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WO2025060631A1 - Système de sécurité de réacteur intégré et son procédé de commande - Google Patents

Système de sécurité de réacteur intégré et son procédé de commande Download PDF

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Publication number
WO2025060631A1
WO2025060631A1 PCT/CN2024/105894 CN2024105894W WO2025060631A1 WO 2025060631 A1 WO2025060631 A1 WO 2025060631A1 CN 2024105894 W CN2024105894 W CN 2024105894W WO 2025060631 A1 WO2025060631 A1 WO 2025060631A1
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WIPO (PCT)
Prior art keywords
pipeline
pressure
integrated reactor
secondary side
containment
Prior art date
Legal status (The legal status 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 status listed.)
Pending
Application number
PCT/CN2024/105894
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English (en)
Chinese (zh)
Inventor
戚展飞
杨子江
严锦泉
王海涛
刘镝
李睿
胡楠
吴燕华
任文星
王国栋
樊普
李盛哲
曹克美
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Original Assignee
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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.)
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Publication of WO2025060631A1 publication Critical patent/WO2025060631A1/fr
Pending legal-status Critical Current
Anticipated expiration legal-status Critical

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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
    • 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 invention relates to the technical field of nuclear reactor safety systems, and in particular to an integrated reactor safety system and method.
  • the integrated pressurized water reactor has the characteristics of small size, compact structure and high system integration. It can be used for different special purposes such as marine development and industrial production, and meet different needs such as power supply, heating and steam supply.
  • the integrated pressurized water reactor has high requirements for system simplification, layout space utilization, safety and economy.
  • the heat of the reactor core is exported to the steam turbine through the main heat exchangers such as the steam generator to generate electricity, or exported to the heat/steam supply system to generate heat or steam.
  • the main heat exchangers such as the steam generator are unavailable, and the residual heat of the core cannot be exported by normal means; if a LOCA accident occurs (the pressure boundary of the reactor pressure vessel is damaged), a large amount of water will be lost in the reactor, which may cause the exposed heat transfer of the core to deteriorate; in addition, the containment may continue to increase in pressure after the accident, resulting in overpressure failure of the containment and damage to the radioactive barrier.
  • a dedicated safety system must be configured to promptly remove the residual heat of the core to ensure that the residual heat of the core is not damaged.
  • the core is replenished with lost water to prevent the accident from further deteriorating into a serious accident of core damage, and to prevent the containment from overpressure failure, resulting in the danger of large-scale radioactive release.
  • the traditional dedicated safety system of a pressurized water reactor generally includes an active residual heat removal system, an active high-pressure, medium-pressure and low-pressure safety injection system, an active containment spray system, etc.
  • the design and configuration scheme of the dedicated safety system in the prior art 1) requires the joint action of many systems and equipment, the system configuration is complex, and the accident mitigation path is long. Once a system or equipment fails, it may affect the entire accident mitigation process, so a large number of redundant equipment needs to be configured; 2) most of them use active systems, rely on external power, and need to be configured with support systems such as equipment cooling water.
  • the active dedicated safety system will not be able to perform its function; 3) the system and equipment and related support systems are complicated, and the layout requires a lot of space, occupying a lot of free space in the containment, and the operation and maintenance convenience is low; 4) in the later stage of the accident, once the cooling water source is exhausted, it is necessary to configure an additional recirculation pump (or borrow a low-pressure injection pump) to extract water from the containment pit and inject water into the reactor pressure vessel. The cooling in the later stage of the accident requires additional equipment to maintain, and the reliability is poor. Post-accident recovery also requires the elimination of radioactivity in the pit. Therefore, the design and configuration scheme of the dedicated safety system in the prior art cannot be applied to the special requirements of the integrated reactor dedicated safety system, such as simplification, small layout space, high safety and economic requirements.
  • the present invention provides an integrated reactor safety system and method to meet the needs of reactor design basis accidents (LOCA and non-LOCA accidents) mitigation, ensure reactor safety, simplify equipment to the maximum extent, improve layout space utilization, and enhance economy.
  • LOCA reactor design basis accidents
  • a first aspect of the present invention provides an integrated reactor safety system, comprising:
  • An integrated reactor pressure vessel which is arranged in the containment vessel, wherein a reactor core and a built-in pressurizer are arranged in the integrated reactor pressure vessel, wherein the reactor core is arranged at the lower part of the integrated reactor pressure vessel, and the built-in pressurizer is arranged at the top of the integrated reactor pressure vessel;
  • a primary and secondary heat exchanger which is arranged inside the integrated reactor pressure vessel, wherein the secondary inlet of the primary and secondary heat exchanger is connected to the secondary water supply pipeline, and the secondary outlet of the primary and secondary heat exchanger is connected to the secondary outlet pipeline;
  • a passive waste heat removal heat exchanger is arranged outside the containment, the outlet of the passive waste heat removal heat exchanger is connected to the secondary side water supply pipeline through a waste discharge outlet pipeline, and the inlet of the non-kinetic waste heat removal heat exchanger is connected to the secondary side outlet pipeline through a waste discharge inlet pipeline;
  • an upper chamber is arranged between the built-in pressurizer and the reactor core, and the in-core components and the control rod drive mechanism are arranged in the upper chamber; an upper chamber water flow hole is opened on the side wall of the upper chamber, the primary and secondary side heat exchanger is located outside the upper chamber, and the upper chamber water flow hole is located above the primary and secondary side heat exchanger.
  • a pressure relief valve is provided on the top of the integrated reactor pressure vessel, and the top of the built-in pressurizer is connected to the pressure relief valve.
  • a secondary water supply line isolation valve is provided on the secondary water supply line, and a secondary outlet line isolation valve is provided on the secondary outlet line.
  • one end of the excess outlet pipeline is connected between the secondary water supply pipeline isolation valve and the secondary inlet of a secondary heat exchanger, and one end of the excess inlet pipeline is connected between the secondary outlet pipeline isolation valve and the secondary outlet of a secondary heat exchanger.
  • a pressure-accumulating safety injection tank is also provided in the containment, which is connected to the integrated reactor pressure vessel through a safety injection pipeline.
  • the pressure-accumulating safety injection tank is filled with coolant, and the safety injection pipeline is provided with a safety injection pipeline check valve and a safety injection pipeline isolation valve.
  • the safety injection pipeline isolation valve is connected in parallel with the bypass pipeline.
  • the passive residual heat removal heat exchanger is placed in an external heat sink outside the containment vessel.
  • the external heat sink is provided with external heat sink cooling means.
  • a containment pressure suppression pool is provided inside the containment, and the containment pressure suppression pool is a closed A closed tank filled with coolant, the top of the containment suppression pool is connected to the containment space through the suppression pool inlet pipeline.
  • a suppression pool bubbler is provided inside the containment suppression pool, the suppression pool bubbler is located below the coolant liquid level in the containment suppression pool and is connected to the end of the suppression pool inlet pipeline.
  • a second aspect of the present invention provides a control method for an integrated reactor safety system, using the integrated reactor safety system as described in the first aspect of the present invention to perform safety control on an integrated reactor, the method comprising the following steps:
  • control method of the integrated reactor safety system further comprises the following steps:
  • the pressure relief valve When the pressure of the integrated reactor pressure vessel drops to the opening pressure of the pressure relief valve, the pressure relief valve is triggered to open, so that the pressure of the integrated reactor pressure vessel drops to the initial pressure accumulation pressure of the pressure accumulation injection tank;
  • the pressurized nitrogen in the pressure storage injection tank pushes the internal coolant and enters the integrated reactor pressure vessel through the injection pipeline to replenish the lost water.
  • the valves on the injection pipeline and the bypass pipeline are configured to achieve different injection flow rates before and after injection, ensuring that the water level in the integrated reactor pressure vessel is always higher than the water flow hole in the upper chamber during the entire accident process, ensuring that a natural circulation can always be established between the reactor core and the primary and secondary side heat exchangers, thereby utilizing the primary and secondary side heat exchangers to remove the heat of the reactor core for a long time.
  • control method of the integrated reactor safety system further comprises the following steps:
  • the integrated reactor safety system and control method thereof of the present invention can cope with various design basis accidents (LOCA and non-LOCA accidents), continuously remove reactor heat, maintain reactor cooling, eliminate high-pressure and low-pressure injection, and active dedicated safety systems and equipment in traditional reactor safety systems, simplify equipment to the maximum extent, and have flexible layout and small space requirements.
  • LOCA and non-LOCA accidents design basis accidents
  • continuously remove reactor heat maintain reactor cooling
  • eliminate high-pressure and low-pressure injection and active dedicated safety systems and equipment in traditional reactor safety systems, simplify equipment to the maximum extent, and have flexible layout and small space requirements.
  • FIG1 is a schematic diagram of an integrated reactor safety system according to a specific embodiment of the present invention.
  • FIG. 2 is a flow chart of a control method for an integrated reactor safety system according to a specific embodiment of the present invention.
  • FIG1 is a schematic diagram of an integrated reactor safety system according to a specific embodiment of the present invention.
  • the integrated reactor safety system 100 includes: a containment vessel 60, an integrated reactor pressure vessel 10, a primary and secondary side heat exchanger 20 and a passive residual heat exchanger 21. Exhaust heat exchanger 40.
  • the integrated reactor pressure vessel 10 is arranged in the containment vessel 60 .
  • a reactor core 11 and a built-in pressurizer 12 are arranged in the integrated reactor pressure vessel 10 .
  • the reactor core 11 is arranged at the lower part of the integrated reactor pressure vessel 10
  • the built-in pressurizer 12 is arranged at the top of the integrated reactor pressure vessel 10 .
  • the primary and secondary heat exchangers 20 are arranged inside the integrated reactor pressure vessel 10 , the secondary inlets of the primary and secondary heat exchangers 20 are connected to the secondary water supply pipeline 21 , and the secondary outlets of the primary and secondary heat exchangers 20 are connected to the secondary outlet pipeline 22 .
  • the passive waste heat removal heat exchanger 40 is arranged outside the containment shell 60, and the outlet of the passive waste heat removal heat exchanger 40 is connected to the secondary side water supply pipeline 21 through the waste heat removal outlet pipeline 41, and the inlet of the non-kinetic waste heat removal heat exchanger 40 is connected to the secondary side outlet pipeline 22 through the waste heat removal inlet pipeline 42.
  • the passive waste heat removal heat exchanger 40 can be a tube bundle type, and its elevation is higher than that of the primary and secondary heat exchangers 20.
  • An upper chamber 16 is arranged between the built-in pressurizer 12 and the reactor core 11, and the upper chamber 16 is provided with in-core components and a control rod drive mechanism 13; an upper chamber water flow hole 14 is opened on the side wall of the upper chamber 16, the primary and secondary side heat exchanger 20 is located outside the upper chamber 16, and the upper chamber water flow hole 14 is located above the primary and secondary side heat exchanger 20.
  • the primary coolant is heated by the reactor core 11, passes through the internal components of the upper chamber 16 and the control rod drive mechanism 13, passes through the upper chamber water flow hole 14, and returns to the reactor core 11 to form a cycle after heat exchange in the primary and secondary heat exchangers 20.
  • the secondary fluid enters the primary and secondary heat exchangers 20 from the secondary water supply pipeline 21, takes out the primary heat, and flows out from the secondary outlet pipeline 22.
  • the integrated reactor pressure vessel 10 may be provided with a primary coolant pump to perform forced circulation on the primary side; or may not be provided with a primary coolant pump and the primary coolant may be circulated in a natural circulation manner.
  • the integrated reactor safety system 100 of this embodiment can cope with various design basis accidents (LOCA and non-LOCA accidents), continuously remove reactor heat, maintain reactor cooling, eliminate high-pressure and low-pressure injection, and active dedicated safety systems and equipment in traditional reactor safety systems, simplify equipment to the maximum extent, and have flexible layout and small space requirements.
  • LOCA and non-LOCA accidents design basis accidents
  • continuously remove reactor heat maintain reactor cooling
  • eliminate high-pressure and low-pressure injection and active dedicated safety systems and equipment in traditional reactor safety systems, simplify equipment to the maximum extent, and have flexible layout and small space requirements.
  • a pressure relief valve 15 is provided on the top of the integrated reactor pressure vessel 10, and the top of the built-in pressurizer 12 is connected to the pressure relief valve 15.
  • the pressure relief valve 15 can be configured in a manner of multiple parallel connections and multiple stages opened separately, with two or more independent series.
  • the secondary inlet of the primary and secondary heat exchanger 20 is connected to the secondary water supply pipeline 21, and the secondary outlet of the primary and secondary heat exchanger 20 is connected to the secondary outlet pipeline 22.
  • a secondary water supply pipeline isolation valve 23 is provided on the secondary water supply pipeline 21, and a secondary outlet pipeline isolation valve 24 is provided on the secondary outlet pipeline 22.
  • a passive residual heat removal heat exchanger 40 is arranged outside the containment 60, and is equipped with two or more independent passive residual heat removal series, each of which is connected to one or a group of primary and secondary side heat exchangers 20.
  • the outlet of the passive residual heat removal heat exchanger 40 is connected to a residual heat outlet pipeline 41, and its inlet is connected to a residual heat inlet pipeline 42.
  • a residual heat outlet pipeline isolation valve 43 is arranged on the residual heat outlet pipeline 41, and the residual heat outlet pipeline isolation valve 43 is a normally open valve.
  • a residual heat inlet pipeline isolation valve 44 is arranged on the residual heat inlet pipeline 42, and the residual heat inlet pipeline isolation valve 44 is connected to the residual heat outlet pipeline 42.
  • the exhaust inlet pipeline isolation valve 44 is a normally closed valve.
  • the exhaust inlet pipeline isolation valve 44 will open.
  • the exhaust outlet pipeline 41 is connected to the secondary water supply pipeline 21, and the connection point is between the secondary water supply pipeline isolation valve 23 and the secondary inlet of the primary and secondary heat exchangers 20; the exhaust inlet pipeline 42 is connected to the secondary outlet pipeline 22, and the connection point is between the secondary outlet pipeline isolation valve 24 and the secondary outlet of the primary and secondary heat exchangers 20.
  • a closed circulation loop between the secondary side heat exchanger 20 and the passive residual heat removal heat exchanger 40 can be formed by closing the secondary side water supply pipeline isolation valve 23 and the secondary side outlet pipeline isolation valve 24 and opening the residual heat removal inlet pipeline isolation valve 44.
  • the passive residual heat removal heat exchanger 40 is placed in an external heat well 70 outside the containment vessel 60.
  • the external heat well 70 is a water pool structure, which has a large capacity that can meet the core residual heat removal requirements for at least 7 days.
  • An external heat well cooling device 71 is provided on the external heat well 70, and the external heat well 70 can be cooled by the external heat well cooling device 71.
  • the external heat sink 70 may also be a natural cooling water source such as a river, lake, or sea.
  • the external heat sink cooling device 71 may be a non-safety grade cooling device.
  • This embodiment provides an external heat sink 70 outside the containment vessel, which can meet the core cooling demand for at least 7 days after an accident and achieve long-term removal of reactor heat.
  • a pressure accumulator injection tank 30 is also provided in the containment 60, and two or more independent pressure accumulator injection systems are configured.
  • the pressure accumulator injection tank 30 is connected to the integrated reactor pressure vessel 10 through an injection pipeline 32.
  • the pressure accumulator injection tank 30 is filled with coolant and a certain proportion of nitrogen is filled for pressure accumulation. When the integrated reactor pressure vessel 10 loses coolant, the coolant is replenished for the integrated reactor pressure vessel 10.
  • the coolant in this embodiment is water.
  • the injection pipeline 32 is provided with an injection pipeline check valve 31 and an injection pipeline isolation valve 33.
  • the injection pipeline isolation valve 33 is a normally open valve.
  • the injection pipeline isolation valve 33 is connected to the bypass pipeline 34.
  • the resistance of the injection line isolation valve 33 and the parallel branch where it is located is much smaller than the resistance of the bypass line 34 and the parallel branch where it is located.
  • the injection pipeline check valve 31 has a check function, which prevents the fluid inside the integrated reactor pressure vessel 10 from entering the pressure accumulator injection tank 30 when the pressure of the integrated reactor pressure vessel 10 is higher than the pressure of the pressure accumulator injection tank 30. Since the injection pipeline check valve 31 has a small opening when the pressure difference between the two ends is small, and the small opening means a large resistance, the injection flow through the injection pipeline check valve 31 is small in the late injection period of the pressure accumulator injection tank 30 when the pressure of the pressure accumulator injection tank 30 is small.
  • the function of the injection line isolation valve 33 is to cut off the pipeline in the late stage of pressure accumulation injection, so that the flow of the pressure accumulation injection tank 30 passes through the bypass line 34. That is, when a certain amount of coolant is still left inside the pressure accumulation injection tank 30, the injection line isolation valve 33 is triggered to close, and the remaining coolant in the pressure accumulation injection tank 30 can continue to be injected into the integrated reactor pressure vessel 10 through the bypass line 34. Since the resistance of the bypass line 34 and the parallel branch where it is located is much greater than the resistance of the injection line isolation valve 33 and the parallel branch where it is located, the injection flow rate will be greatly reduced.
  • the injection line isolation valve 33 When the pressure accumulator injection tank 30 replenishes the coolant into the pressure vessel 10, at the initial stage of injection, the injection line isolation valve 33 is in an open state, and the injection line check valve 31 is also in an open state because the pressure of the pressure accumulator injection tank 30 is greater than the pressure of the pressure vessel 10; at the later stage of injection, when a certain amount of coolant is still left inside the pressure accumulator injection tank 30, the injection line isolation valve 33 is closed, so that the injection flow only passes through the parallel bypass line 34 with greater resistance. As the injection progresses, the pressure of the pressure accumulator injection tank 30 gradually decreases, and the pressure difference with the pressure vessel 10 also gradually decreases, so the opening of the injection line check valve 31 also gradually decreases (and does not close), and the resistance gradually increases. In this way, at the later stage of injection, the resistance from the pressure accumulator injection tank 30 to the pressure vessel 10 increases, achieving an injection flow different from that at the initial stage of injection.
  • the check valve 31 of the injection pipeline is a swing check valve.
  • the pressure difference between the two ends of the check valve 31 is small, the valve opening is small, the resistance is large, and the injection flow rate is small.
  • the pressurized nitrogen can push the coolant in the pressure-accumulated injection tank 30 through the injection pipeline 32.
  • Water is replenished by entering the integrated reactor pressure vessel 10 so that the water level in the integrated reactor pressure vessel 10 is always higher than the water flow hole 14 of the upper chamber, ensuring that natural circulation can always be established between the reactor core 11 and the primary and secondary side heat exchangers 20, thereby utilizing the primary and secondary side heat exchangers 20 to remove heat from the reactor core 11 for a long time.
  • This embodiment maintains natural circulation between the reactor core 11 and the primary and secondary heat exchangers 20 through the pressure storage injection and passive residual heat removal heat exchanger 40, without the need for containment pit recirculation, greatly simplifying the post-accident mitigation path and facilitating post-accident recovery.
  • a containment suppression pool 50 is further provided inside the containment 60.
  • the containment suppression pool 50 is located at the bottom of the containment 60.
  • the containment suppression pool 50 is a closed tank body, including a suppression pool inlet pipeline 51, a suppression pool bubbler 52, and a suppression pool shell 53.
  • the suppression pool shell 53 shares a portion of the wall of the containment 60.
  • the containment suppression pool 50 is filled with coolant and a certain proportion of air space is reserved.
  • the containment suppression pool 50 is only connected to the space of the containment 60 through the suppression pool inlet pipeline 51.
  • the suppression pool bubbler 52 is located below the coolant liquid level in the containment suppression pool 50 and is connected to the end of the suppression pool inlet pipeline 51.
  • the pressure suppression tank bubbler 52 can reduce the occurrence of steam hammer. This process does not require the wall of the containment 60 to have good heat conduction or cooling capabilities.
  • the pressure suppression tank shell 53 shares a portion of the wall of the containment 60, and can flexibly utilize the space inside the containment 60, reducing the need for the overall layout of the containment pressure suppression tank 50.
  • this embodiment can passively reduce or maintain the pressure of the containment 60 at a low level. There is no need for complex active spraying equipment and support systems, nor does it require the wall of the containment 60 to have good thermal conductivity or cooling capabilities.
  • the containment pressure suppression pool 50 is simple in layout and has high layout space utilization.
  • This embodiment provides a control method of an integrated reactor safety system 100, which uses the above-mentioned integrated reactor safety system 100 to perform safety control on an integrated reactor.
  • the method includes the following steps:
  • Step S1 when a non-LOCA accident occurs, a control method of the integrated reactor safety system 100.
  • Step S2 when a LOCA accident occurs, a control method of the integrated reactor safety system 100.
  • Step S3 when the pressure of the containment vessel 60 is high, the control method of the integrated reactor safety system 100.
  • step S1 when a non-LOCA accident occurs, the control method of the integrated reactor safety system 100 specifically includes the following steps:
  • Step S11 when a non-LOCA accident occurs, close the secondary water supply pipeline isolation valve 23 and the secondary outlet pipeline isolation valve 24.
  • Step S12 open the waste heat inlet pipeline isolation valve 44, and confirm that the waste heat outlet pipeline isolation valve 43 is normally open.
  • the primary and secondary side heat exchangers 20 and the passive waste heat removal heat exchanger 40 rely on natural circulation to form a closed circulation loop, bringing the heat of the reactor core 11 to the external heat sink 70.
  • Step S21 when a LOCA accident occurs, close the secondary water supply pipeline isolation valve 23 and the secondary outlet pipeline isolation valve 24.
  • Step S22 opening the waste gas inlet pipeline isolation valve 44 , and ensuring that the waste gas outlet pipeline isolation valve 43 is normally open, so as to continuously bring out the reactor core heat to the external heat sink 70 .
  • Step S23 when the pressure of the integrated reactor pressure vessel 10 drops to the opening pressure of the pressure relief valve 15 , the pressure relief valve 15 is triggered to open, so that the pressure of the integrated reactor pressure vessel 10 drops to the initial pressure accumulation pressure of the pressure accumulation injection tank 30 .
  • step S24 the pressurized nitrogen in the pressure storage injection tank 30 pushes the internal coolant to enter the integrated reactor pressure vessel 10 through the injection pipeline 32 to replenish the lost water volume, and through the configuration of the valve on the injection pipeline 32 and the bypass pipeline 34, different injection flow rates before and after injection are achieved, ensuring that the water level in the integrated reactor pressure vessel 10 is always higher than the upper chamber water flow hole 14 during the entire accident process, ensuring that a natural circulation can always be established between the reactor core 11 and the primary and secondary side heat exchangers 20, thereby utilizing the primary and secondary side heat exchangers 20 to remove the heat of the reactor core 11 for a long time.
  • Excessive injection causes the water in the integrated reactor pressure vessel 10 to overflow from the rupture, and can also replenish the water volume lost due to long-term evaporation and the water body shrinkage caused by overcooling, thereby maintaining the water level in the integrated reactor pressure vessel 10 always higher than the upper chamber water flow hole 14, ensuring that the heat of the reactor core 11 is always taken out by the natural circulation between the reactor core 11 and the primary and secondary side heat exchangers 20. Therefore, there is no need to use pit recirculation to maintain long-term cooling after the LOCA accident, which greatly simplifies the post-accident mitigation path and is conducive to post-accident recovery.
  • step S3 when the pressure of the containment vessel 60 is high, the integrated reactor safety system 100
  • the control method specifically comprises the following steps:
  • Step S31 when the pressure of the containment 60 is high, high-temperature and high-pressure steam is passively sucked from the suppression pool inlet pipeline 51 into the containment suppression pool 50 to be condensed, thereby ensuring that the pressure inside the containment 60 does not exceed the limit.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

La présente invention concerne un système de sécurité de réacteur intégré et son procédé de commande. Le système comprend une cuve sous pression de réacteur intégrée et une enceinte de confinement. La cuve sous pression de réacteur intégrée est disposée dans l'enceinte de confinement, et un échangeur de chaleur côté primaire et côté secondaire est disposé dans la cuve sous pression de réacteur intégrée, une entrée côté secondaire de l'échangeur de chaleur côté primaire et côté secondaire est raccordée à la tuyauterie d'alimentation en eau côté secondaire, et une sortie côté secondaire de l'échangeur de chaleur côté primaire et côté secondaire est raccordée à la tuyauterie de sortie côté secondaire ; un échangeur de chaleur à évacuation de chaleur résiduelle passive est disposé sur un côté externe de l'enceinte de confinement ; une sortie de l'échangeur de chaleur à évacuation de chaleur résiduelle passive est raccordée à la tuyauterie d'alimentation en eau côté secondaire au moyen d'une tuyauterie de sortie d'évacuation de chaleur résiduelle, et une entrée de l'échangeur de chaleur à évacuation de chaleur résiduelle passive est raccordée à la tuyauterie de sortie côté secondaire au moyen d'une tuyauterie d'entrée d'évacuation de chaleur résiduelle. La présente invention répond aux exigences d'atténuation des accidents de conception des réacteurs, garantit la sécurité des réacteurs, simplifie au maximum l'équipement, améliore l'utilisation de l'espace disponible et est plus économique.
PCT/CN2024/105894 2023-09-20 2024-07-17 Système de sécurité de réacteur intégré et son procédé de commande Pending WO2025060631A1 (fr)

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CN202311221353.XA CN117253634A (zh) 2023-09-20 2023-09-20 一种一体化反应堆安全系统及方法

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CN117253634A (zh) * 2023-09-20 2023-12-19 上海核工程研究设计院股份有限公司 一种一体化反应堆安全系统及方法

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CN108346475A (zh) * 2018-01-24 2018-07-31 中广核研究院有限公司 一种小型堆安全壳非能动抑压系统
CN110911020A (zh) * 2019-12-04 2020-03-24 上海核工程研究设计院有限公司 一种压力容器顶部双层的先进专设安全设施配置方案
CN111540486A (zh) * 2020-04-16 2020-08-14 中国核动力研究设计院 一种小型压水反应堆及安全壳长期非能动热量排出系统
CN112530611A (zh) * 2020-12-24 2021-03-19 上海核工程研究设计院有限公司 一种先进简化的小堆非能动专设安全系统
CN215450910U (zh) * 2021-03-17 2022-01-07 上海核工程研究设计院有限公司 一种一体化非能动先进小堆
CN114582529A (zh) * 2022-02-16 2022-06-03 中国核动力研究设计院 基于大盘管蒸汽发生器的微型全自然循环压水反应堆系统
CN115240879A (zh) * 2022-07-05 2022-10-25 上海核工程研究设计院有限公司 一种双层安全壳反应堆安全系统及反应堆系统
CN117253634A (zh) * 2023-09-20 2023-12-19 上海核工程研究设计院股份有限公司 一种一体化反应堆安全系统及方法

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