasters, the third barrier of the reactor is at risk of rupture, and the risk of radioactive leakage increases.
  • the passive special safety system of the invention has simple operation and operation, does not rely on external resources (such as water source and power source), can be put into operation quickly after an accident, and relieves the consequences of the accident. Therefore, the passive special safety system should be used as an effective backup for the safety injection system and the sprinkler system 70 in the containment 10 after the "primary circuit breach accident".
  • the high water tank of the containment shell 10 can be eliminated in design, and only the heat exchanger 41 and the water tank 42 of the immersion heat exchanger 41 are retained.
  • water is injected into the water tank 42 of the immersion heat exchanger 41 through the steam pressurized water tank 61 or the active water pump, thereby reducing the load of the containment vessel 10 .
  • the "charge-exhaust mode” will be used to maintain the core cooling and withdraw.
  • the implementation of this strategy is divided into two steps: 1. Waiting; 2. Open the pressure relief pipeline of the pressure regulator and start the safety injection; 3. Put the containment 10 spray into operation, and the heat is removed by the containment 10 spray system (EAS) cooler. It is transferred to the equipment cooling water system (RRI), and then the heat is transferred to the sea by the important plant water system (SEC).
  • This strategy can effectively bring the unit to the state where the waste heat discharge system is connected, but it also causes great damage to the unit.
  • the unit may face the consequences of long-term shutdown for system equipment maintenance, or even direct decommissioning.
  • the passive special system of the present invention can be used as a mitigation means for the accident of losing all the water supply of the unit.
  • the passive special safety system establishes the water supply for the steam generator 50, and withdraws the primary circuit back to the connection state of the waste heat discharge system, thereby avoiding the input of the "charge-discharge mode".
  • the water tank of the heat exchanger and the immersion heat exchanger can be kept and the volume of the water tank can be reduced to maintain operation for several hours.
  • the Steam pressurized water tanks provide continuous make-up, or directly replace secondary passive cooling systems.
  • the passive special safety system of the invention has simple operation and operation, does not rely on external resources (such as water source and power source), can be put into operation quickly after an accident, and relieves the consequences of the accident. Therefore, for NPPs without secondary passive cooling systems, the non-energy-specific safety system should be the first choice after the "loss of all water supply accident".
  • the heat exchanger 42 and the water tank 41 immersing the heat exchanger 42 can be retained, and the water tank with a smaller volume can be replaced to maintain operation for several hours.
  • the secondary side passive cooling system When the secondary side passive cooling system When the system is put into operation, continuous water supply is provided by the steam pressurized water tank 61 .
  • the large flow stage of RPF can fill the reactor cavity with water within half an hour, and then transfer to the small flow water replenishment stage to compensate for the evaporation loss. This stage lasts for about 24 hours.
  • JPD fire-fighting water distribution system
  • a temporary water injection interface can be added to the system, and water can be taken from the steam pressurized water tank 61 of the present invention and injected into the reactor cavity.
  • a primary circuit break accident occurs in a passive special safety system equipped with four steam pressurized water tanks 60 in a third-generation unit with a high-level water tank 41 installed on the containment as an example.
  • Cooling the core requires an adequate source of water as a cooling medium.
  • the cooling and depressurization of the containment vessel 10 requires a sufficient water source as a spray water source.
  • This implementation case uses demineralized water in the factory as the cooling water source.
  • the main steam generated by the steam generator 50 still has high-temperature and high-pressure energy. After being decompressed by the atmospheric discharge valve 521, it can be used as water injection power to drive the low-pressure water of the steam pressurized water tank 61 into the system requiring cooling water.
  • the water injection channel needs to be opened as soon as possible, and the discharge valve 641 that is directly connected to the steam pressurized water tank 61 should be opened.
  • the system is put into operation according to the three steps in the technical solution.
  • Step 1 The steam generator is separated and decompressed. Implement the main steam isolation, and close the main steam isolation valves of the three steam generators 50. And reduce the steam pressure to 15bar.G through the pressure reducing valve. No depressurization when gas is supplied via SVA auxiliary steam.
  • Step 2 The steam pressurized water tank 61 pressurizes water to the core assembly 20 , the passive containment cooling system 30 , the secondary side passive cooling system 40 , the steam generator 50 , and/or the spray system 70 .
  • the steam pressurization valve 621 of the first steam pressurized water tank 61 is opened, and the steam pressurized water tank 61 is boosted to the operating pressure.
  • the outlet valve 652 of the last steam pressurized water tank 61 is opened, and the water stored in the steam pressurized water tank 61 is output from the drain line 64 to the core assembly 20, the passive containment cooling system 30, the secondary side passive cooling system 40, and the steam generation. water to the device 50, and/or the sprinkler system 70.
  • Step 3 The steam pressurized water tank 61 is refilled with water. After the steam pressurized water tank 61 is emptied, the interior is filled with high pressure steam. It is isolated from other steam pressurized water tanks 61, and the exhaust line 614 corresponding to each water chamber 613 is opened to relieve pressure. Since the steam pressurized water tank is installed at the ground level, the water level of the demineralized water tank in the factory is relatively high. There are generally water tanks on the mountains of the factory area, and the location is higher. Therefore, after the steam pressurized water tank 61 is completely depressurized, the water replenishment valve 631 can be opened to replenish water by gravity. After the water replenishment is completed, close the water replenishment valve, and then it can be put back into the steam pressurized water tank 61, or placed in a standby state.
  • the system is put into operation according to the three steps in the technical solution.
  • Step 1 The steam generator is separated and decompressed. Implement the main steam isolation, and close the main steam isolation valves of the three steam generators 50. And reduce the steam pressure to 15bar.G through the pressure reducing valve. No depressurization when gas is supplied via SVA auxiliary steam.
  • Step 2 The steam pressurized water tank 61 pressurizes water to the core assembly 20 , the passive containment cooling system 30 , the secondary side passive cooling system 40 , the steam generator 50 , and/or the spray system 70 .
  • the steam pressurization valve 621 of the first steam pressurized water tank 61 is opened, and the steam pressurized water tank 61 is boosted to the operating pressure.
  • the outlet valve 652 of the last steam pressurized water tank 61 is opened, and the water stored in the steam pressurized water tank 61 is output from the drain line 64 to the core assembly 20, the passive containment cooling system 30, the secondary side passive cooling system 40, and the steam generation. water to the device 50, and/or the sprinkler system 70.
  • Step 3 The steam pressurized water tank 61 is refilled with water. After the steam pressurized water tank 61 is emptied, the interior is filled with high pressure steam. It is isolated from other steam pressurized water tanks 61, and the exhaust line 614 corresponding to each water chamber 613 is opened to relieve pressure. Since the steam pressurized water tank is installed at the ground level, the water level of the demineralized water tank in the factory is relatively high. There are generally water tanks on the mountains of the factory area, and the location is higher. Therefore, after the steam pressurized water tank 61 is completely depressurized, the water replenishment valve 631 can be opened to replenish water by gravity. After the water replenishment is completed, close the water replenishment valve, and then it can be put back into the steam pressurized water tank 61, or placed in a standby state.
  • the penetration of the containment 10 can be reduced, the possible routes of radioactive release in the event of an accident can be reduced, and the potential risk of radioactive release to the public can be reduced; the size of the pool can also be reduced, and the steam pressurized water tank 61 can be charged when it is put into operation. water;
  • the steam pressurized water tank 61 After being put into operation, it has the characteristics of long-term passive operation.
  • the steam pressurized water tank 61 is refilled with water, and no external energy is needed to be put into operation again, and it can be passively operated for a long time.
  • the remaining high-level water tanks cannot be passively refilled because the installation elevation is too high;
  • the water tank group can be assembled on site after the modular construction of the factory, which does not occupy the key construction path and reduces the construction time of the containment;
  • the operation mode of the water tank group is flexible.
  • a set of steam pressurized water tank 61 is installed for the two units. During operation, according to the specific circumstances of the accident, water can be supplied to one unit or divided into two units to jointly supply water to realize the common use of the two units. , and further reduce the cost of nuclear power plants.

Abstract

核电厂非能动专设安全系统及供水系统(60)，用于核电厂非能动专设安全系统的供水系统(60)，包括至少一个蒸汽加压水箱(61)、蒸汽加压管线(62)、补水管线(63)以及排水管线(64)；蒸汽加压管线(62)与蒸汽加压水箱(61)和核电厂非能动专设安全系统中的蒸汽发生器(50)和/或外置的蒸汽系统连接；补水管线(63)与蒸汽加压水箱(61)和外部水源连接；排水管线(64)与蒸汽加压水箱(61)连接，并与非能动安全壳冷却系统(30)、二次侧非能动冷却系统(40)、喷淋系统(70)和/或堆芯组件(20)连接。该供水系统(60)可在能动专设安全系统失效的情况下，及时和迅速对反应堆一回路和堆芯进行有效冷却，使核电站顺利进入安全的冷停堆状态，抑制或缓解反应堆严重事故后果，降低事故危害，提高核电厂的安全性。

Description

核电厂非能动专设安全系统及供水系统 技术领域
本发明涉及核电领域，更具体地说，涉及一种核电厂非能动专设安全系统及供水系统。
 背景技术
专设安全系统的主要作用是减轻事故所造成的后果。例如，在发生一回路失水、二回路蒸汽/给水管道破裂、蒸汽发生器传热管破裂、失电和低压熔堆等事故时，相应的专设安全系统启动，限制和缓解事故后果，确保核安全功能：
1) 反应性控制：即能终止链式裂变反应；
2) 堆芯余热导出：无论反应堆状态如何，均能导出堆芯热量；
3) 放射性产物包容：放射源的辐射及其防护。
以AP1000为代表的第三代核电机组，通常采用钢制安全壳及安全壳顶部水箱的结构，以及二次侧非能动冷却系统，通过钢壁安全壳或换热器，可实现对安全壳大气、以及二回路的非能动冷却。但该设计在第二代核电机组上应用难度较大，改造困难，成本较高。
AP1000设有安全壳冷却系统（PCS) ，其主要作用是在导致安全壳压力和温度升高的设计基准事故下，导出安全壳热量，降低安全壳压力和温度。
中核的华龙一号新增安全壳高位水箱（内存水约3000吨）和浸泡在水箱内的非能动安全壳热量导出系统（PCS) ，二次侧非能动余热排出系统（PRS），堆腔注水冷却系统等非能动安全系统，这些系统通过闭路管道实现能量从蒸汽发生器50或安全壳大气向高位水箱的转移。但这些系统有大量管道在安全壳标高较高的位置，力学分析，管道防甩及埋件设计复杂，给建筑施工和设备安装带来了不小的麻烦。
中广核的华龙一号同样新增安全壳高位水箱（内存水3100吨）和浸泡在水箱内的二次侧非能动余热排出系统（PRS），没有设计非能动安全壳热量导出系统，该部分功能由（EHR）安全壳热量导出系统的两台泵和热交换器实现。堆坑注水功能由EHR 系统水泵实现能动注水，由安全壳内设置的堆坑注水箱实现非能动注水。
相关技术中，诸如《一种核电站非能动专设安全系统》CN201110037783.7
该发明公开一种核电厂非能动专设安全系统，该系统包括二次侧非能动余热排出热交换器、蒸汽冷凝水箱、非能动堆腔注水系统、非能动高压堆芯补水箱和相关的阀门与管道。在核电站发生设计基准事故或超设计基准事故时，通过有步骤的投入一系列的非能动与能动的安全设施，及时和迅速对反应堆一回路和堆芯进行有效冷却，使核电站顺利进入安全的冷停堆状态，抑制或缓解反应堆严重事故后果，降低事故危害，提高核电站的安全性。再诸如《一种核电站的非能动专设安全设施》CN201610297360.1该发明提供一种核电站的非能动专设安全设施，其包括：排放管线；热交换器；扩散器；快速卸压阀和注射总管。该发明提供的核电站非能动专设安全设施，与传统核电站的专设安全设施不同，非能动专设安全设施的接管集中设置在压力容器上，通过非能动专设安全设施直接对堆芯进行冷却和注水，增大了自然循环能力，使安全保护系统更加安全可靠。 
 技术问题
上文列举的相关技术虽然都能及时和迅速对反应堆一回路和堆芯进行有效冷却，使核电站顺利进入安全的冷停堆状态，抑制或缓解反应堆严重事故后果，降低事故危害，提高核电站的安全性，但是在非能动安全壳冷却系统，二次侧非能动冷却系统，安注系统和/或安全壳喷淋系统失效情况下，则无法继续对对反应堆一回路和堆芯进行有效冷却。 
 技术解决方案
本发明要解决的技术问题在于，提供一种改进的核电厂非能动专设安全系统及供水系统。
本发明解决其技术问题所采用的技术方案是：构造一种用于核电厂非能动专设安全系统的供水系统，与所述核电厂非能动专设安全系统中的非能动安全壳冷却系统、二次侧非能动冷却系统、喷淋系统和/或堆芯组件连接，包括至少一个蒸汽加压水箱、蒸汽加压管线、补水管线以及排水管线；
所述蒸汽加压管线与所述蒸汽加压水箱和所述核电厂非能动专设安全系统中的蒸汽发生器和/或外置的蒸汽系统连接；
所述补水管线与所述蒸汽加压水箱和外部水源连接；
所述排水管线与所述蒸汽加压水箱连接，并与所述非能动安全壳冷却系统、二次侧非能动冷却系统、喷淋系统和/或堆芯组件连接。
优选地，所述蒸汽加压水箱包括箱体、以及设置于所述箱体中将所述箱体中的空间分隔为多个水室的多个隔板。
优选地，所述箱体为卧式箱体，多个所述隔板沿所述箱体的长度方向间隔设置。
优选地，所述箱体包括底壁、以及与所述底壁相对设置的顶壁；
所述底壁上设有朝所述顶壁延伸的多个所述隔板；
所述顶壁上设有朝所述底壁延伸的多个所述隔板；
所述顶壁上的多个所述隔板和所述底壁上的多个所述隔板交错设置使多个水室相互连通。
优选地，每个所述水室上设有排气管线，所述排气管线上设有排气阀。
优选地，所述蒸汽加压水箱为多个，多个所述蒸汽加压水箱依次连接设置；
所述供水系统还包括设置于相邻设置的两个所述蒸汽加压水箱之间以连接相邻设置的两个所述蒸汽加压水箱的串联管线；所述串联管线上设有连通或隔离相邻设置的两个蒸汽加压水箱的串联阀；
所述串联管线与所述排水管线连接；所述串联管线与所述排水管线相接的一端设有出口阀。
优选地，所述补水管线为多个，多个所述补水管线与多个所述蒸汽加压水箱一一对应连接。
优选地，所述蒸汽加压管线上设有蒸汽加压阀。
优选地，所述补水管线上设有补水阀。
本发明还构造一种核电厂非能动专设安全系统，包括非能动安全壳冷却系统、二次侧非能动冷却系统、堆芯组件、蒸汽发生器、喷淋系统以及本发明所述的用于核电厂非能动专设安全系统的供水系统；
所述非能动安全壳冷却系统与所述堆芯组件相对设置；
所述堆芯组件与所述蒸汽发生器连接；
所述二次侧非能动冷却系统与所述蒸汽发生器和/或非能动安全壳冷却系统连接；
所述供水系统的蒸汽加压管线与所述蒸汽发生器连接，所述供水系统的排水管线与所述非能动安全壳冷却系统、二次侧非能动冷却系统、喷淋系统和/或堆芯组件连接。
 有益效果
实施本发明的核电厂非能动专设安全系统及供水系统，具有以下有益效果：该供水系统通过设置至少一个蒸汽加压水箱，并通过将与蒸汽加压水箱连接的蒸汽加压管线与核电厂非能动专设安全系统中的蒸汽发生器连接，将排水管线与该蒸汽加压水箱连接，并与该非能动安全壳冷却系统、二次侧非能动冷却系统和/或堆芯组件连接，从而可作为备用手段，在能动专设安全系统失效的情况下，对非能动安全壳冷却系统、二次侧非能动冷却系统和/或堆芯组件进行供水，及时和迅速对反应堆一回路和堆芯进行有效冷却，使核电站顺利进入安全的冷停堆状态，抑制或缓解反应堆严重事故后果，降低事故危害，提高核电厂的安全性。 
 附图说明
下面将结合附图及实施例对本发明作进一步说明，附图中：
图1是本发明一些实施例中核电厂非能动专设安全系统的结构示意图。
 本发明的最佳实施方式
为了对本发明的技术特征、目的和效果有更加清楚的理解，现对照附图详细说明本发明的具体实施方式。
图1示出了本发明核电厂非能动专设安全系统的一些优选实施例。该核电厂非能动专设安全系统在反应堆发生事故后，能动专设安全系统失效的情况下，作为其备用的非能动专设安全系统，建立堆芯冷却能力，保证放射性包容，限制和缓解事故后果，确保核安全。同时可以取代现有三代核电机组安全壳高位水箱，降低安全壳荷载，提高安全壳安全性。
如图1所示，在一些实施例中，该核电厂非能动专设安全系统可包括安全壳10、堆芯组件20、非能动安全壳冷却系统30、二次侧非能动冷却系统40、蒸汽发生器50、喷淋系统70以及供水系统60。该安全壳10可用于收容堆芯组件20、非能动安全壳冷却系统30、蒸汽发生器50。该堆芯组件20可设置于该安装壳10中，并可与该蒸汽发生器40连接。该非能动安全壳冷却系统30可设置于该安装壳10的上部空间，且与该堆芯组件20相对设置，可用于对该堆芯组件20进行冷却。该二次侧非能动冷却系统40可设置于该安全壳10的上部，可与该蒸汽发生器40和该非能动安全冷却系统30连接。在一些实施例中，该二次侧非能动冷却系统40可以为两组，其中一组可与该蒸汽发生器40连接，另一组可与该非能动安全冷却系统30连接。在一些实施例中，该蒸汽发生器50可与该堆芯组件20和该蒸汽发生器40连接。在一些实施例中，该喷淋系统70可设置于该安全壳10的上部空间，可与该堆芯组件20相对设置，可通过喷淋对堆芯组件20进行冷却。在一些实施例中，该供水系统可与该非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70以及堆芯组件20连接，可向该非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70以及该堆芯组件20进行供水。当然，可以理解地，在其他一些实施例中，也可只与该非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70或者堆芯组件20连接。
进一步地，在一些实施例中，堆芯组件20可设置于该安全壳10的下部，可包括压力容器21，该压力容器21可以为核燃料反应容器。该压力容器21可置于堆坑中，该压力容器21的冷却剂输入端可与低压安注系统23连接，该堆坑可与堆坑注水系统22连接。该压力容器21的冷却剂输出端可与蒸汽发生器50连接。
进一步地，在一些实施例中，该非能动安全壳冷却系统30可包括螺旋盘管，该螺旋盘管可设置于该安全壳10的穹顶区域，且可与该二次侧非能动冷却系统40连接，具体地，在一些实施例中，该螺旋盘管可与该二次侧非能动冷却系统40的换热器42连接。
进一步地，在一些实施例中，该二次侧非能动冷却系统40可包括水箱41、以及设置于该水箱41中的换热器42。该水箱41可与该供水系统60连接，可由该供水系统60给该水箱41进行供水。该换热器42可设置于该水箱41中，可与水箱41中的水体进行热交换。在一些实施例中，其中一组的二次侧非能动冷却系统40的换热器42的出口端可与该非能动安全壳冷却系统30的入口端连接，其入口端可与该非能动安全壳冷却系统30的出口端连接，可将冷却后的水体输送至该非能动安全壳冷却系统，并对接收该非能动安全壳冷却系统30对安全壳10进行冷却后形成的高温水体，另一组的二次侧非能动冷却系统40的换热器42的入口端可与该蒸汽发生器50的蒸汽出口连接，其出口端可与该供水系统60连接，可对该蒸汽发生器50输出的蒸汽进行冷却，并将冷却后形成水体输送至该供水系统60，形成循环利用。
进一步地，在一些实施例中，该蒸汽发生器50可以为3台，当然，可以理解地，在其他一些实施例中，该蒸汽发生器50可不限于3台。该3台蒸汽发生器50的蒸汽出口管线51可相互连接。每台蒸汽发生器50可包括壳体以及设置于该壳体中的换热管。该壳体的入口端可与该供水系统60连接，该供水系统60可向该壳体的入口端输送水体。该壳体的蒸汽出口端可连接蒸汽出口管线51，该蒸汽出口管线51可与蒸汽输出管线53连接，以将蒸汽输送至汽轮机，以推动汽轮机做功。在一些实施例中，该蒸汽出口管线51上可设置排压管线52，该排压管线52上可设置大气排放阀521，该大气排放阀521打开，可给该蒸汽出口管线51及时排压。该蒸汽输出管线53上可与该蒸汽加压母管54的一端连接，该蒸汽加压母管54的另一端可与该供水系统60连接，以输送蒸汽至该供水系统60，以给该供水系统60进行加压，使得供水系统60输出水体。在一些实施例中，该蒸汽加压母管54上可设置主蒸汽隔离阀541，该主蒸汽隔离阀541打开，可向该供水系统60输送蒸汽。
进一步地，在一些实施例中，喷淋系统70可设置于该非能动安全壳冷却系统30的下方，可位于该堆芯组件20的上方，可向堆芯组件20进行喷淋，以冷却堆芯组件20。在一些实施例中，该喷淋系统70可与该供水系统60连接，可由该供水系统60对其进行供水。
进一步地，在一些实施例中，该供水系统60可包括至少一个蒸汽加压水箱61、蒸汽加压管线62、补水管线63以及排水管线64。该蒸汽加压水箱61可接入该蒸汽发生器50产生的蒸汽，通过蒸汽进行加压，驱动置于该蒸汽加压水箱61中的水体输送出。该蒸汽加压管线62可与该蒸汽加压水箱61和该蒸汽发生器50连接，具体地，在一些实施例中，该蒸汽加压管线62可该蒸汽加压母管54和该蒸汽加压水箱61的加压蒸汽入口连接。该补水管线63可与该蒸汽加压水箱61和外部水源，可及时给该蒸汽加压水箱61及时补水。在一些实施例中，该排水管线64可与该蒸汽加压水箱61连接，且可与该非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70以及堆芯组件20连接。当然，可以理解地，在其他一些实施例中，该排水管线64也可只与非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70或者堆芯组件20连接。
进一步地，在一些实施例中，该蒸汽加压水箱61可包括箱体611、多个隔板612。该箱体611可以为卧式箱体，该多个隔板612可设置于该箱体611中，且可沿该箱体611的长度方向间隔设置，并可与该箱体611的底壁呈设定夹角设置，以进行导流，以及将该箱体611中的空间分隔为多个水室613。具体地，在一些实施例中，该箱体611可包括底壁以及与该底壁相对设置的顶壁。该底壁上设有多个隔板612，该顶壁上也设有多个隔板612，该底壁上的多个隔板612可朝该顶壁延伸设置，可与该底壁垂直设置，以形成垂直导流设计，该顶壁上的多个隔板612可朝该底壁延伸设置，且可与该顶壁垂直设置，以形成垂直导流设计。该隔板612的高度可小于该箱体611的高度，该顶壁上的多个隔板612和该低壁上的多个隔板612可交错设置，使得该多个水室613相互连通，以引导蒸汽从一个水室613下端进入另一个水室的上端，其中，垂直导流设计的好处是避免热蒸汽与冷水过多接触，减少蒸汽消耗。利用水的温度越高密度越小的特性，使蒸汽或热水始终处于冷水的上方，从而限制蒸汽与冷水的接触面积，减少蒸汽消耗、降低水温上升。在一些实施例中，该箱体611的左端水室613上部可设置加压蒸汽入口，该加压蒸汽入口可与蒸汽加压管线62连接，该箱体611的右端水室613的下部可设置排水口，该排水口可与该排水管线64连接。在一些实施例中，每个水室613上可设置排气管线614，该排气管线614可用于将每个水室613中的蒸汽排出。在一些实施例中，该排气管线614上可设置排气阀6141，该排气阀6141打开，可使得水室613中的蒸汽从该排气管线614排出。当箱体611排空后，可开启该排气阀6141，排出箱体611的高压蒸汽，对水箱进行卸压。
进一步地，在一些实施例中，该蒸汽加压管线62可与该蒸汽加压水箱61一一对应设置，可连接于该蒸汽加压水箱61水室613上部的加压蒸汽入口，从而可使得高压蒸汽可从每一水室613的上部进入，将水向下压，从排水管线64注入至非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70以及堆芯组件20，也可以经过串联管线65进入下一级蒸汽加压水箱61。在一些实施例中，该蒸汽加压管线62上可设置旁路阀621，该旁路阀621开启，可使得蒸汽加压母管54中的蒸汽输出至蒸汽加压管线62，并输入至蒸汽加压水箱61。在一些实施例中，该蒸汽加压管线62还可与外置的蒸汽系统连接。该外置的蒸汽系统可以为SVA辅助蒸汽系统以及相邻机组主蒸汽系统。该蒸汽加压管线62可选择该核电厂非能动专设安全系统的蒸汽发生器50进行供气，也可选择外置的蒸汽系统进行供气。其中，当采用蒸汽发生器50进行供气时，可打开大气排放阀521将蒸汽压力降至15bar.G，SVA辅助蒸汽供气时，不减压。
进一步地，在一些实施例中，该补水管线63可与该蒸汽加压水箱61一一对应设置，当然，可以理解地，在其他一些实施例中，该补水管线63可不限于与该蒸汽加压水箱61一一对应设置。该补水管线63的一端可与该箱体611左端的水室613下部的入水口连接，另一端可与外部水源连接。具体地，在一些实施例中，该补水管线63的一端可与该山顶高位水箱和/或厂内除盐水箱连接，从而可及时向该蒸汽加压水箱61进行补水。在一些实施例中，该补水管线61上可设置补水阀631，该补水阀631开启，该补水管线63可向该蒸汽加压水箱61进行供水。由于蒸汽加压水箱61安装于地面高度，厂内除盐水箱水位较高，厂区山上一般都有水箱，而且位置更高。所以，可以在蒸汽加压水箱61彻底卸压后，可开启补水阀631利用重力补水。补水完毕后，关闭补水阀631，即可将其重新投运蒸汽加压水箱61，或置于备用状态。
进一步地，在一些实施例中，该排水管线64的一端可与该蒸汽加压水箱61右端的水室下部的水体出口连接，该排水管线64上可设置多个分支管路，分别与非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70以及堆芯组件20连接。在一些实施例中，该排水管线64上可设置排水阀641，该排水阀641打开，可向非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70以及堆芯组件20排水。在一些实施例中，该排水管线64的分支管路上也可对应设置有排水阀641。
进一步地，在一些实施例中，该蒸汽加压水箱61可以为多个，该多个蒸汽加压水箱61可依次连接设置，形成一个多级水箱组。具体地，在一些实施例中，该蒸汽加压水箱61可以为四个，当然，可以理解地，在其他一些实施例中，该蒸汽加压水箱61可不限于四个，可以为一个或者大于四个。进一步地，在一些实施例中，该供水系统还包括串联管线65。该串联管线65可设置于相邻设置的两个蒸汽加压水箱61之间，可用于连接相邻设置的两个蒸汽加压水箱61，从而可使得相邻设置的两个蒸汽加压水箱61连通。在一些实施例中，该串联管线65上可设置串联阀651，该串联阀651可用于连通或者隔离相邻设置的两个蒸汽加压水箱61，该串联阀651开启，可使得该多个蒸汽加压水箱61形成一个多级水箱，该串联阀651关闭，每个蒸汽加压水箱61均为独立的水箱。在一些实施例中，该串联管线65还可与该排水管线64连接，在一些实施例中，该串联管线65与该排水管线64相接的一端可设置出口阀652。该出口阀652开启可使得该串联管线65与该排水管线64连通。通过该串联阀651和该出口阀652，可实现对蒸汽加压水箱串联运行，也可实现蒸汽加压水箱的切除/隔离和投运。根据蒸汽加压水箱61的存水情况，利用蒸汽加压水箱61的出口阀652和串联阀651可以实现对蒸汽加压水箱61独立运行或并联运行，也可以实现排空蒸汽加压水箱61或缺水蒸汽加压水箱61的切除/隔离。
该核电厂非能动专设安全系统，通过非能动的方式，利用外置的蒸汽系统和/或蒸汽发生器产生的高温高压蒸汽，将蒸汽加压水箱61中的水注入至非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70和堆芯组件20。该核电厂非能动专设安全系统的投运可包括三个步骤，分别为蒸汽发生器分离减压、蒸汽加压水箱61加压向用户供水、蒸汽加压水箱再充水。具体操作为：
1、蒸汽发生器分离减压。蒸汽发生器50分离指实施主蒸汽隔离，关闭3台蒸汽发生器50的主蒸汽隔离阀541。并打开大气排放阀521将蒸汽压力降至15bar.G。通过SVA辅助蒸汽供气时，不减压；
2、蒸汽加压水箱61加压向非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70和堆芯组件20供水。系统投运时，将蒸汽加压水箱61的蒸汽加压阀621开启，蒸汽加压水箱61升压至运行压力。再将蒸汽加压水箱61的出口阀652开启，蒸汽加压水箱61存水从排水管线64输出向非能动安全壳冷却系统30、二次侧非能动冷却系统40、喷淋系统70和堆芯组件20供水；
3、蒸汽加压水箱61再充水。蒸汽加压水箱61排空后，内部充满高压蒸汽。将排空是蒸汽加压水箱61与其他蒸汽加压水箱61隔离，开启每一水室613对应的排气管线614卸压，再打开补水阀631给对应的蒸汽加压水箱61进行补水。
根据事故控制策略的需要，非能动专设安全系统有“安注模式”、“安全壳喷淋模式”、“安全壳冷却模式”、“二次侧补水模式”、“二次侧非能动冷却模式”和“堆坑注水模式”等六种运行模式，具体如下：
（1）安注模式
在发生一回路破口事故后，如果安注系统已启动，则一回路水装量会得以恢复。如果安注系统由于设备或外部灾害等原因失效，可以采本发明的供水系统60向堆芯组件20注水。发明的供水系统60投运后，水箱出口水温约30℃，压力15bar.G或12bar.G，其压头与低压安注泵出口压头相同，出口水温与换料水箱水温接近，因此可以作为一列低压安注使用。
（2）安全壳喷淋模式
在发生一回路破口事故后，如果安全壳喷淋系统已启动，则安全壳压力会降低。如果安全壳喷淋系统由于设备或外部灾害等原因失效，可以采本发明的供水系统60向安全壳进行喷淋。发明的供水系统60投运后，水箱出口水温约30℃，压力15bar.G或12bar.G，其压头与安全壳喷淋泵出口压头相同，出口水温与换料水箱水温接近，因此可以作为一列安全壳喷淋使用。
（3）安全壳冷却模式
对于安装有安全壳非能动冷却系统的电厂，设计上可以取消安全壳高位水箱，仅保留换热器42和浸泡该换热器42的水箱41，当需要投入安全壳非能动冷却系统时，通过蒸汽加压水箱61或能动水泵向浸泡该换热器42的水箱41注水，从而减少安全壳荷载。
（4）二次侧补水模式
发生失去全部给水事故时，对于未安装二次侧非能动冷却系统的核电厂，非能动专设系统可作为机组失去全部给水事故的缓解手段，在“充-排模式”投入之前，使用蒸汽加压水箱61代替主给水系统（ARE）或辅助给水系统（ASG）给SG补水，将一回路后撤至余热排出系统连接状态，从而避免“充-排模式”的投入。
（5）二次侧非能动冷却模式
发生失去全部给水事故时，对于安装二次侧非能动冷却系统的核电厂，可以在保留换热器42和浸泡该换热器42的水箱41，可更换体积较小的水箱41至维持数小时运行，当二次侧非能动冷却系统投运时，由蒸汽加压水箱61提供持续补水，或直接取代二次侧非能动冷却系统。
（6）堆坑注水模式当电站发生严重事故（堆芯出口温度达到650℃）时，堆腔注水系统（RPF）大流量（大于360m3/h）阶段能够在半个小时内将堆腔充满水（堆腔高度为-3.5m～7.7m，空间体积为约180m3），然后转入小流量（约40m3/h）补水阶段，以补偿蒸发损失，此阶段持续约24小时，当消防水分配系统（JPD）无法供水或不能提供足够水量时，考虑在系统上增加临时注水接口，从蒸汽加压水箱61取水，注入堆腔。
在出现以下事故时，通过采用本发明核电厂非能动专设安全系统可缓解反应堆事故后果，具体如下：
1、一回路破口事故
一回路破口事故发生后，安注系统和喷淋系统根据一回路的温度压力以及安全壳10压力等参数自动启动，则一回路的水装量得以恢复，安全壳10压力也会下降。对于安装有安全壳10非能动冷却系统的电厂，当安全壳10压力和温度升高时，安全壳10上设置的位水箱，通过钢壁安全壳10或换热器，可实现对安全壳10大气进行冷却。如果安注系统的设备故障或由于外部灾害无法运行时，则一回路水装量无法恢复，会导致堆芯的裸露。如果安全壳10喷淋的设备故障或由于外部灾害无法运行时，则反应堆第三道屏障有破裂风险，放射性外泄风险增大。
本发明所述的非能动专设安全系统运行操作简单，不依靠外部资源（如水源、电源），能够在事故后快速投入运行，缓解事故后果。因此，投运非能动专设安全系统应作为“一回路破口事故”后对安注系统和安全壳10中喷淋系统70的有效后备。
对于安装有安全壳10非能动冷却系统的电厂，采用本发明后设计上可以取消安全壳10高位水箱，仅保留换热器41和浸泡换热器41的水箱42，当需要投入安全壳非能动冷却系统时，通过蒸汽加压水箱61或能动水泵向浸泡换热器41的水箱42注水，从而减少安全壳10荷载。
2、失去全部给水事故
在“失去全部给水”事故后，按照现有事故处理策略，将使用“充-排模式”维持堆芯冷却并后撤。该策略的实施分两步：1、等待；2、开启稳压器泄压管线，启动安注；3、投运安全壳10喷淋，通过安全壳10喷淋系统（EAS）冷却器将热量传至设备冷却水系统（RRI），再由重要厂用水系统（SEC）将热量传至大海。该策略可以有效的将机组带至余热排出系统相连的状态，但对机组也存在较大的伤害。实施“充-排模式”操作后，机组可能面临长期停运进行系统设备维修，甚至直接退役的后果。
对于未安装二次侧非能动冷却系统的核电厂，本发明所述的非能动专设系统可作为机组失去全部给水事故的缓解手段，在“充-排模式”投入之前，使用本发明所述非能动专设安全系统建立蒸汽发生器50给水，将一回路后撤至余热排出系统连接状态，从而避免“充-排模式”的投入。对于已安装二次侧非能动冷却系统的核电厂，可以在保留换热器和浸泡换热器的水箱，缩小水箱体积至维持数小时运行，当二次侧非能动冷却系统投运时，由蒸汽加压水箱提供持续补水，或直接取代二次侧非能动冷却系统。
本发明所述的非能动专设安全系统运行操作简单，不依靠外部资源（如水源、电源），能够在事故后快速投入运行，缓解事故后果。因此，对于未安装二次侧非能动冷却系统的核电厂，投运非能专设安全系统应作为“失去全部给水事故”后的首选应对措施。对于已安装二次侧非能动冷却系统的核电厂，可以在保留换热器42和浸泡换热器42的水箱41，更换体积较小的水箱至维持数小时运行，当二次侧非能动冷却系统投运时，由蒸汽加压水箱61提供持续补水。
3、严重事故
在电站发生严重事故，堆芯熔融物落入反应堆压力容器（RPV）21下封头时，向堆腔内注水进行压力容器21外部冷却，并与其他安全功能（如一回路卸压等）同时作用以保持RPV完整性，从而将堆芯熔融碎片滞留于压力容器21中，防止大多数可能威胁安全壳10完整性的堆外现象（安全壳10直接加热、蒸汽爆炸、熔融物-混凝土反应等）。
配置了堆腔注水系统（RPF）的核电厂，RPF大流量阶段能够在半个小时内将堆腔充满水，然后转入小流量补水阶段，以补偿蒸发损失，此阶段持续约24小时，当消防水分配系统（JPD）无法供水或不能提供足够水量时，可在系统上增加临时注水接口，从本发明的蒸汽加压水箱61取水，注入堆腔。
再如图1所示，以在安装了安全壳高位的水箱41的三代机组配置有4个蒸汽加压水箱60的非能动专设安全系统发生一回路破口事故为实施例。
水源
冷却堆芯需要足够的水源作为冷却介质。安全壳10降温降压需要足够的水源作为喷淋水源。本实施案例采用厂内除盐水作为冷却水源。
注水动力
事故后蒸汽发生器50产生的主蒸汽仍有高温高压的能量，经大气排放阀521减压后可作为注水动力，驱动蒸汽加压水箱61的低压水注入需要冷却水的系统。
注水条件与注水通道
蒸汽发生器50隔离之后，需尽快打通注水通道，开启相关系统与蒸汽加压水箱61直接连接的排放阀641。
4、系统投运
按照技术方案中的3个步骤投运该系统。
第1步：蒸汽发生器分离减压。实施主蒸汽隔离，关闭3台蒸汽发生器50的主蒸汽隔离阀。并经减压阀将蒸汽压力降至15bar.G。通过SVA辅助蒸汽供气时，不减压。
第2步：蒸汽加压水箱61加压向堆芯组件20、非能动安全壳冷却系统30、二次侧非能动冷却系统40、蒸汽发生器50、和/或喷淋系统70供水。供水系统投运时，第一蒸汽加压水箱61的蒸汽加压阀621开启，蒸汽加压水箱61升压至运行压力。最后一个蒸汽加压水箱61的出口阀652开启，蒸汽加压水箱61存水从排水管线64输出向堆芯组件20、非能动安全壳冷却系统30、二次侧非能动冷却系统40、蒸汽发生器50、和/或喷淋系统70供水。
第3步：蒸汽加压水箱61再充水。蒸汽加压水箱61排空后，内部充满高压蒸汽。将其与其他蒸汽加压水箱61隔离，开启每一水室613对应的排气管线614进行卸压。由于蒸汽加压水箱安装于地面高度，厂内除盐水箱水位较高，厂区山上一般都有水箱，而且位置更高。所以可以在蒸汽加压水箱61彻底卸压后，开启补水阀631利用重力补水。补水完毕后，关闭补水阀，即可将其重新投入蒸汽加压水箱61，或置于备用状态。
5、一回路破口事故处理
按照技术方案中的3个步骤投运该系统。
第1步：蒸汽发生器分离减压。实施主蒸汽隔离，关闭3台蒸汽发生器50的主蒸汽隔离阀。并经减压阀将蒸汽压力降至15bar.G。通过SVA辅助蒸汽供气时，不减压。
第2步：蒸汽加压水箱61加压向堆芯组件20、非能动安全壳冷却系统30、二次侧非能动冷却系统40、蒸汽发生器50、和/或喷淋系统70供水。供水系统投运时，第一蒸汽加压水箱61的蒸汽加压阀621开启，蒸汽加压水箱61升压至运行压力。最后一个蒸汽加压水箱61的出口阀652开启，蒸汽加压水箱61存水从排水管线64输出向堆芯组件20、非能动安全壳冷却系统30、二次侧非能动冷却系统40、蒸汽发生器50、和/或喷淋系统70供水。
第3步：蒸汽加压水箱61再充水。蒸汽加压水箱61排空后，内部充满高压蒸汽。将其与其他蒸汽加压水箱61隔离，开启每一水室613对应的排气管线614进行卸压。由于蒸汽加压水箱安装于地面高度，厂内除盐水箱水位较高，厂区山上一般都有水箱，而且位置更高。所以可以在蒸汽加压水箱61彻底卸压后，开启补水阀631利用重力补水。补水完毕后，关闭补水阀，即可将其重新投入蒸汽加压水箱61，或置于备用状态。
该核电厂非能动专设安全系统的有益效果如下：
1、无需在安全壳10上部安装超大型水箱，降低安全壳10荷载，提高安全壳安全性；
2、可作为所有低压注入和安全壳喷淋专设安全系统的后备手段，提高核电厂安全性；
3、优化“失去全部给水”事故处理策略，避免机组进入“充排模式”造成机组长时间大修甚至退役的严重后果。
4、作为堆腔注水的后备水源，可以防止大多数可能威胁安全壳完整性的堆外现象，增加了堆腔冷却时间。
5、对于三代堆安全壳，可以减少安全壳10的贯穿件，减少事故情况下放射性释放可能途径，降低对公众潜在放射性释放风险；也可以缩小水池规模，投运时由蒸汽加压水箱61充水；
6、投入运行后，具有长期非能动运行特性，蒸汽加压水箱61再充水，再投运均无需利用外接能源，可长期非能动运行。其余高位水箱由于安装标高太高，无法实现非能动再充水；
7、与安全壳高位水箱相比，水箱组可在工厂模块化建造完毕后现场组装，不占用施工关键路径，减少安全壳施工时间；
8、水箱组运行方式灵活，双机组安装一套蒸汽加压水箱61，运行时根据事故具体情况，既可以全部向一台机组供水，可也分为向两台机组共同供水，实现双机组公用，进一步降低核电厂造价。
可以理解的，以上实施例仅表达了本发明的优选实施方式，其描述较为具体和详细，但并不能因此而理解为对本发明专利范围的限制；应当指出的是，对于本领域的普通技术人员来说，在不脱离本发明构思的前提下，可以对上述技术特点进行自由组合，还可以做出若干变形和改进，这些都属于本发明的保护范围；因此，凡跟本发明权利要求范围所做的等同变换与修饰，均应属于本发明权利要求的涵盖范围。

Claims (10)

  1. 一种用于核电厂非能动专设安全系统的供水系统，与所述核电厂非能动专设安全系统中的非能动安全壳冷却系统（30）、二次侧非能动冷却系统（40）、喷淋系统（70）和/或堆芯组件（20）连接，其特征在于，包括至少一个蒸汽加压水箱（61）、蒸汽加压管线（62）、补水管线（63）以及排水管线（64）；
    所述蒸汽加压管线（62）与所述蒸汽加压水箱（61）和所述核电厂非能动专设安全系统中的蒸汽发生器（40）和/或外置的蒸汽系统连接；
    所述补水管线（63）与所述蒸汽加压水箱（61）和外部水源连接；
    所述排水管线（64）与所述蒸汽加压水箱（61）连接，并与所述非能动安全壳冷却系统（30）、二次侧非能动冷却系统（40）、喷淋系统（70）和/或堆芯组件（20）连接。
  2. 根据权利要求1所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述蒸汽加压水箱（61）包括箱体（611）、以及设置于所述箱体（611）中将所述箱体（611）中的空间分隔为多个水室（613）的多个隔板（612）。
  3. 根据权利要求2所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述箱体（611）为卧式箱体，多个所述隔板（612）沿所述箱体（611）的长度方向间隔设置。
  4. 根据权利要求3所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述箱体（611）包括底壁、以及与所述底壁相对设置的顶壁；
    所述底壁上设有朝所述顶壁延伸的多个所述隔板（612）；
    所述顶壁上设有朝所述底壁延伸的多个所述隔板（612）；
    所述顶壁上的多个所述隔板（612）和所述底壁上的多个所述隔板（612）交错设置使多个水室（613）相互连通。
  5. 根据权利要求2所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，每个所述水室（613）上设有排气管线（614），所述排气管线（614）上设有排气阀（6141）。
  6. 根据权利要求1所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述蒸汽加压水箱（61）为多个，多个所述蒸汽加压水箱（61）依次连接设置；
    所述供水系统还包括设置于相邻设置的两个所述蒸汽加压水箱（61）之间以连接相邻设置的两个所述蒸汽加压水箱（61）的串联管线（65）；所述串联管线（65）上设有连通或隔离相邻设置的两个蒸汽加压水箱（61）的串联阀（651）；
    所述串联管线（65）与所述排水管线（64）连接；所述串联管线（65）与所述排水管线（64）相接的一端设有出口阀（652）。
  7. 根据权利要求6所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述补水管线（63）为多个，多个所述补水管线（63）与多个所述蒸汽加压水箱（61）一一对应连接。
  8. 根据权利要求1所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述蒸汽加压管线（62）上设有蒸汽加压阀（621）。
  9. 根据权利要求1所述的用于核电厂非能动专设安全系统的供水系统，其特征在于，所述补水管线（63）上设有补水阀（631）。
  10.  一种核电厂非能动专设安全系统，其特征在于，包括非能动安全壳冷却系统（30）、二次侧非能动冷却系统（40）、堆芯组件（20）、蒸汽发生器（40）、喷淋系统（70）以及权利要求1至9任一项所述的用于核电厂非能动专设安全系统的供水系统（60）；
    所述非能动安全壳冷却系统（30）与所述堆芯组件（20）相对设置；
    所述堆芯组件（20）与所述蒸汽发生器（40）连接；
    所述二次侧非能动冷却系统（40）与所述蒸汽发生器（40）和/或非能动安全壳冷却系统（30）连接；
    所述供水系统（60）的蒸汽加压管线（62）与所述蒸汽发生器（40）连接，所述供水系统（60）的排水管线（64）与所述非能动安全壳冷却系统（30）、二次侧非能动冷却系统（40）、喷淋系统（70）和/或堆芯组件（20）连接。
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