WO2024131546A1 - Réacteur nucléaire - Google Patents

Réacteur nucléaire Download PDF

Info

Publication number
WO2024131546A1
WO2024131546A1 PCT/CN2023/137013 CN2023137013W WO2024131546A1 WO 2024131546 A1 WO2024131546 A1 WO 2024131546A1 CN 2023137013 W CN2023137013 W CN 2023137013W WO 2024131546 A1 WO2024131546 A1 WO 2024131546A1
Authority
WO
WIPO (PCT)
Prior art keywords
pipe
cavity
heat exchange
reactor vessel
exchange device
Prior art date
Application number
PCT/CN2023/137013
Other languages
English (en)
Chinese (zh)
Inventor
梁活
林继铭
段承杰
崔大伟
宋磊
沈永刚
王迪
徐伟峰
王晓婷
徐昌恒
潘晖
廖子昱
袁昭君
Original Assignee
中广核研究院有限公司
中国广核集团有限公司
中国广核电力股份有限公司
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 中广核研究院有限公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 中广核研究院有限公司
Publication of WO2024131546A1 publication Critical patent/WO2024131546A1/fr

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
    • 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
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • 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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • 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 present application relates to the technical field of nuclear power equipment, and in particular to a nuclear reactor.
  • the international community has carried out research on small mobile nuclear reactors with inherent safety, simple systems, and the ability to be fully prefabricated and quickly assembled in factories.
  • the containment of the small mobile nuclear reactor is set to a cylindrical shape. The resulting problem is that the height difference between the reactor core and the heat exchanger is small, and the circulation capacity is weak.
  • a nuclear reactor comprising:
  • a reactor vessel wherein a liquid coolant is arranged in the reactor vessel, wherein the liquid coolant is located in the reactor vessel The portion above the coolant forms an air cavity;
  • the heat exchange device being arranged in the reactor vessel and below the liquid level of the liquid coolant, the heat exchange device comprising an inner wall and an outer wall, the inner wall surrounding a first cavity for accommodating a core, and the outer wall and the inner wall jointly defining a closed second cavity;
  • a driving device is arranged in the reactor vessel and is located higher than the liquid level of the liquid coolant, and comprises a suction end and a re-injection end, the suction end is communicated with the air cavity, and the re-injection end extends into the first cavity and is arranged close to the core;
  • a water supply device is connected to the second cavity and is used to provide circulating cold source water required by the heat exchange device.
  • a plurality of heat dissipation fins are disposed on opposite side walls of the second cavity, the plurality of heat dissipation fins are circumferentially spaced along the side walls of the second cavity, and the heat dissipation fins extend vertically along the side walls of the second cavity.
  • a plurality of support members are arranged inside the reactor vessel, including a first support member arranged on the inner side wall of the reactor vessel and a second support member arranged on the bottom of the reactor vessel, and the heat exchange device is suspended in the reactor vessel in cooperation with the support members.
  • the liquid coolant is a molten metal coolant
  • the air cavity is filled with an inert gas
  • the driving device includes a gas compression pump, one end of which is provided with a suction pipe connected to the air cavity, and the other end is provided with a reinjection pipe, an annular injection pipe is provided near the core, and a plurality of upward nozzles are provided along the circumference of the annular injection pipe, one end of the reinjection pipe is connected to the gas compression pump, and the other end is connected to the annular injection pipe.
  • the reactor vessel includes a vessel body and a vessel cover, the upper end surface of the vessel body is provided with an opening, the opening is provided with a matching vessel cover, a steam generator is relatively provided on the inner wall of the vessel body, and the heat exchange device is provided on the steam generator so that the outer wall surface is close to the steam generator.
  • the heat exchange device further includes a coolant pipe, one end of the coolant pipe is connected to the water supply device, and the other end is connected to the second cavity, the coolant pipe includes an outlet pipe and an inlet pipe, and the outlet pipe is arranged above the inlet pipe.
  • the core includes a fuel rod bundle and a control rod assembly.
  • the nuclear power of the fuel rods undergoing nuclear reaction is controlled.
  • the outer side of the core is wrapped with a neutron reflection layer.
  • the water supply device is configured as a pool-type water supply device, including a water supply device for accommodating the reactor
  • the reactor container is provided with a pipeline through hole, and the outlet pipeline and the inlet pipeline are both connected with the pit through the pipeline through hole.
  • the water supply device is configured as a tubular water supply device, including an inlet mother pipe, an outlet mother pipe and a cold source water tank.
  • a plurality of the outlet pipes and a plurality of the inlet pipes are circumferentially arranged along the outer wall of the heat exchange device.
  • a plurality of the inlet pipes merge to form the inlet mother pipe, and a plurality of the outlet pipes merge to form the outlet mother pipe.
  • the inlet mother pipe and the outlet mother pipe are respectively used to connect the cold source water tank with the second cavity.
  • a second isolation valve is provided on the outlet mother pipe, and a third isolation valve is provided on the inlet mother pipe.
  • the height of the cold source water tank is higher than the reactor vessel, and an exhaust window communicating with the outside is provided on the upper end surface of the cold source water tank.
  • FIG1 is a front cross-sectional view of a nuclear reactor (excluding a water supply device);
  • FIG2 is a schematic diagram of the internal cross-section of a reactor vessel of a nuclear reactor
  • FIG3 is a front cross-sectional view of a heat exchange device of a nuclear reactor
  • FIG4 is a top cross-sectional view of a heat exchange device of a nuclear reactor
  • FIG5 is a schematic diagram of the structure of a nuclear reactor using a pool-type water supply device
  • FIG. 6 is a schematic diagram showing the structure of a tubular water supply device used in a nuclear reactor.
  • Cold source water tank 430. Drain pipe; 440. First isolation valve; 450. Exhaust window; 460. Inlet main pipe; 470. Outlet main pipe; 480. Second isolation valve; 490. The third isolation valve; 500, core; 510, neutron reflector.
  • the term "and/or" is only a description of the association relationship of associated objects, indicating that three relationships may exist.
  • a and/or B can represent: A exists alone, A and B exist at the same time, and B exists alone.
  • the character "/" in this article generally indicates that the associated objects before and after are in an "or" relationship.
  • multiple refers to more than two (including two).
  • multiple groups refers to more than two groups (including two groups), and “multiple pieces” refers to more than two pieces (including two pieces).
  • loop heat exchangers In the related art, nuclear reactors often use loop heat exchangers to form the power of natural circulation. The size of the power depends on the relative height difference between the heat source and the cold source. If the height difference is too small, natural circulation cannot be formed.
  • the use of loop heat exchangers requires the installation of heat exchangers as heat transfer interfaces. For small integrated reactors, there is no extra space to install heat exchangers.
  • loop heat exchangers use thin tubes with small diameters and thin walls, which are easy to break under high temperature and high pressure conditions and have low reliability.
  • the present application provides a nuclear reactor, including: a reactor vessel 100, a heat exchange device 200, a drive device 300 and a water supply device 400, wherein the reactor vessel 100 is provided with liquid coolant, and a portion of the reactor vessel 100 located above the liquid coolant forms an air cavity 150, and the heat exchange device 200 is provided in the reactor vessel 100 and is located below the liquid level of the liquid coolant, and the heat exchange device 200 includes an inner wall surface 210 and an outer wall surface 220, and the inner wall surface 210 is provided with a liquid coolant, and the outer wall surface 220 is provided with a liquid coolant, and the inner wall surface 210 is provided with a liquid coolant, and the inner ...20 is provided with a liquid coolant, and the inner wall surface 220 is provided with a liquid coolant, and the inner wall surface 210 is provided with a liquid coolant, and the inner wall surface 220 is provided with a liquid coolant, and the inner wall surface 220 is provided with a liquid coolant, and the inner wall surface 220 is provided
  • the nuclear reactor includes a reactor vessel 100, a heat exchange device 200, a drive device 300 and a water supply device 400, wherein liquid coolant is arranged in the reactor vessel 100, and the part located above the liquid coolant forms an air cavity 150, and the heat exchange device 200 is arranged below the liquid level of the liquid coolant in the reactor vessel 100.
  • the first cavity 240 surrounded by the inner wall surface 210 of the heat exchange device 200 is used to accommodate the core 500, and the outer wall surface 220 and the inner wall surface 210 jointly define a closed second cavity 250 connected to the water supply device 400.
  • the reactor core 500 When the nuclear power plant is operating normally, the reactor core 500 has a relatively high power.
  • the suction end of the driving device 300 extracts gas from the air cavity 150 and then injects it into the liquid coolant at the top of the core 500 through the reinjection end.
  • the injected gas makes the average density of the liquid coolant above the top of the core 500 less than the average density of the coolant near the steam generator 140 at the same height, thereby generating a gravity difference, driving the liquid coolant to circulate inside the reactor vessel 100, so as to form a circulation route from the outlet above the first cavity core 500-upper chamber 160-downward annular cavity 171-lower chamber 170-core 500 inlet-core 500-outlet above the core 500.
  • the liquid coolant flows from top to bottom in the reactor vessel 100 to transfer the heat generated by the core 500 to the steam generator 140 arranged in the downward annular cavity 171.
  • the driving device 300 stops operating.
  • the heat removal system configured for the core 500 cannot work properly, and the circulating cold source water in the water supply device 400 circulates in the second cavity 250 to continuously exchange heat with the core 500 to remove the excess heat of the core 500.
  • the reactor does not need to be equipped with a large-volume main pump, which reduces the complexity and cost of the entire system and avoids the problem of low system reliability caused by failure of the heat removal system.
  • the outer wall 220 is arranged outside the inner wall 210, and the heat exchange device 200 also includes a connecting wall 230 for defining the second cavity 250.
  • the connecting wall 230 is arranged between the outer wall 220 and the two end surfaces of the inner wall, forming an annular cavity sealed on all sides.
  • the inner and outer wall 220 of the heat exchange device 200 are in contact with the coolant of the core 500 of the first cavity 240, and the heat of the coolant can be transferred to the inner wall of the second cavity 250 and the heat dissipation fins 260 welded to the inner wall of the second cavity 250 by heat conduction.
  • the heat exchange device 200 in this embodiment is made of stainless steel material, and is used to bear the function of removing residual heat when the nuclear reactor is shut down.
  • the core 500 and the outer side are separated into two different circulation channels, so that the nuclear reactor does not need to be equipped with a core 500 hanging basket, saving equipment cost and space.
  • a plurality of heat dissipation fins 260 are arranged on the opposite side walls of the second cavity 250, and the plurality of heat dissipation fins 260 are arranged circumferentially at intervals along the side walls of the second cavity 250, and the heat dissipation fins 260 are extended in the vertical direction along the side walls of the second cavity 250.
  • the heat dissipation fins 260 are arranged as a thin sheet structure, which is used to increase the heat exchange area in contact with the cold source water and improve the heat exchange efficiency.
  • a plurality of support members are arranged inside the reactor vessel 100, including a first support member arranged on the inner wall of the reactor vessel 100 and a second support member arranged on the bottom of the reactor vessel 100.
  • the heat exchange device 200 is suspended in the reactor vessel 100 in cooperation with the support members to achieve a better heat exchange effect.
  • the heat exchange device 200 is suspended inside the reactor vessel 100 by a plurality of supports, and an upper chamber 160 is formed above the core 500 in the reactor vessel 100 and below the liquid coolant level, and a lower chamber 170 is formed below the core 500 in the reactor vessel 100, and the lower chamber 170 also includes a descending annular cavity 171 between the outer wall 220 of the heat exchange device 200 and the inner wall of the reactor vessel 100.
  • the liquid coolant is a molten metal coolant
  • the air cavity 150 is filled with an inert gas.
  • the molten metal coolant of the nuclear reactor can be a variety of different types of liquids, including liquid sodium, lead, lead-bismuth alloy, etc. Since the liquid metal coolant has a large density and good thermal conductivity, the use of molten metal coolant in the nuclear reactor can greatly increase the safety performance of the reactor.
  • the air cavity 150 at the liquid level of the molten metal coolant is filled with an inert gas to control the pressure of the molten metal coolant and keep it within a certain safety range.
  • the primary circuit uses molten metal as a coolant, which does not require too much high head difference between cold and hot sources, and can save layout space.
  • the driving device 300 includes a gas compression pump 310, one end of the gas compression pump 310 is provided with a suction pipe 320 connected to the air cavity 150, and the other end is provided with a re-injection pipe 330.
  • An annular jet pipe 340 is provided near the core 500 , and a plurality of upward nozzles 341 are provided circumferentially along the annular jet pipe 340 .
  • One end of the reinjection pipe 330 is connected to the gas compression pump 310 , and the other end is connected to the annular jet pipe 340 .
  • the gas compression pump 310 is set at a height higher than the liquid level of the liquid coolant inside the reactor vessel 100, that is, the positions where the suction pipe 320 and the re-injection pipe 330 are inserted through the wall of the reactor vessel 100 are both higher than the liquid level of the internal coolant.
  • the re-injection pipe 330 includes a first pipe body 331 inserted through the reactor vessel 100 and a second pipe body 332 that turns downward and extends downward along the inner wall 210 of the heat exchange device 200.
  • the second pipe body 332 is connected to the annular jet pipe 340, and multiple nozzles 341 distributed at intervals in the annular jet pipe 340 can discharge gas more evenly.
  • a gas compression pump 310 with a simpler configuration is used instead of the main pump. By adjusting the flow rate of the gas compression pump 310 to change the gravity difference, the coolant flow rate of the core 500 is changed, so that the flow path of the entire nuclear reactor is simple, the resistance generated is reduced, and the natural circulation capacity is improved.
  • the reactor vessel 100 includes a container body 110 and a container cover 120, the upper end surface of the container body 110 is provided with an opening, and the opening is provided with an adaptable container cover 120, a steam generator 140 is relatively provided on the inner wall of the container body 110, and a heat exchange device 200 is provided on the steam generator 140 so that the outer wall surface 220 is close to the steam generator 140.
  • the container body 110 is cylindrical and vertically upward, mainly used to accommodate the nuclear reactor core 500 and the internal coolant, and is made of stainless steel.
  • the steam generator 140 is arranged between the outer wall 220 of the heat exchange device 200 and the inner wall of the container body 110, that is, the upper part of the descending annular cavity 171, and the height is higher than the core 500 and as high as possible.
  • the steam generator 140 is a normal heat removal system in a nuclear reactor.
  • the steam generator 140 directly exchanges heat with the liquid coolant in the reactor vessel 100, and the high-temperature superheated steam generated drives the turbine and then drives the generator to generate electricity.
  • the isolation valve in the water supply device 400 is not opened; after an accident occurs in a nuclear power plant, the steam generator 140 in the normal heat removal system cannot work.
  • the second cavity 250 in the heat exchange device 200 is used to cooperate with the water supply device 400 to perform heat exchange to discharge the residual heat of the core 500.
  • the steam generator 140 is composed of a spiral heat exchange tube bundle, the interior of the tube bundle is provided with cold water by the main water supply system of the nuclear reactor, and the exterior of the tube bundle is immersed in the coolant of the nuclear reactor.
  • the spiral heat exchange tube is made of high-strength steel alloy material, and can transfer heat in the nuclear reactor coolant to the inner wall of the heat exchange tube, gradually heating the cold water flowing inside it. After absorbing heat, the cold water gradually vaporizes and becomes high-temperature and high-pressure superheated steam, which is discharged from the end of the heat exchange tube and enters the main steam system of the nuclear reactor, driving the turbine, and then driving the generator to generate power.
  • the heat exchange device 200 further includes a coolant pipe 270, one end of the coolant pipe 270 is connected to the water supply device 400, and the other end is connected to the second cavity 250, and the coolant pipe 270 includes an outlet pipe 271 and an inlet pipe 272.
  • the outlet pipe 271 is disposed above the inlet pipe 272 .
  • the outlet pipe 271 and the inlet pipe 272 can be arranged at multiple angles in the radial cross section of the reactor vessel 100, and the angles and numbers of the arrangements can be set according to actual needs.
  • the outlet pipe 271 is arranged above the inlet pipe 272.
  • the outlet pipe 271 is arranged at one end of the heat exchange device 200 away from the core 500, and the inlet pipe 272 is arranged at one end of the heat exchange device 200 close to the bottom of the core 500, so that the cold source water in the second cavity 250 can fully realize heat exchange therein.
  • the outlet pipe 271 and the inlet pipe 272 penetrate the wall of the reactor vessel 100, one end is connected to the second cavity 250 of the heat exchange device 200, and the other end is connected to the water supply device 400 for providing circulating cold source water.
  • the second cavity 250 of the heat exchange device 200 is filled with non-condensable inert gas and will not exchange heat with the liquid coolant in the nuclear reactor.
  • the cold source water in the water supply device 400 enters the inlet pipe 272 due to gravity and enters the bottom of the heat exchange device 200, before the water level rises to the height of the pipe mouth of the outlet pipe 271, the cold source water contacts and exchanges heat with the two side walls and the heat dissipation fins 260 in the second cavity 250. After being heated by the heat of the core 500, the cold source water will be heated and evaporated, and the generated water vapor is discharged from the outlet pipe 271.
  • the core 500 includes a fuel rod bundle and a control rod assembly.
  • the nuclear power of the nuclear reaction of the fuel rods is controlled by controlling the insertion depth of the control rod assembly.
  • the outer side of the core 500 is wrapped with a neutron reflection layer 510.
  • the outer wall surface 220 contacts the coolant in the descending annular cavity 171 for heat exchange, part of the inner wall surface 210 contacts the neutron reflector 510 for heat exchange, and part of the inner wall surface 210 contacts the coolant in the upper chamber 160 for heat exchange, even under the condition of low natural circulation flow of the core 500, the decay heat of the core 500 can still be continuously discharged through the inner wall surface 210 of the heat exchange device 200.
  • the heat generated by the nuclear reaction in the core 500 is transferred to the coolant flowing through the core 500 through heat exchange, and by wrapping a layer of neutron reflector 510 around the core 500 with the function of reflecting neutrons back to the core 500, the loss of fission neutrons to the surrounding environment is reduced, and the burnup depth of the nuclear reactor is increased.
  • the isolation valve is in a closed state, and the second cavity 250 of the heat exchange device 200 is filled with non-condensable inert gas, and does not exchange heat with the coolant in the reactor core 500.
  • the reactor is shut down, and the isolation valve is activated by an automatic signal to start the emergency residual heat removal operation.
  • the water supply device 400 is configured as a pool-type water supply device 400, including a pit 410 for accommodating the reactor vessel 100, and a pipe through hole 130 is provided on the reactor vessel 100, and the outlet pipe 271 and the inlet pipe 272 are both connected to the pit 410 through the pipe through hole 130.
  • the entire reactor vessel 100 is arranged in the sunken pit 410, and the outlet pipe 271 and the inlet pipe 272 of the heat exchange device 200 are directly connected to the heat exchange device 200 through the pipe through hole 130. It is connected to the inner space of the pit 410 , and no additional isolation valve is required between the two, which simplifies the structure of the reactor vessel 100 .
  • the water supply device 400 can directly inject cold source water into the pit 410 .
  • the water supply device may include a cold source water tank 420 and a drain pipe 430.
  • the drain pipe 430 is provided to connect the cold source water tank 420 and the pit 410.
  • a first isolation valve 440 for controlling the on-off is provided on the drain pipe 430.
  • the height of the cold source water tank 420 is higher than the pit 410, and an exhaust window 450 connected to the outside is provided on the upper end surface of the cold source water tank 420.
  • the cold source water tank 420 is set on the upper part of the reactor vessel 100 and the pit 410, and the first isolation valve 440 is set on the drain pipe 430 to control the on and off of the cold source water.
  • the exhaust window 450 on the top of the cold source water tank 420 plays the role of sucking the gas outside the water tank into the water tank to balance the pressure inside the water tank, ensuring that the cooling water in the water tank can be smoothly injected into the pit 410.
  • the diameter of the drain pipe 430 can be appropriately increased, and the volume of the pit 410 below the height of the outlet pipe 271 can be reduced.
  • the working process of nuclear reactor waste heat discharge under this scheme is as follows: when the waste heat of the core 500 cannot be discharged normally, the emergency waste heat signal is sent to trigger the first isolation valve 440 to open, and the cooling water of the cold source water tank 420 is injected into the pit 410 through the drain pipe 430 under the action of gravity. When the water level in the pit 410 rises to submerge the inlet pipe 272, the cooling water begins to enter the second cavity 250 of the heat exchange device 200, thereby contacting and exchanging heat with the heat dissipation fins 260 in the second cavity 250 and the wall surface of the second cavity 250.
  • Part of the cooling water in the second cavity 250 will be heated and evaporated, and the generated water vapor will be discharged from the outlet pipe 271, forming a natural circulation flow channel of cooling water from the cold source water tank 420-pit 410-inlet pipe 272-second cavity 250 of the heat exchange device-outlet pipe 271-pit 410, which continuously brings out the decay heat inside the nuclear reactor.
  • the water supply device 400 is configured as a tubular water supply device 400, including an inlet mother pipe 460, an outlet mother pipe 470 and a cold source water tank 420, multiple outlet pipes 271 and multiple inlet pipes 272 are circumferentially arranged along the outer wall of the heat exchange device 200, multiple inlet pipes 272 merge to form the inlet mother pipe 460, and multiple outlet pipes 271 merge to form the outlet mother pipe 470.
  • the inlet mother pipe 460 and the outlet mother pipe 470 are respectively used to connect the cold source water tank 420 with the second cavity 250, a second isolation valve 480 is provided on the outlet mother pipe 470, and a third isolation valve 490 is provided on the inlet mother pipe 460.
  • the height of the cold source water tank 420 is higher than the reactor vessel 100, and an exhaust window 450 communicating with the outside is provided on the upper end surface of the cold source water tank 420.
  • the cold source water tank 420 is arranged at a position as high as possible on the upper part of the reactor vessel 100, and the outlet mother pipe 470 and the inlet mother pipe are respectively connected to the bottom of the cold source water tank 420, thereby forming a circulating heat exchange loop of cold source water tank 420-inlet mother pipe 460-inlet pipe 272-second cavity 250 of heat exchange device 200-outlet pipe 271-outlet mother pipe 470-cold source water tank 420.
  • the working process of the nuclear reactor residual heat removal under this scheme is as follows: when the residual heat of the core 500 cannot be discharged normally, the emergency residual heat signal is sent to trigger the second isolation valve 480 and the third isolation valve 490 to open at the same time, and the cooling water in the cold source water tank 420 is turned off. Under the action of gravity, it is injected into the inlet main pipe 460, and then enters the inlet pipe 272 of the heat exchange device 200, pushing away the non-condensable gas originally in the second cavity 250 of the heat exchange, and the non-condensable gas enters the outlet pipe 271, then reaches the outlet main pipe, and finally enters the cold source water tank 420.
  • the cooling water is in contact with the heat dissipation fins 260 and the wall of the second cavity 250 for heat exchange, the temperature gradually rises, and the density gradually decreases, so that the gravity pressure head of the water inlet main pipe is greater than the gravity pressure head of the water outlet main pipe, forming a gravity difference driving force, and then forming a circulation heat exchange loop of cold source water tank 420-inlet main pipe-inlet pipe 272-heat exchange device 200-outlet pipe 271-outlet main pipe-cold source water tank 420, which continuously brings out the decay heat of the reactor. Under this scheme, the water temperature in the cold source water tank 420 gradually rises, and the steam generated after boiling will be discharged to the external environment through the exhaust window 450 on the top of the water tank.
  • the cold source water tank 420 of the above two schemes can be arranged into various irregular shapes such as square and cylindrical according to the characteristics of the nuclear reactor building, and can be made of stainless steel or concrete with stainless steel lining. A large amount of deionized water is filled in the cold source water tank 420, and the initial water volume can be set according to the power characteristics of the reactor.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

L'invention concerne un réacteur nucléaire, comprenant : une cuve de réacteur (100), un dispositif d'échange de chaleur (200), un dispositif d'entraînement (300) et un dispositif d'alimentation en eau (400). Un liquide de refroidissement et une cavité de gaz (150) sont prévus dans la cuve de réacteur (100) ; le dispositif d'échange de chaleur (200) est disposé dans la cuve de réacteur (100) ; le dispositif d'échange de chaleur (200) comprend une surface de paroi externe (220) et une surface de paroi interne (210), une première cavité (240) destinée à recevoir un cœur de réacteur (500) étant formée sur la surface de paroi interne (210), et la surface de paroi externe (220) et la surface de paroi interne (210) délimitant conjointement une seconde cavité (250) ; le dispositif d'entraînement (300) a une extrémité reliée à la cavité de gaz (150) et l'autre extrémité est disposée à proximité du cœur de réacteur (500) ; et le dispositif d'alimentation en eau (400) est relié à la seconde cavité (250). Selon le réacteur nucléaire, lorsqu'une situation d'accident se produit, la chaleur au niveau d'un côté primaire du réacteur et du cœur de réacteur (500) peut être évacuée, évitant ainsi d'endommager le combustible par un réchauffement supplémentaire du cœur de réacteur (500).
PCT/CN2023/137013 2022-12-22 2023-12-07 Réacteur nucléaire WO2024131546A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN202211656253.5A CN116052908A (zh) 2022-12-22 2022-12-22 一种核反应堆
CN202211656253.5 2022-12-22

Publications (1)

Publication Number Publication Date
WO2024131546A1 true WO2024131546A1 (fr) 2024-06-27

Family

ID=86117350

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CN2023/137013 WO2024131546A1 (fr) 2022-12-22 2023-12-07 Réacteur nucléaire

Country Status (2)

Country Link
CN (1) CN116052908A (fr)
WO (1) WO2024131546A1 (fr)

Also Published As

Publication number Publication date
CN116052908A (zh) 2023-05-02

Similar Documents

Publication Publication Date Title
JP4148417B2 (ja) 液体金属炉の安定的な受動残熱除去系
KR100966854B1 (ko) 부분잠김형 열교환기를 사용하는 소듐냉각 고속로의 완전 피동형 잔열제거계통
WO2022194247A1 (fr) Réacteur passif intégré
US8542792B1 (en) Reactor vessel coolant deflector shield
JP2002156485A (ja) 原子炉
CN105047235A (zh) 核反应堆严重事故状态下熔融物堆内滞留非能动冷却系统
US10102936B2 (en) Nuclear stream supply system
US20100226471A1 (en) System for evacuating the residual heat from a liquid metal or molten salts cooled nuclear reactor
US20040240601A1 (en) Forced cooling circular deep & minus; water pond type heat supply nuclear reactor with natural circulation
CN204680390U (zh) 压水堆核电站分离式热管式非能动余热排出系统
JPH0585040B2 (fr)
WO2024131546A1 (fr) Réacteur nucléaire
JPH0659076A (ja) 加圧水型原子炉の残留出力除去装置
US4554129A (en) Gas-cooled nuclear reactor
CN113140337B (zh) 多介质共用冷却通道的非能动冷却系统、方法及反应堆
CN212230087U (zh) 一种利用浮球阀控制的池式反应堆余热排出系统
JP7439263B2 (ja) 一体型原子炉
JP2003139881A (ja) 超臨界圧水冷却炉、チャンネルボックス、水ロッドおよび燃料集合体
CN111899902A (zh) 一种利用浮球阀控制的池式反应堆余热排出系统
CN112382420B (zh) 一种基于水冷器的非能动余热排出系统
JP5595672B2 (ja) 原子炉
CN112420226B (zh) 一种基于环形气冷器的非能动余热排出系统
FI129308B (en) Nuclear reactor module and a nuclear nuclear thermal reactor comprising the same and a method for operating the nuclear reactor module
JP2740995B2 (ja) 液体金属冷却型高速炉及びそれを用いた発電システム
CN117976263A (zh) 非能动余热排出热交换器强化换热装置