WO2016015474A1 - 非能动混凝土安全壳冷却系统 - Google Patents

非能动混凝土安全壳冷却系统 Download PDF

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Publication number
WO2016015474A1
WO2016015474A1 PCT/CN2015/074662 CN2015074662W WO2016015474A1 WO 2016015474 A1 WO2016015474 A1 WO 2016015474A1 CN 2015074662 W CN2015074662 W CN 2015074662W WO 2016015474 A1 WO2016015474 A1 WO 2016015474A1
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WIPO (PCT)
Prior art keywords
containment
heat exchanger
cooling
wall
cooling system
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PCT/CN2015/074662
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English (en)
French (fr)
Inventor
曹建华
卢向晖
李冬生
孙吉良
Original Assignee
中科华核电技术研究院有限公司
中国广核集团有限公司
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Application filed by 中科华核电技术研究院有限公司, 中国广核集团有限公司 filed Critical 中科华核电技术研究院有限公司
Priority to GB1600197.6A priority Critical patent/GB2531190B/en
Publication of WO2016015474A1 publication Critical patent/WO2016015474A1/zh

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/093—Concrete vessels
    • 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
    • G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
    • 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 plant reactor safety equipment, in particular to a passive cooling system suitable for concrete containment.
  • nuclear power is a major breakthrough in the history of energy use.
  • nuclear fission reactions nuclear power plants can produce high-energy output that is unmatched by all other traditional fossil energy sources, and these high-energy outputs often require only a small amount of nuclear fuel.
  • This low-input and high-output characteristics has made humans pay more and more attention to the use of nuclear energy and continuously increase research and development in the field of nuclear energy.
  • nuclear energy has become an important energy component of many countries in the world.
  • nuclear power has a very high utilization value, and it may also cause great harm.
  • a major accident such as a nuclear leak occurs due to improper protection, it will affect the environment around the nuclear power plant and even the whole civilization. Bringing extremely serious nuclear pollution disasters.
  • the containment In active PWR nuclear power plants, the containment is an important safety facility for the reactor and the last barrier to prevent the release of radioactive products into the atmosphere.
  • the primary circuit means that the cooling water discharges the thermal energy of the nuclear fuel out of the reactor pressure vessel and enters the steam generator, passing thousands of heat transfer tubes to transfer the heat to the secondary circuit water outside the pipe. The water is boiled to generate steam; the cooling water flows through the steam generator, and then is sent to the reactor pressure vessel by the main pump, so that it circulates back and forth.
  • the cooling water in the reactor pressure vessel becomes less. Therefore, the temperature of the reactor pressure vessel will rise rapidly. If the cooling of the reactor pressure vessel is not performed in time, the heat of the reactor pressure vessel may be led out. The temperature and pressure of the containment are increased, resulting in a more serious safety accident. Therefore, it is necessary to provide further safety protection for the containment.
  • the existing containment is widely used in concrete structures. Since the concrete itself has poor thermal conductivity and thick wall thickness, it is impossible to rely on the concrete containment itself to quickly and efficiently discharge the heat inside the shell to the atmosphere after the accident. in. To this end, some nuclear power plants have set up active cooling facilities to achieve the discharge of residual heat in the containment, but the operation of these active systems relies on external power, in the event of a full-field power outage Such a situation can lead to serious consequences.
  • the technical proposal of the present invention is to provide a passive concrete containment cooling system suitable for deriving heat in a containment, the passive concrete containment cooling system including a heat exchange loop system and condensation a water recovery system, the heat exchange loop system sealingly penetrating the containment to direct heat within the containment out of the containment, the condensate recovery system being disposed within the containment and communicating with the Reactor pits inside the containment.
  • the condensed water recovery system includes a first condensate collector disposed on an inner wall surface of the containment, the first condensate collector being higher than a reactor pit in the containment and connected The reactor pit.
  • the high-energy steam released from the first circuit of the reactor and the high-energy steam generated by the cooling water in the reactor pit are released into the containment.
  • Some of the steam is condensed on the inner wall of the containment and then collected by the first condensed water.
  • the device collects and then returns to the reactor pit.
  • the passive reactor reactor is filled with water for a long period of time, and the safety shell can be realized without external AC power and water source. The natural circulation inside.
  • the first condensate collector is connected to the reactor pit through a first valve.
  • the first condensate collector has a channel structure and a side wall thereof abuts against an inner wall surface of the containment.
  • the heat exchange circuit system includes an internal heat exchanger disposed in the containment
  • the condensate recovery system further includes a second condensate collector disposed in the containment
  • the A second condensate collector is located below the inner heat exchanger and above the reactor sump within the containment, and the second condensate collector is in communication with the reactor sump.
  • the second condensate collector Collected by the second condensate collector, Then, it flows back to the reactor pit, and the collection and reflux measures of the first and second condensate collectors are matched to realize the water injection of the passive reactor cavity in a long period of time, without the need of external AC power source and water source. Natural circulation inside the containment.
  • the second condensate collector is connected to the reactor pit through a second valve.
  • the second condensate collector has a V-shaped structure.
  • the heat exchange circuit system further includes an outer heat exchanger, an ascending pipe, a descending pipe and a cooling medium
  • the outer heat exchanger is accommodated in a condensing pool outside the safety shell, the internal heat exchange
  • the position of the device is lower than the position of the condensing pool, the rising pipe sealingly penetrating through the containment and communicating with the outlet of the inner heat exchanger and the inlet of the outer heat exchanger, the descending pipe sealingly penetrating
  • the containment vessel communicates with an outlet of the outer heat exchanger and an inlet of the inner heat exchanger, the cooling medium being in the inner heat exchanger, the ascending conduit, the outer heat exchanger, the Flow in the circulation channel formed by the descending pipe.
  • the descending pipe is provided with a third valve, and the third valve is located outside the safety casing.
  • the passive concrete containment cooling system further comprises a water tank, the water tank is disposed at the top of the safety shell, and the water tank is divided into mutually connected water cooling descending passages, air cooling descending passages and rising passages And the air cooling descending channel and the rising channel respectively communicate with the atmospheric space, the heat exchange circuit system sealingly penetrates the safety shell and a part is accommodated in the rising channel, and another part of the heat exchange circuit system Located in the containment.
  • the setting of the water tank can realize the rapid discharge of a large amount of residual heat in the safety shell at the beginning of the accident.
  • the portion of the loop heat transfer system located in the water tank is exposed to the air, the air is heated, and then rises along the ascending passage to form a natural convection of the organized air, thereby eventually forming the containment.
  • the heat is transferred to the atmosphere, so even if the cooling water is evaporated, the containment can be cooled by air for a long time.
  • the heat exchange loop system includes an outer heat exchanger, and the outer heat exchanger is housed in the ascending passage.
  • the water tank has a bottom wall and an inner wall and an outer wall connected to and spaced apart from the bottom wall, and the inner wall, the outer wall and the bottom wall together define a receiving space.
  • a first partition and a second partition are vertically disposed in the receiving space of the water tank, and the lower end of the first partition and the second partition and the bottom wall Between each having a gap between the first partition and the second partition, the first partition and the inner wall The water cooling descending passage is formed therebetween, and the air cooling descending passage is formed between the second partition and the outer wall.
  • the water tank further has a top plate, the inner wall and the upper end of the first partition plate are connected to the top plate, and an upper end of the second partition plate and the top plate are provided with an opening.
  • the ascending passage communicates with the atmospheric space through the opening.
  • the air cooling descending channel communicates with the gap between the outer wall and the top plate to communicate with the air space.
  • the air cooling descending channel communicates with the gap between the outer wall and the top plate to communicate with the air space.
  • the water tank is divided into a plurality of mutually independent pools, and each of the pools is provided with the water cooling descending passage, the air cooling descending passage and the rising passage, and each of the pools corresponds to A heat exchange loop system is provided.
  • Multiple sets of independent pools and heat exchange loop systems are set up, and the work of each group of heat exchange loop systems can be independent of each other. Even if part of the failure occurs, other parts can still work effectively and achieve high system reliability.
  • the passive concrete containment cooling system further includes a high level pool disposed in the containment, the high level pool being located above the reactor pit within the containment and communicating with the reactor pit.
  • a fourth valve is disposed between the high level pool and the reactor pit. When the accident occurs, the fourth valve is opened, and the cooling water in the high level pool is automatically injected into the reactor pit, and the first stage of large-flow water injection is performed to realize rapid injection of the reactor pit and flooding of the pressure vessel, thereby performing external pressure vessel Cooling, the passive natural circulation inside the containment can realize the passive water injection inside the containment without any external AC power and water source.
  • the passive concrete containment cooling system of the present invention including the heat exchange loop system and the condensate recovery system
  • the heat exchange loop system sealingly penetrates the containment to guide the heat inside the containment out of the containment
  • the condensate recovery system is located in the containment and communicates with the reactor pits in the containment.
  • the heat exchange loop system is exported to the final heat sink of the atmospheric environment to cool the pressure vessel, prevent the pressure vessel from being penetrated and the containment overpressure, and eliminate the release of large-scale radioactive materials; the condensate recovery system is recovered in the heat exchange loop
  • the condensed water generated by the condensation of the system or / and the inner wall of the containment is automatically injected into the reactor pit to realize the injection of water into the passive reactor stack in a long period of time; the invention can realize the accident without relying on external AC power and other power.
  • the derivation of residual heat in the containment and the passive water injection in the containment improve the safety of the nuclear power plant, especially the protection capability under the over-design conditions such as full-field power failure and complete loss of cooling chain.
  • Figure 1 is a schematic view showing the structure of an embodiment of a passive concrete containment cooling system of the present invention.
  • Figure 2 is a schematic view showing the flow direction of the cooling water and the cooling medium of Figure 1.
  • Figure 3 is a cross-sectional view showing another embodiment of the passive concrete containment cooling system of the present invention.
  • Figure 4 is an enlarged schematic view of the water cooling mode of Figure 3.
  • Figure 5 is an enlarged schematic view of the hollow cooling mode of Figure 3.
  • Figure 6 is a schematic view of the third partition in the water tank of Figure 3.
  • the passive concrete containment cooling system 100 of the present invention is suitable for deriving heat within the containment vessel 110.
  • the containment 110 has a top portion 111, and a reactor stack 112 and a pressure vessel 113 accommodated in the reactor pit 112 are disposed in the containment vessel 110.
  • the high level pool 114 is located above the reactor pile 112, and the high level pool 114 is connected to the reactor pile 112 through a pipeline.
  • the high level pool 114 has cooling water therein; the high level pool 114 is higher than the reactor pile 112 to ensure that it occurs.
  • the water in the high level pool 114 can be automatically injected into the reactor pit 112 to achieve rapid flooding of the reactor pressure vessel 113, thereby cooling the outside of the pressure vessel 113, eliminating the use of water pumping to achieve passive water injection and preventing accidents.
  • the power is turned off and the water cannot be injected, the safety is improved.
  • the passive concrete containment cooling system 100 includes a condensate recovery system 120 and a heat exchange loop system 130.
  • the heat exchange loop system 130 sealingly penetrates the containment 110 to discharge heat inside the containment 110 out of the containment vessel 110.
  • the condensate recovery system 120 is disposed in the containment vessel 110 and communicates with the reactor stack 112.
  • the condensate recovery system 120 recovers the condensed water produced by the heat exchange circuit system 130 or/and the inner wall of the containment vessel 110 and injects it into the reactor pit 112.
  • a condensate pool 140 is further disposed outside the containment vessel 110.
  • the heat exchange loop system 130 includes an inner heat exchanger 131, an ascending conduit 132, an outer heat exchanger 133, a descending conduit 134, and a cooling medium.
  • the inner heat exchanger 131 is disposed in the containment vessel 110. The position of the inner heat exchanger 131 is lower than the position of the condensate pool 140 disposed outside the containment vessel 110.
  • the outer heat exchanger 133 is housed in the condensing pool 140, and the condensing pool 140 With cooling water therein, the outer heat exchanger 133 is completely submerged in the cooling water; the rising duct 132 sealingly penetrates the containment 110 and communicates with the outlet of the inner heat exchanger 131 and the inlet of the outer heat exchanger 133, The descending duct 134 sealingly penetrates the safety envelope 110 and communicates with the outlet of the outer heat exchanger 133 and the inlet of the inner heat exchanger 131; the cooling medium is in the inner heat exchanger 131, the rising duct 132, and the outer heat exchange The 133 and the descending conduit 134 flow in a circulation passage formed by the conduit 134. When an accident occurs, the heat in the reactor pit 112 is carried to the outer heat exchanger 133 by the circulation of the cooling medium in the circulation passage and finally to the final heat trap of the atmospheric environment without any external AC power source and water source. .
  • the inlet of the inner heat exchanger 131 is at the lower end
  • the outlet of the inner heat exchanger 131 is at the upper end
  • the inlet of the outer heat exchanger 133 is at the upper end
  • the outlet of the outer heat exchanger 133 is at the lower end.
  • the cooling medium in the internal heat exchanger 131 absorbs heat
  • the outlet of the inner heat exchanger 131, the riser pipe 132 enters the outer heat exchanger 133 outside the containment vessel 110, and condenses heat in the outer heat exchanger 133, and the heat released continuously heats the cooling water in the condensate tank 140 to secure the containment vessel.
  • the heat in 110 is led to the final heat trap of the atmospheric environment; after the heat medium is condensed by heat in the outer heat exchanger 133, it is returned to the inside of the containment 110 through the outlet of the outer heat exchanger 133 and the descending pipe 134 under the action of gravity.
  • a closed circuit is formed, which does not depend on external power The source can realize the waste heat release in the containment 110 under the accident.
  • the condensed water recovery system 120 includes a first condensed water collector 121 and a second condensed water collector 123 .
  • the first condensed water collector 121 is disposed on an inner wall surface of the containment 110 . And the position of the first condensate collector 121 is higher than the position of the reactor hopper 112, and the first condensate collector 121 communicates with the reactor hopper 112 through the first valve 122.
  • the second condensate collector 123 is disposed within the containment vessel 110, and the second condensate trap 123 is located below the inner heat exchanger 131 and above the reactor stack 112, ie, the second condensate collector 123 is at a height
  • the direction is located between the inner heat exchanger 131 and the reactor pit 112, and the second condensate collector 123 communicates with the reactor pit 112 through the second valve 124.
  • the collecting and recirculating measures of the first condensed water collector 121 and the second condensed water collector 123 cooperate with the high level pool 114 to realize the injection of the passive reactor pit 112 in a long period of time without using an external AC power source and water source.
  • a natural circulation inside the containment vessel 110 can be achieved.
  • the first condensed water collector 121 is disposed along the inner wall surface of the containment 110, and preferably has a groove-shaped structure, one side wall of which is in close contact with the inner wall surface of the safety shell 110, the first condensation
  • the bottom wall of the water collector 121 is connected to the reactor pit 112 through a pipe, and the pipe is provided with a first valve 122.
  • the side wall of the first condensate collector 121 is in close contact with the inner wall surface of the containment vessel 110, so that it is more convenient and efficient to collect the condensed water formed by condensation on the inner wall surface of the containment vessel 110.
  • the second condensate collector 123 has a V-shaped structure, and the bottom of the second condensate collector 123 communicates with the reactor hopper 112 through a second valve 124; that is, the second condensate collector 123 has two sides
  • the wall has two side walls which are inclined, the bottom connection of the two side walls is connected to the reactor pit 112 through a pipeline, and the second valve 124 is arranged on the pipeline, and the V-shaped structure enables the collected condensed water to be quickly
  • the reactor pit 112 is injected into the ground.
  • the third valve 135 is disposed on the descending pipe 134. In the embodiment, the third valve 135 is located outside the safety casing 110.
  • the pipeline between the high water tank 114 and the reactor pit 112 is further disposed.
  • the fourth valve 115 is further disposed.
  • the operator opens the first condensate collector 121, the second condensate collector 123, the first valve 122, the second valve 124 on the pipeline connecting the reactor hopper 112, and manually opens the downcomer 134.
  • the third valve 135 simultaneously opens the fourth valve 115 on the injection line of the high level pool 114.
  • the cooling water in the high level pool 114 is automatically injected into the reactor pit 112 due to the pressure difference, and the first stage large-flow water injection is performed to realize rapid injection of the reactor pile 112 and rapid flooding of the pressure vessel 113;
  • the pressure vessel 113 heats the cooling water in the reactor pit 112.
  • the high-energy steam generated by the heating of the cooling water in the reactor pit 112 and the high-energy steam generated by the break of the first circuit of the reactor are released into the containment vessel 110, and some of the steam is condensed on the inner wall of the containment vessel 110 and collected by the first condensed water collector 121.
  • the backflow measures cooperate to achieve water injection into the passive reactor stack 112 over a longer period of time without the need for any external AC power and water source to achieve natural circulation within the containment 110.
  • the outer heat exchanger 133 in the condensing water tank 140 passes through the outlet of the inner heat exchanger 131 and the rising pipe 132, and is condensed and released in the outer heat exchanger 133 to release the heat.
  • the heat continuously heats the cooling water in the external condensing tank 140 to conduct the heat in the containment 110 to the final heat trap of the atmospheric environment; after the cooling medium is condensed by heat, the outlet of the outer heat exchanger 133 is lowered by gravity.
  • the conduit 134 returns to the inner heat exchanger 131 within the containment vessel 110 to form a closed loop. Therefore, independent of the AC power source, the waste heat of the concrete containment vessel 110 under the accident is derived, and the safety of the power plant is improved, especially the protection capability under the over-design conditions such as full-field power failure and complete loss of the cooling chain.
  • a second embodiment of the passive concrete containment cooling system 100 will now be described with reference to FIGS. 3-6.
  • the difference between this embodiment and the first embodiment is that it does not have a condensing pool 140.
  • the water tank 150 is included. Since the position and structure of the water tank 150 are different from those of the condensing pool 140, the position of the heat exchange loop system 130 in this embodiment is slightly different from that of the above embodiment. The difference is described.
  • the water tank 150 is disposed above the top portion 111 of the containment vessel 110, and the water tank 150 is partitioned into mutually connected water-cooling descending passages 157, rising passages 158, and air-cooling descending passages 159.
  • the ascending channel 158 and the air-cooling descending channel 159 respectively communicate with the atmospheric space, so that the pressure of the water tank 150 is the atmospheric environment pressure, and the related voltage stabilization system is not needed, so that the system structure is simplified.
  • the structure of the heat exchange loop system 130 is the same as that of the first embodiment described above, but in the present embodiment, the outer heat exchanger 133 is housed in the ascending passage 158 of the water tank 150, and the riser pipe 132 is sealingly penetrated through the safety.
  • the top portion 111 of the shell 110 communicates with the outlet of the inner heat exchanger 131 and the inlet of the outer heat exchanger 133.
  • the descending duct 134 sealingly penetrates the top portion 111 of the containment vessel 110 and communicates with the outlet and internal heat exchange of the outer heat exchanger 133.
  • the entrance of the device 131 is the same as that of the first embodiment described above, but in the present embodiment, the outer heat exchanger 133 is housed in the ascending passage 158 of the water tank 150, and the riser pipe 132 is sealingly penetrated through the safety.
  • the top portion 111 of the shell 110 communicates with the outlet of the inner heat exchanger 131 and the inlet of the outer heat exchanger 133.
  • the water tank 150 includes an inner wall 151, an outer wall 152, and a top plate 153.
  • the inner wall 151 and the outer wall 152 are spaced apart, and the upper end of the inner wall 151 is fixedly coupled to the top plate 153, and the upper end of the outer wall 152 is connected to the top plate.
  • the pressure of the water tank 150 at the top of the containment vessel 110 is the atmospheric environment pressure, and the relevant voltage stabilization system is not required, so that the system structure is simplified.
  • the water tank 150 further includes a first partition 154 and a second partition 155.
  • the first partition 154 and the second partition 155 are vertically and spaced apart from the water tank.
  • the first partition 154 and the second partition 155 are disposed at intervals along the circumferential direction of the water tank 150, and the lower ends of the first partition 154 and the second partition 155 are disposed at intervals.
  • the first partition plate 154 and the second partition plate are separated from each other.
  • the rising passage 158 is formed between the plates 155, the water-cooling descending passage 157 is formed between the first partition 154 and the inner wall 151, and the air-cooling descending passage 159 is formed between the second partition 155 and the outer wall 152, that is, along the edge In the direction from the inner wall 151 to the outer wall 152, a water-cooling descending passage 157, an ascending passage 158, and an air-cooling descending passage 159 are sequentially formed.
  • the ascending passage 158 communicates with the atmospheric space through the opening 158a
  • the air-cooling descending passage 159 communicates with the atmospheric space through the gap between the outer wall 152 and the top plate 153.
  • the outer heat exchanger 113 is disposed in the passage of the ascending passage 158 and is accommodated in the cooling water, so that the heat exchange loop system 130 is a closed structure. When any one end is damaged, the other end is still intact, so that it does not lead. Through the containment 110, the radioactive material in the containment 110 is not released to the external atmosphere.
  • a plurality of sets of heat exchange loop systems 130 may be provided. Specifically, the plurality of sets of heat exchange loop systems 130 are disposed along the circumference of the water tank 150, each of which is disposed at intervals The outer heat exchangers 133 of the group heat exchange loop system 130 are disposed in the ascending passage 158 and are accommodated in the cooling water.
  • the water tank 150 can also be divided into a plurality of mutually independent pools 150' (see FIG. 6), and each pool 150' is correspondingly installed with a group of heat exchange loop systems 130, and multiple groups are set.
  • the independent pool 150', the heat exchange loop system 130, and the heat exchange loop system 130 of each group work independently of each other. Even if part of the heat exchange loop system 130 fails, other parts can still work effectively, achieving high system reliability.
  • the water tank 150 further includes a third partition 156, the third partition 156 is radially disposed, and the third partition 156 is connected between the inner wall 151 and the outer wall 152 so as to be
  • the water tank 150 is partitioned into a plurality of independent pools 150', and each of the pools 150' is provided with a first partition 154 and a second partition 155, wherein the two sides of the first partition 154 are respectively connected to two phases.
  • the adjacent third partition 156 has an upper end connected to the top plate 153, and two sides of the second partition 155 are respectively connected to two adjacent third partitions 156, and the upper end of the second partition 155 and the top plate 153
  • An opening 158a for the rising passage 158 to pass through the atmospheric space is formed, and the opening 158a may be formed by a gap between the upper end of the second partition 155 and the top plate 153, or a through hole may be directly formed at the upper end of the second partition 155. Formed and not limited to this.
  • the gap between the outer wall 152 and the top plate 153 is a passage for the air cooling descending passage 159 to communicate with the air space.
  • a through hole may be formed in the outer wall 152.
  • the air cooling down channel 159 is connected to the atmospheric space, but is not limited thereto.
  • the structure of the condensed water recovery system 120 is the same as that of the first embodiment described above, and will not be described again.
  • the water in the inner heat exchanger 131 is heated and evaporated, and enters the outer heat exchanger 133 in the water tank 150 along the riser pipe 132, and then condensation heat transfer occurs, and the condensed water returns to the containment vessel 110 along the downcomer pipe 134.
  • the inner heat exchanger 131 forms a natural circulation; the heat transferred from the outer heat exchanger 133 heats the cooling water in the water tank 150/sink 150', and after a certain time, the cooling water in the water tank 150/sink 150' boils, steam It rises along the ascending channel 158 and is released to the atmosphere by the opening 158a, while the cooling water in the tank 150/sink 150' flows through the water-cooling down channel 157 to the ascending channel 158, as indicated by the direction of the arrow in FIG.
  • the outer heat exchanger 133 is exposed to the air, the surrounding air is heated, and the heated air rises along the ascending passage 158 and is released by the opening 158a.
  • the 110 performs long-term cooling and can cope with the cooling problem of the containment 110 under severe accident conditions such as a water loss accident condition.
  • the heat exchange loop system 130 sealingly penetrates the containment vessel 110 to conduct heat within the containment vessel 110 Outside the containment vessel 110, a condensate recovery system 120 is disposed within the containment vessel 110 and communicates with the reactor stack 112 within the containment vessel.
  • the high-energy steam is led to the final heat sink of the atmospheric environment via the heat exchange loop system 130, thereby achieving cooling of the pressure vessel 113, preventing the pressure vessel 113 from passing through and the overpressure of the containment vessel 110, thereby eliminating large-scale radioactivity.
  • the condensate recovery system 120 recovers the condensed water generated by condensation at the inner wall of the heat exchange circuit system 130 or/and the containment vessel 110 and automatically injects into the reactor pit 112 to realize the passive reactor stack for a long period of time. Pile pit water injection.
  • the invention can realize the derivation of the residual heat in the containment 110 and the passive water injection in the safety shell without relying on the external AC power source and the like, thereby improving the safety of the nuclear power plant, especially improving the power failure in the whole field and completely losing the cooling chain. Protection capability under design conditions.

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  • Engineering & Computer Science (AREA)
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Abstract

一种非能动混凝土安全壳冷却系统（100），包括换热回路系统（130）及冷凝水回收系统（120），所述换热回路系统（130）密封地贯穿安全壳（110）以将所述安全壳（110）内的热量导出所述安全壳（110）外，所述冷凝水回收系统（120）设于所述安全壳（110）内并连通反应堆堆坑（112）。事故时产生的高能蒸汽经换热回路系统导出至大气环境最终热阱，冷凝水回收系统回收在换热回路系统或/和安全壳内壁处冷凝产生的冷凝水后自动注入反应堆堆坑，实现较长时间段内的非能动反应堆堆坑注水，从而不依赖外部交流电源等动力便可实现事故下安全壳内余热的导出功能，提高核电站的安全性，尤其提高在全场断电以及完全丧失冷却链等超设计工况下的防护能力。

Description

非能动混凝土安全壳冷却系统 技术领域
本发明涉及核电站反应堆安全设备领域，尤其涉及一种适用于混凝土安全壳的非能动冷却系统。
背景技术
核电的使用是人类在能源利用史上的一个重大突破，利用原子核的裂变反应，核电厂能够产生其他所有传统化石能源所无法比拟的高能量输出，并且这些高能量输出往往只需要耗费少量的核燃料，这种低投入高产出的特性，使得人类日益重视对核能的利用，并不断加大在核能领域的研究开发，时至今日，核能已成为世界上许多国家的重要能源组成部分。然而，核电具有极高利用价值的同时，也可能带来很大的危害，在使用核电的过程中，如果保护不当而致使出现核泄漏等重大事故，将会对核电厂周边的环境乃至全人类带来极其严重的核污染灾害。
现役的压水堆核电站，安全壳是反应堆重要的安全设施，是防止放射性产物释放到大气环境中的最后一道屏障。在压水堆核电站中，一回路是指冷却水把核燃料放出的热能带出反应堆压力容器，并进入蒸汽发生器，通过数以千计的传热管，把热量传给管外的二回路水，使水沸腾产生蒸汽；冷却水流经蒸汽发生器后，再由主泵送入反应堆压力容器，这样来回循环。当反应堆一回路发生大破口失水的安全事故时，反应堆压力容器内的冷却水变少，因此，反应堆压力容器的温度会迅速上升，若不及时冷却并将反应堆压力容器的热量导出，可能使安全壳的温度及压力升高，从而引致更严重的安全事故，因此，需要对安全壳设置进一步的安全保障。
现有的安全壳广泛采用混凝土结构，由于混凝土本身的导热性能很差，且壁厚较厚，因此在事故后，不可能依靠混凝土安全壳本身来将壳内的热量迅速有效地排出至大气环境中。为此，一些核电站设置了能动的冷却设施来实现安全壳内余热的排出，但这些能动系统的运行依赖外部动力，一旦发生全场断电 等情况就会导致严重后果。
因此，有必要提供一种不依赖于外部动力就能实现事故下安全壳内余热快速导出的非能动冷却系统，以解决上述现有技术的不足。
发明内容
本发明的目的在于提供一种不依赖于外部动力就能实现事故下安全壳内余热快速导出的非能动混凝土安全壳冷却系统。
为实现上述目的，本发明的技术方案为：提供一种非能动混凝土安全壳冷却系统，适用于对安全壳内的热量进行导出，所述非能动混凝土安全壳冷却系统包括换热回路系统及冷凝水回收系统，所述换热回路系统密封地贯穿所述安全壳以将所述安全壳内的热量导出所述安全壳外，所述冷凝水回收系统设于所述安全壳内并连通所述安全壳内的反应堆堆坑。
较佳地，所述冷凝水回收系统包括设于所述安全壳的内壁面上的第一冷凝水收集器，所述第一冷凝水收集器高于所述安全壳内的反应堆堆坑并连通所述反应堆堆坑。当事故发生时，反应堆一回路破口释放的高能蒸汽、反应堆堆坑内的冷却水经加热产生的高能蒸汽均释放到安全壳内，部分蒸汽在安全壳的内壁面冷凝后由第一冷凝水收集器收集，然后回流至反应堆堆坑，通过第一冷凝水收集器的收集回流措施，实现较长时间段内的非能动反应堆堆腔注水，不需借助外部的交流电源和水源即可实现安全壳内的自然循环。
较佳地，所述第一冷凝水收集器通过第一阀门连通所述反应堆堆坑。
较佳地，所述第一冷凝水收集器呈槽形结构且其一侧壁紧贴于所述安全壳的内壁面。
较佳地，所述换热回路系统包括设于所述安全壳内的内换热器，所述冷凝水回收系统还包括设于所述安全壳内的第二冷凝水收集器，所述第二冷凝水收集器位于所述内换热器的下方并高于所述安全壳内的反应堆堆坑，且所述第二冷凝水收集器连通所述反应堆堆坑。当事故发生时，反应堆一回路破口释放的高能蒸汽、反应堆堆坑内的冷却水经加热产生的高能蒸汽均释放到安全壳内，大部分蒸汽在换热回路系统的内换热器壁面凝结后由第二冷凝水收集器收集， 然后流回至反应堆堆坑，通过第一、第二冷凝水收集器的收集回流措施相配合，实现较长时间段内非能动反应堆堆腔注水，不需借助外部的交流电源和水源即可实现安全壳内的自然循环。
较佳地，所述第二冷凝水收集器通过第二阀门连通所述反应堆堆坑。
较佳地，所述第二冷凝水收集器呈V型结构。
较佳地，所述换热回路系统还包括外换热器、上升管道、下降管道及冷却介质，所述外换热器容置于所述安全壳外的冷凝水池内，所述内换热器的位置低于所述冷凝水池的位置，所述上升管道密封地贯穿所述安全壳并连通所述内换热器的出口及所述外换热器的入口，所述下降管道密封地贯穿所述安全壳并连通所述外换热器的出口及所述内换热器的入口，所述冷却介质在所述内换热器、所述上升管道、所述外换热器、所述下降管道形成的循环通道内流动。
较佳地，所述下降管道上设有第三阀门，所述第三阀门位于所述安全壳外。
较佳地，所述非能动混凝土安全壳冷却系统还包括水箱，所述水箱设置于所述安全壳的顶部，且所述水箱内被分隔成相互连通的水冷下降通道、空冷下降通道及上升通道，且所述空冷下降通道、所述上升通道分别连通大气空间，所述换热回路系统密封地贯穿所述安全壳且一部分容置于所述上升通道内，所述换热回路系统的另一部分位于所述安全壳内。水箱的设置可实现事故初期安全壳内大量余热的快速排出。而当水箱内的水蒸发完毕后，回路传热系统的位于水箱内的部分暴露于空气中，空气被加热，然后沿着上升通道上升，形成有组织的空气自然对流，从而最终将安全壳内的热量导出至大气环境，因此即便是冷却水蒸干条件下，仍可利用空气冷却的方式对安全壳进行长期冷却。
较佳地，所述换热回路系统包括外换热器，所述外换热器容置于所述上升通道内。
较佳地，所述水箱具有底壁及与所述底壁相连接且相间隔的内壁、外壁，所述内壁、所述外壁、所述底壁共同围成一容纳空间。
较佳地，所述水箱的容纳空间内竖直地设置有相间隔的第一隔板及第二隔板，且所述第一隔板、所述第二隔板的下端与所述底壁之间均具有间隙，所述第一隔板与所述第二隔板之间形成所述上升通道，所述第一隔板与所述内壁之 间形成所述水冷下降通道，所述第二隔板与所述外壁之间形成所述空冷下降通道。
较佳地，所述水箱还具有一顶板，所述内壁、所述第一隔板的上端均连接于所述顶板，所述第二隔板的上端与所述顶板之间具有设置有开口，所述上升通道通过所述开口连通大气空间。
较佳地，所述外壁与所述顶板之间具有间隙，所述空冷下降通道连通所述外壁与所述顶板之间的间隙连通大气空间。当水箱内的水蒸发完毕以后，外换热器暴露于空气中，因此上升通道内的空气被加热后沿着上升通道上升，大气环境中的空气通过空冷下降通道进入上升通道内，形成有组织的空气自然对流，从而最终依靠空气冷却将安全壳内余热排出到大气环境，即使水池蒸干条件下，也可利用空气冷却的方式对安全壳进行长期冷却。
较佳地，所述水箱被分隔成多个相互独立的水池，每一所述水池内均设置有所述水冷下降通道、所述空冷下降通道及所述上升通道，且每一所述水池对应设置一所述换热回路系统。设置多组独立的水池、换热回路系统，各组换热回路系统的工作可相互独立，即使部分失效，其它部分仍然可以有效工作，实现较高的系统可靠性。
较佳地，所述非能动混凝土安全壳冷却系统还包括设于所述安全壳内的高位水池，所述高位水池位于所述安全壳内的反应堆堆坑的上方并连通所述反应堆堆坑，所述高位水池与所述反应堆堆坑之间设有第四阀门。事故发生时，打开第四阀门，高位水池内的冷却水自动注入反应堆堆坑，进行第一阶段的大流量注水，以实现反应堆堆坑的快速注入和压力容器的淹没，从而对压力容器外部进行冷却，实现安全壳内部的非能动自然循环，不需借助任何外部的交流电源和水源即可实现安全壳内部的非能动注水。
与现有技术相比，由于本发明的非能动混凝土安全壳冷却系统，包括换热回路系统及冷凝水回收系统，换热回路系统密封地贯穿安全壳以将安全壳内的热量导出安全壳外，冷凝水回收系统设于安全壳内并连通安全壳内的反应堆堆坑。当反应堆一回路发生安全事故时，反应堆堆坑内的冷却水被加热产生的高能蒸汽及反应堆一回路破口释放的高能蒸汽均释放到安全壳的内部，高能蒸汽 经换热回路系统导出至大气环境最终热阱，实现对压力容器的冷却，防止压力容器熔穿及安全壳超压，达到消除大规模放射性物质释放的目的；冷凝水回收系统回收在换热回路系统或/和安全壳内壁处冷凝产生的冷凝水后自动注入反应堆堆坑，实现较长时间段内的非能动反应堆堆堆坑注水；本发明不依赖于外部交流电源等动力便可实现事故下安全壳内余热的导出及安全壳内的非能动注水，提高核电站的安全性，尤其提高在全场断电以及完全丧失冷却链等超设计工况下的防护能力。
附图说明
图1是本发明非能动混凝土安全壳冷却系统一实施例的结构示意图。
图2是图1中冷却水及冷却介质的流向示意图。
图3是本发明非能动混凝土安全壳冷却系统另一实施例的剖视图。
图4是图3中水冷模式的的放大示意图。
图5是图3中空冷模式的的放大示意图。
图6是图3中水箱内第三隔板的示意图。
具体实施方式
现在参考附图描述本发明的实施例，附图中类似的元件标号代表类似的元件。
如图1、图3所示，本发明所提供的非能动混凝土安全壳冷却系统100，其适用于对安全壳110内的热量进行导出。其中，所述安全壳110具有一顶部111，安全壳110内设有反应堆堆坑112及容置于所述反应堆堆坑112内的压力容器113；所述安全壳111内还设有高位水池114，高位水池114位于所述反应堆堆坑112的上方，且高位水池114通过一管路连通反应堆堆坑112，高位水池114内具有冷却水；高位水池114高于反应堆堆坑112是为了保证在发生紧急事故时，高位水池114内的水能自动注入反应堆堆坑112，实现对反应堆压力容器113的快速淹没，从而对压力容器113外部进行冷却，免去使用水泵抽水，实现非能动注水，防止事故时因断电而无法注水的情况出现，提高安全性。
所述非能动混凝土安全壳冷却系统100包括冷凝水回收系统120及换热回路系统130。所述换热回路系统130密封地贯穿安全壳110以将安全壳110内的热量导出安全壳110外，所述冷凝水回收系统120设于所述安全壳110内并连通反应堆堆坑112，所述冷凝水回收系统120回收换热回路系统130或/和安全壳110的内壁产生的冷凝水并将其注入所述反应堆堆坑112。
下面结合附图所示，对本发明非能动混凝土安全壳冷却系统100的不同实施例分别进行说明。
如图1所示，所述非能动混凝土安全壳冷却系统100的第一实施例中，安全壳110外还设有冷凝水池140。其中，所述换热回路系统130包括内换热器131、上升管道132、外换热器133、下降管道134及冷却介质。内换热器131设于安全壳110内，内换热器131的位置低于设于安全壳110外的冷凝水池140的位置，外换热器133容置于冷凝水池140内，冷凝水池140中具有冷却水，外换热器133完全淹没于冷却水中；所述上升管道132密封地贯穿所述安全壳110并连通所述内换热器131的出口及外换热器133的入口，所述下降管道134密封地贯穿所述安全壳110并连通外换热器133的出口及内换热器131的入口；所述冷却介质在所述内换热器131、上升管道132、外换热器133、下降管道134形成的循环通道内流动。当事故发生时，通过冷却介质在循环通道内的循环，将反应堆堆坑112内的热量带到外换热器133并最终导出至大气环境最终热阱，不需借助任何外部的交流电源和水源。
继续参阅图1所示，所述内换热器131的入口位于下端，内换热器131的出口位于上端；所述外换热器133的入口位于上端，外换热器133的出口位于下端。事故发生时，由反应堆一回路破口释放的高能蒸汽及反应堆堆坑112内的冷却水被加热产生的高能蒸汽均释放于安全壳110内，内换热器131中的冷却介质吸收热量后，经内换热器131的出口、上升管道132进入安全壳110外的外换热器133，在外换热器133中放热冷凝，放出的热量持续加热冷凝水池140中的冷却水而将安全壳110内的热量导出至大气环境最终热阱；冷却介质在外换热器133中放热冷凝后，在重力作用下经外换热器133的出口、下降管道134回到安全壳110内部的内换热器131中，形成闭式回路，不依赖于外部动力 源便可实现事故下安全壳110内的余热导出。
再次参阅图1所示，所述冷凝水回收系统120包括第一冷凝水收集器121及第二冷凝水收集器123，第一冷凝水收集器121设于所述安全壳110的内壁面上，且第一冷凝水收集器121的位置高于反应堆堆坑112的位置，第一冷凝水收集器121通过第一阀门122连通所述反应堆堆坑112。第二冷凝水收集器123设于安全壳110内，且第二冷凝水收集器123位于内换热器131的下方并高于所述反应堆堆坑112，即第二冷凝水收集器123在高度方向上位于内换热器131与反应堆堆坑112之间，第二冷凝水收集器123通过第二阀门124连通所述反应堆堆坑112。当事故发生时，反应堆一回路破口释放的高能蒸汽、反应堆堆坑112内的冷却水被加热产生的高能蒸汽均释放到安全壳110内，部分蒸汽在安全壳110的内壁面冷凝后由第一冷凝水收集器121收集，然后回流至反应堆堆坑112，大部分蒸汽则在内换热器131的壁面凝结后由第二冷凝水收集器123收集，然后流回至反应堆堆坑112，通过第一冷凝水收集器121、第二冷凝水收集器123的收集回流措施与高位水池114相配合，实现较长时间段内非能动反应堆堆坑112注水，不需借助外部的交流电源和水源即可实现安全壳110内部的自然循环。
具体地，所述第一冷凝水收集器121沿安全壳110的内壁面设置，且其优选呈槽形结构，其一侧壁紧贴于所述安全壳110的内壁面，所述第一冷凝水收集器121的底壁通过一管路连通反应堆堆坑112，该管路上设有第一阀门122。第一冷凝水收集器121的侧壁紧贴于安全壳110的内壁面，使其能更方便有效地收集经安全壳110的内壁面冷凝后形成的冷凝水。
所述第二冷凝水收集器123呈V型结构，所述第二冷凝水收集器123的底部通过第二阀门124连通所述反应堆堆坑112；即，第二冷凝水收集器123具有两侧壁，其两侧壁均呈倾斜设置，两侧壁的底部连接处通过一管路连通反应堆堆坑112，且在该管路上设置有第二阀门124，V型结构使得收集的冷凝水可快速地注入反应堆堆坑112。
另外，所述下降管道134上设有第三阀门135，本实施例中，所述第三阀门135位于所述安全壳110外；高位水池114与反应堆堆坑112之间的管路上还设有第四阀门115。
结合图1、图2所示，对本实施例非能动混凝土安全壳冷却系统100的工作原理进行说明。
当事故发生时，操纵员打开第一冷凝水收集器121、第二冷凝水收集器123连通反应堆堆坑112的管路上的第一阀门122、第二阀门124，并手动打开下降管道134上的第三阀门135，同时打开高位水池114的注入管路上的第四阀门115。
打开第四阀门115后，高位水池114内的冷却水由于压力差而自动注入反应堆堆坑112，进行第一阶段大流量注水，实现反应堆堆坑112的快速注入和压力容器113的快速淹没；此时，压力容器113对反应堆堆坑112内的冷却水加热。反应堆堆坑112内的冷却水经加热产生的高能蒸汽、反应堆一回路破口产生的高能蒸汽均释放到安全壳110内，部分蒸汽在安全壳110内壁冷凝后由第一冷凝水收集器121收集，然后流回至反应堆堆坑112，大部分蒸汽则在内换热器131壁面凝结后经第二冷凝水收集器123收集，然后流回至反应堆堆坑112，通过高位水池114与冷凝水收集回流措施相配合，实现较长时间段内的非能动反应堆堆腔112注水，而不需借助任何外部交流电源和水源即可实现安全壳110内部的自然循环。
同时，内换热器131中的冷却介质吸热后，经内换热器131出口、上升管道132进入冷凝水池140中的外换热器133，在外换热器133中放热冷凝，释放出的热量持续加热外部冷凝水池140中的冷却水而将安全壳110内的热量导出至大气环境最终热阱；冷却介质放热冷凝后，在重力作用下，经由外换热器133的出口、下降管道134回到安全壳110内的内换热器131中，形成闭式回路。因此，不依赖交流电源，实现事故下混凝土式安全壳110的余热导出，提高电厂安全性，尤其具有对于全场断电以及完全丧失冷却链等超设计工况下的防护能力。
下面结合图3-图6所示，对所述非能动混凝土安全壳冷却系统100的第二实施例进行说明，本实施例与上述第一实施例的差别在于：其不具有冷凝水池140，而包括一水箱150，由于水箱150的位置及结构不同于冷凝水池140，因此，本实施例中换热回路系统130的位置与上述实施例略有不同，下面仅就两 者的差别进行描述。
本实施例中，所述水箱150设置于所述安全壳110的顶部111的上方，且所述水箱150内被分隔成相互连通的水冷下降通道157、上升通道158及空冷下降通道159，且所述上升通道158、空冷下降通道159分别连通大气空间，从而使水箱150的压力为大气环境压力，无需相关稳压系统，使系统结构简化。
换热回路系统130的结构与上述第一实施例相同，但本实施例中，外换热器133容置于所述水箱150的上升通道158内，所述上升管道132密封地贯穿所述安全壳110的顶部111并连通内换热器131的出口及外换热器133的入口，下降管道134密封地贯穿所述安全壳110的顶部111并连通外换热器133的出口及内换热器131的入口。
继续参阅图3-图6所示，所述水箱150包括内壁151、外壁152及顶板153，内壁151、外壁152相间隔设置，且内壁151的上端与顶板153固定连接，外壁152的上端与顶板153之间具有一定间隙，所述内壁151、外壁152、所述顶部111共同围成一容纳空间，该容纳空间内被分隔形成水冷下降通道157、上升通道158及空冷下降通道159，且上升通道158及空冷下降通道159均连通大气空间，这样，安全壳110顶部的水箱150的压力为大气环境压力，无需相关稳压系统，使系统结构简化。
再次参阅图3-图6所示，所述水箱150还包括第一隔板154及第二隔板155，第一隔板154、第二隔板155竖直且相间隔地设置于所述水箱150的容纳空间，具体地，第一隔板154、第二隔板155均沿所述水箱150的周向相间隔地设置，所述第一隔板154、所述第二隔板155的下端与所述顶部111之间均具有间隙，第一隔板154的上端与顶板153固定连接，第二隔板155的上端与顶板153之间形成有开口158a，其中，第一隔板154与第二隔板155之间形成所述上升通道158，第一隔板154与内壁151之间形成所述水冷下降通道157，第二隔板155与外壁152之间形成所述空冷下降通道159，也即沿内壁151到外壁152方向，依次形成水冷下降通道157、上升通道158、空冷下降通道159。上升通道158通过所述开口158a连通大气空间，空冷下降通道159通过外壁152与顶板153之间的间隙连通大气空间。
外换热器113设于上升通道158通内并容置于冷却水中，从而使换热回路系统130为封闭式结构，当其任何一端发生破损等情况时，另一端仍然完好，这样不会导通安全壳110，安全壳110内的放射性物质不会释放到外部大气环境。
为提高本发明所述混凝土安全壳非动能冷却系统100的散热效果，可设置多组换热回路系统130，具体地，多组换热回路系统130沿水箱150的四周相间隔地设置，每一组换热回路系统130的外换热器133均设置于所述上升通道158内，且均容置于冷却水中。
同时，为提高系统的可靠性，还可以将水箱150分隔成多个相互独立的水池150`(见图6所示)，每一水池150`对应安装一组换热回路系统130，设置多组独立的水池150`、换热回路系统130，各组换热回路系统130的工作相互独立，即使部分换热回路系统130失效，其它部分仍然可以有效工作，实现较高的系统可靠性。
具体结合图3-图6所示，所述水箱150还包括第三隔板156，所述第三隔板156呈放射状的设置，第三隔板156连接于内壁151与外壁152之间从而将水箱150分隔成多个独立的水池150`，每一个水池150`中均设置有第一隔板154及第二隔板155，其中，所述第一隔板154的两侧分别连接于两相邻的第三隔板156，其上端连接于所述顶板153，所述第二隔板155的两侧分别连接于两相邻的第三隔板156，第二隔板155的上端与顶板153之间形成供上升通道158通过大气空间的开口158a，所述开口158a可通过第二隔板155的上端与顶板153之间的间隙形成，也可以直接在第二隔板155的上端开设通孔形成，且不以此为限。本实施例中，由于外壁152低于内壁151，因此外壁152与所述顶板153之间的间隙即为空冷下降通道159连通大气空间的通道，当然，亦可在外壁152上开设通孔而使空冷下降通道159连通大气空间，但不仅限于此。这样，当其中一部分换热回路系统130失效时，其他换热回路系统130仍正常工作，从而提高系统的可靠性。
所述冷凝水回收系统120的结构与上述第一实施例相同，不再赘述。
下面结合图3-图6所示，对本实施例中混凝土安全壳非动能冷却系统100的工作过程进行描述。
当反应堆出现事故后，从破口释放的水蒸汽等物质进入安全壳110，导致安全壳110内的温度和压力上升，高温的水蒸气及空气混合物上升到安全壳110的上部，并在此接触安全壳110内的内换热器131，与内换热器131的外表面之间发生冷凝传热，水蒸气被冷凝为水，冷凝水被内换热器131下方的第二冷凝水收集器123收集，然后流回至反应堆堆坑112；同时，第一冷凝水收集器121收集由安全壳110内壁冷凝后形成的冷凝水，然后流回至反应堆堆坑112。
内换热器131内的水受热后蒸发，并沿着上升管132进入水箱150内的外换热器133，然后发生冷凝传热，冷凝后的水沿着下降管134回到安全壳110内的内换热器131，从而形成自然循环；外换热器133传递出的热量加热水箱150/水池150`中的冷却水，一定时间后，水箱150/水池150`中的冷却水沸腾，蒸汽沿上升通道158上升并由开口158a释放到大气环境，同时水箱150/水池150`中的冷却水通过水冷下降通道157向上升通道158流动，如图4中箭头方向所示；由于冷却水的汽化潜热大，因此在事故前期利用水箱150/水池150`中的冷却水将热量排入大气环境，可以很好的防止事故初期因大规模的质能释放而导致的安全壳110的超温超压。
当水箱150/水池150`内的冷却水蒸发完毕以后，外换热器133暴露于空气中，其周围的空气被加热，被加热后的空气沿着上升通道158上升，并由开口158a释放到大气环境，同时常温空气通过外壁152与顶板153之间的间隙进入空冷下降通道159，并向上升通道158流动，形成有组织的空气自然对流，如图5中箭头方向所示；从而最终依靠空气冷却将安全壳110内的余热排出到大气环境，实现事故初期安全壳110内大量余热的排出，又可在水箱150/水池150`内的冷却水蒸干条件下利用空气冷却的方式对安全壳110进行长期冷却，能够应对安全壳110在恶劣的事故工况(如失水事故工况)下的冷却问题。
由于本发明的非能动混凝土安全壳冷却系统100，包括换热回路系统130及冷凝水回收系统120，换热回路系统130密封地贯穿所述安全壳110以将安全壳110内的热量导出所述安全壳110外，冷凝水回收系统120设于安全壳110内并连通安全壳内的反应堆堆坑112。当反应堆一回路发生安全事故时，反应堆堆坑112内的冷却水被加热产生的高能蒸汽、反应堆一回路破口释放的高能蒸汽均释 放到安全壳110的内部，高能蒸汽经换热回路系统130导出至大气环境最终热阱，实现对压力容器113的冷却，防止压力容器113熔穿及安全壳110超压，达到消除大规模放射性物质释放的目的；冷凝水回收系统120回收在换热回路系统130或/和安全壳110的内壁处冷凝产生的冷凝水后自动注入反应堆堆坑112，实现较长时间段内的非能动反应堆堆堆坑注水。本发明不依赖外部交流电源等动力便可实现事故下安全壳110内余热的导出及安全壳内的非能动注水，提高核电站的安全性，尤其提高在全场断电以及完全丧失冷却链等超设计工况下的防护能力。
以上所揭露的仅为本发明的优选实施例而已，当然不能以此来限定本发明之权利范围，因此依本发明申请专利范围所作的等同变化，仍属本发明所涵盖的范围。

Claims (17)

  1. 一种非能动混凝土安全壳冷却系统，适用于对安全壳内的热量进行导出，其特征在于：所述非能动混凝土安全壳冷却系统包括换热回路系统及冷凝水回收系统，所述换热回路系统密封地贯穿所述安全壳以将所述安全壳内的热量导出所述安全壳外，所述冷凝水回收系统设于所述安全壳内并连通安全壳内的反应堆堆坑。
  2. 如权利要求1所述的非能动混凝土安全壳冷却系统，其特征在于：所述冷凝水回收系统包括设于所述安全壳的内壁面上的第一冷凝水收集器，所述第一冷凝水收集器高于所述安全壳内的反应堆堆坑并连通所述反应堆堆坑。
  3. 如权利要求2所述的非能动混凝土安全壳冷却系统，其特征在于：所述第一冷凝水收集器通过第一阀门连通所述反应堆堆坑。
  4. 如权利要求2所述的非能动混凝土安全壳冷却系统，其特征在于：所述第一冷凝水收集器呈槽形结构且其一侧壁紧贴于所述安全壳的内壁面。
  5. 如权利要求1所述的非能动混凝土安全壳冷却系统，其特征在于：所述换热回路系统包括设于所述安全壳内的内换热器，所述冷凝水回收系统还包括设于所述安全壳内的第二冷凝水收集器，所述第二冷凝水收集器位于所述内换热器的下方并高于所述安全壳内的反应堆堆坑，且所述第二冷凝水收集器连通所述反应堆堆坑。
  6. 如权利要求5所述的非能动混凝土安全壳冷却系统，其特征在于：所述第二冷凝水收集器通过第二阀门连通所述反应堆堆坑。
  7. 如权利要求5所述的非能动混凝土安全壳冷却系统，其特征在于：所述第二冷凝水收集器呈V型结构。
  8. 如权利要求5所述的非能动混凝土安全壳冷却系统，其特征在于：所述换 热回路系统还包括外换热器、上升管道、下降管道及冷却介质，所述外换热器容置于安全壳外的冷凝水池内，所述内换热器的位置低于所述冷凝水池的位置，所述上升管道密封地贯穿所述安全壳并连通所述内换热器的出口及所述外换热器的入口，所述下降管道密封地贯穿所述安全壳并连通所述外换热器的出口及所述内换热器的入口，所述冷却介质在所述内换热器、所述上升管道、所述外换热器、所述下降管道形成的循环通道内流动。
  9. 如权利要求8所述的非能动混凝土安全壳冷却系统，其特征在于：所述下降管道上设有第三阀门，所述第三阀门位于所述安全壳外。
  10. 如权利要求1所述的非能动混凝土安全壳冷却系统，其特征在于：还包括水箱，所述水箱设置于所述安全壳的顶部，且所述水箱内被分隔成相互连通的水冷下降通道、空冷下降通道及上升通道，且所述空冷下降通道、所述上升通道分别连通大气空间，所述换热回路系统密封地贯穿所述安全壳且一部分容置于所述上升通道内，所述换热回路系统的另一部分位于所述安全壳内。
  11. 如权利要求10所述的非能动混凝土安全壳冷却系统，其特征在于：所述换热回路系统包括外换热器，所述外换热器容置于所述上升通道内。
  12. 如权利要求10所述的非能动混凝土安全壳冷却系统，其特征在于：所述水箱具有底壁及与所述底壁相连接且相间隔的内壁、外壁，所述内壁、所述外壁、所述底壁共同围成一容纳空间。
  13. 如权利要求12所述的非能动混凝土安全壳冷却系统，其特征在于：所述水箱的容纳空间内竖直地设置有相间隔的第一隔板及第二隔板，且所述第一隔板、所述第二隔板的下端与所述底壁之间均具有间隙，所述第一隔板与所述第二隔板之间形成所述上升通道，所述第一隔板与所述内壁之间形成所述水冷下降通道，所述第二隔板与所述外壁之间形成所述空冷下降通道。
  14. 如权利要求13所述的非能动混凝土安全壳冷却系统，其特征在于：所述水箱还具有一顶板，所述内壁、所述第一隔板的上端均连接于所述顶板，所述 第二隔板的上端与所述顶板之间具有设置有开口，所述上升通道通过所述开口连通大气空间。
  15. 如权利要求14所述的非能动混凝土安全壳冷却系统，其特征在于：所述外壁与所述顶板之间具有间隙，所述空冷下降通道连通所述外壁与所述顶板之间的间隙连通大气空间。
  16. 如权利要求10所述的非能动混凝土安全壳冷却系统，其特征在于：所述水箱被分隔成多个相互独立的水池，每一所述水池内均设置有所述水冷下降通道、所述空冷下降通道及所述上升通道，且每一所述水池对应设置一所述换热回路系统。
  17. 如权利要求1所述的非能动混凝土安全壳冷却系统，其特征在于：还包括设于所述安全壳内的高位水池，所述高位水池位于所述安全壳内的反应堆堆坑的上方并连通所述反应堆堆坑，所述高位水池与所述反应堆堆坑之间设有第四阀门。
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