CN119993576A - A natural circulation heat removal system for a pile pit, a nuclear power plant reactor and a heat removal method thereof - Google Patents
A natural circulation heat removal system for a pile pit, a nuclear power plant reactor and a heat removal method thereof Download PDFInfo
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- CN119993576A CN119993576A CN202510465286.9A CN202510465286A CN119993576A CN 119993576 A CN119993576 A CN 119993576A CN 202510465286 A CN202510465286 A CN 202510465286A CN 119993576 A CN119993576 A CN 119993576A
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- 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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
本申请属于核电技术领域，具体涉及一种堆坑自然循环排热系统、核电站反应堆及其排热方法。该堆坑自然循环排热系统包括堆坑排风系统和拔风烟囱。堆坑排风系统包括进风管道、出风管道、进风风机、第一阀门、第二阀门、第三阀门和排风风机。进风风机和第一阀门沿进风管道的进风方向依次串设在进风管道上。第二阀门设置在与进风管道连通的支路管道上。第三阀门和排风风机沿出风管道的出风方向依次串设在出风管道上。进风管道穿过反应堆大厅的侧面和安全壳后与堆坑连接。本申请通过以非能动自然循环方式带走堆坑热量，以解决目前快堆均未考虑堆坑自然循环排热设计及应用，堆坑通风系统设计较为复杂的技术问题。
The present application belongs to the field of nuclear power technology, and specifically relates to a natural circulation heat removal system for a reactor pit, a nuclear power plant reactor and a heat removal method thereof. The natural circulation heat removal system for the reactor pit includes a reactor pit exhaust system and an air extraction chimney. The reactor pit exhaust system includes an air inlet duct, an air outlet duct, an air inlet fan, a first valve, a second valve, a third valve and an exhaust fan. The air inlet fan and the first valve are sequentially arranged on the air inlet duct along the air inlet direction of the air inlet duct. The second valve is arranged on a branch duct connected to the air inlet duct. The third valve and the exhaust fan are sequentially arranged on the air outlet duct along the air outlet direction of the air outlet duct. The air inlet duct passes through the side of the reactor hall and the containment and is connected to the reactor pit. The present application removes the heat from the reactor pit in a passive natural circulation manner to solve the technical problem that the current fast reactors do not consider the design and application of natural circulation heat removal from the reactor pit, and the design of the reactor pit ventilation system is relatively complicated.
Description
Technical Field
The application belongs to the technical field of nuclear power, and particularly relates to a natural circulation heat removal system for a pit, a nuclear power station reactor and a heat removal method thereof.
Background
Fast reactors with liquid metal as coolant are typically high temperature systems, and the pit in which the reactor is located is subject to high temperatures under both normal and accident conditions. The original design is to set up complicated ventilation system, guarantees under normal operating mode that the heap hole temperature is under the concrete loses the crystallization water temperature, under the accident operating mode, also considers whether auxiliary facilities can be inefficacy, leads to the accident result further to enlarge.
When the fast reactor nuclear power station normally operates, the fan of the reactor ventilation system normally operates to continuously replace air in the reactor pit, the air is discharged to the atmosphere through a ventilation pipeline and a chimney, and the reactor pit is maintained in a negative pressure state. The negative pressure design ensures that the gas flow direction is from the reactor factory to the pit during normal operation, so that a very small amount of radioactive substances released by the reactor are prevented from entering the reactor hall, and the safety of operators is threatened. Radiation monitoring monitors radioactivity levels in the reactor building and in the roof shield in real time.
When a design reference accident occurs in the sodium-cooled fast reactor nuclear power station, a loop boundary can be kept complete, radioactive substances in the reactor are contained in the loop boundary, so that the reactor pit is not required to bear the function of radioactive containment in most cases, but the surface of the reactor container has certain heat dissipation capacity, and the surface of the reactor container needs to be discharged so as to maintain the temperature of the reactor body and equipment in the reactor pit within a certain range. At present, a pit exhaust system is arranged, and a fan drives gas in the pit to be exhausted, so that equipment in the pit is cooled.
In the event of a severe accident, the radioactive material in the main reactor vessel leaks into the containment through the main vessel roof equipment. When the radiation monitoring system of the containment detects radioactivity abnormality, the containment isolation system is triggered to operate, and the isolation valves on the coolant pipeline and the ventilation pipeline penetrating through the containment device are automatically isolated. At this time, the inner containment is in a sealed state, so that radioactive substances can be effectively prevented from leaking to the environment in serious accidents, and the environment is influenced. After the containment device is sealed for a period of time, a relatively large portion of the short-lived radioactive material in the radioactive material decays, leaving only a small amount of long-lived radioactive material. At this time, the containment isolation state is released, the reactor ventilation system is started, and the radioactive substances are filtered and then discharged from the overhead.
However, at present, no design and application of natural circulation heat removal of a pit are considered in the fast reactor, and the design of a pit ventilation system is complex.
Disclosure of Invention
In view of the above, the present application is directed to providing a natural circulation heat removal system for a pit, a nuclear power plant reactor and a heat removal method thereof, which solve the technical problem that the design and application of natural circulation heat removal for the pit are not considered in the prior fast reactor, and the design of a ventilation system for the pit is relatively complex.
The first aspect of the application provides a natural circulation heat removal system for a pit, which is applied to a nuclear island part of a nuclear power station. The nuclear island part of the nuclear power station comprises a reactor body, a reactor pit, a containment vessel and a reactor hall. The pile body is arranged in the pile pit, and the upper parts of the pile body and the pile pit are containment vessels. The reactor hall is enclosed outside the containment. The natural circulation heat removal system for the pit comprises a pit exhaust system and an air extraction chimney. The pit exhaust system comprises an air inlet pipeline, an air outlet pipeline, an air inlet fan, a first valve, a second valve, a third valve and an exhaust fan. The air inlet fan and the first valve are sequentially arranged on the air inlet pipeline in series along the air inlet direction of the air inlet pipeline and are positioned in the area between the containment and the reactor hall. The second valve is arranged on a branch pipeline communicated with the air inlet pipeline and is positioned on one side of the first valve close to the containment, and the second valve and the branch pipeline are both positioned in an area between the containment and the reactor hall. The third valve and the exhaust fan are sequentially arranged on the air outlet pipeline in series along the air outlet direction of the air outlet pipeline and are positioned in the area between the containment and the reactor hall. The air outlet pipeline passes through the containment and then is connected with the stacking pit. The draft chimney is connected with an air outlet of the air outlet pipeline and is positioned outside the reactor hall. The air inlet pipeline passes through the side surface of the reactor hall and the containment, and then is connected with the stacking pit.
In one embodiment of the application, the air intake duct extends to a first linear distance from the floor of the pit. The air outlet pipeline extends to a second linear distance from the bottom surface of the stacking pit. The second linear distance is greater than the first linear distance.
In one embodiment of the application, the reactor body is a liquid metal reactor body.
In one embodiment of the application, the core outlet temperature of the liquid metal reactor body is greater than 500 ℃.
In one embodiment of the application, the liquid metal reactor body is a sodium cooled fast reactor body.
In one embodiment of the application, the height and the arrangement position of the draft chimney are obtained through coupling calculation of natural circulation driving force and flow resistance.
A second aspect of the application provides a nuclear power plant reactor comprising a nuclear island portion of a nuclear power plant and a natural circulation heat rejection system of the first aspect of the application.
The third aspect of the application provides a heat removal method of a nuclear power station reactor, which comprises the steps of opening a first valve and a third valve of a natural circulation heat removal system of a reactor pit in the embodiment of the application when the reactor is in a normal power operation condition, closing a second valve, filtering air in the reactor pit by an air exhaust fan and an air draft chimney, discharging the filtered air into the environment, closing an air inlet fan and the air exhaust fan when the reactor is in a shutdown material replacement condition, adopting a natural circulation mode to maintain the temperature and the negative pressure of the reactor pit, automatically isolating a containment under an accident condition when the reactor is in the accident condition, and then opening the third valve and placing the second valve at a valve opening of 5%.
The technical scheme of the application has the beneficial effects that the wind extraction chimney is arranged outside the reactor hall and is connected with the reactor pit through the wind outlet pipeline, and the first valve, the second valve and the third valve are arranged to realize taking away of heat of the reactor pit in a passive natural circulation mode by opening and closing the first valve, the second valve and the third valve, thereby being beneficial to maintaining the structural integrity of the reactor body and the reactor pit, assisting in enhancing the natural circulation capacity in the reactor, improving the safety and the economy of the reactor and simplifying the operation. In addition, when the natural circulation heat removal system of the pit can be used for keeping the natural circulation heat removal of the pit when the primary pressure boundary is not damaged or the radionuclide leakage influence is not higher than the tiny damage required by the annual discharge amount in the national standard, under the accident working condition, the natural circulation heat removal system of the pit can be used for reliably removing the heat in a natural circulation mode, and meanwhile, the organized discharge of the filtration of the gas in the containment is realized, and the auxiliary effect on the discharge of the residual heat of the reactor accident can be realized.
Drawings
Fig. 1 is a schematic view of a nuclear power plant reactor according to an embodiment of the present application.
Detailed Description
The following description of the embodiments of the present application will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present application, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the application without making any inventive effort, are intended to be within the scope of the application.
At least one embodiment of the application provides a natural circulation heat removal system for a pit, which is applied to a nuclear island part of a nuclear power station. The nuclear island section of the nuclear power plant includes a reactor body 1, a reactor pit 2, a containment vessel 3, and a reactor hall 10. The pile body 1 is located in the pile pit 2, and the upper parts of the pile body 1 and the pile pit 2 are the containment vessel 3. The reactor hall 10 is enclosed outside the containment vessel 3. The natural circulation heat removal system for the pit comprises a pit exhaust system and an air extraction chimney 9. The pit exhaust system comprises an air inlet pipeline, an air outlet pipeline, an air inlet fan 4, a first valve 5, a second valve 6, a third valve 7 and an exhaust fan 8. The air inlet fan 4 and the first valve 5 are sequentially arranged on the air inlet pipeline in series along the air inlet direction of the air inlet pipeline and positioned in the area between the containment vessel 3 and the reactor hall 10. The second valve 6 is arranged on a branch pipeline communicated with the air inlet pipeline and is positioned on one side of the first valve 5 close to the containment vessel 3, and the second valve 6 and the branch pipeline are both positioned in the area between the containment vessel 3 and the reactor hall 10. The third valve 7 and the exhaust fan 8 are sequentially arranged on the air outlet pipeline in series along the air outlet direction of the air outlet pipeline and positioned in the area between the containment vessel 3 and the reactor hall 10. The air outlet pipeline passes through the containment vessel 3 and then is connected with the stacking pit 2. The air draft chimney 9 is connected with an air outlet of the air outlet pipeline. The air intake pipe is connected with the pit 2 after passing through the side surface of the reactor hall 10 and the containment vessel 3.
The stack body 1 refers to all components in the entire stack vessel, including the core and a loop system. The draft chimney 9 may be located outside the reactor hall 10, or may be partially outside the reactor hall 10, and partially inside the reactor hall 10. The air outlet pipeline can also pass through the top of the reactor hall and the containment vessel 3 and then be connected with the pit 2.
Next, the working principle of the natural circulation heat removal system for a pit will be specifically described with reference to fig. 1.
When the reactor is in a normal power operation working condition, the reactor body 1 is in a high temperature state, when the natural circulation heat removal system of the reactor pit is started, the first valve 5 and the third valve 7 are opened, the second valve 6 is closed, and the air in the reactor pit 2 is discharged into the environment after being filtered by the air exhaust fan 8 and the air draft chimney 9.
When the reactor is in a shutdown and refueling working condition, the first valve 5 and the third valve 7 are in an open state, the second valve 6 is in a closed state, the temperature of the reactor body 1 is low, the heat load of the reactor pit is small, the air inlet fan 4 and the air outlet fan 8 can be closed, and the temperature and the negative pressure of the reactor pit 2 are maintained in a natural circulation mode.
Under the accident condition of the reactor, the first valve 5 is in a closed state, the containment vessel 3 is automatically isolated, the nuclide with short half-life is decayed, at the moment, the temperature in the pit 2 is increased, and the radioactivity level is accumulated. After this, the third valve 7 is opened and the second valve 6 is placed at a small opening (e.g., 5% valve opening), maintaining natural circulation cooling of the pit 2 and achieving filtration of residual radioactivity and organized discharge.
According to the natural circulation heat removal system for the pit, provided by the embodiment of the application, the air draft chimney 9 is arranged outside the reactor hall 10, the air draft chimney 9 is connected with the pit 2 through the air outlet pipeline, and the first valve 5, the second valve 6 and the third valve 7 are arranged, so that the heat of the pit is taken away in an passive natural circulation mode by opening and closing the first valve 5, the second valve 6 and the third valve 7, the structural integrity of the pit body 1 and the pit 2 is kept, the natural circulation capacity in the reactor is enhanced in an auxiliary manner, the safety and the economy of the reactor are improved, and the operation is simplified. In addition, when the natural circulation heat removal system of the pit can be used for keeping the natural circulation heat removal of the pit 2 when the primary pressure boundary is not damaged or the radionuclide leakage is not affected by the tiny damage of the annual discharge requirement in the national standard, under the accident working condition, the natural circulation heat removal system of the pit can reliably remove the heat in a natural circulation mode, and meanwhile, the filtration and organized discharge of the gas in the containment vessel 3 are realized, and the auxiliary effect on the discharge of the reactor accident waste heat can be realized.
In at least one embodiment of the present application, the air intake duct extends to a first linear distance D1 from the bottom surface S Bottom of the pit 2. The air outlet pipe extends to a second linear distance D2 from the bottom surface S Bottom of the pit 2. The second linear distance D2 is greater than the first linear distance D1. Therefore, the air inlet pipeline and the air outlet pipeline are reasonably designed to extend to the position in the stacking pit 2, so that the natural circulation heat removal efficiency is higher.
The air intake fan 4 may be installed on the horizontal floor S 1 of the reactor hall 10.
In at least one embodiment of the application, the reactor body 1 is a liquid metal reactor body. Further, in some embodiments, the core outlet temperature of the liquid metal reactor body is greater than 500 ℃.
It should be noted that the liquid metal reactor body includes, but is not limited to, a sodium-cooled fast reactor body or a lead-cooled fast reactor body, which is not particularly limited in the embodiment of the present application. For example, the core outlet temperature of the sodium cooled fast reactor body may be 565 ℃. The core outlet temperature of the lead cooled fast reactor body may be 540 ℃.
In at least one embodiment of the application, the height and arrangement position of the draft chimney 9 are obtained by coupling calculation of natural circulation driving force and flow resistance. In this way, the height and arrangement position of the wind extraction chimney 9 can meet the requirements of natural circulation ventilation under normal power operation working conditions and accident working conditions.
The resistance can be determined through geometric parameters such as pipeline length, pipe inner diameter, pipe inner elbow and the like, and the natural circulation driving force can be determined through reasonably setting the position height of the draft chimney.
At least one embodiment of the present application also provides a nuclear power plant reactor, which includes a nuclear island portion of a nuclear power plant and a natural circulation heat rejection system of a pit according to any one of the above embodiments of the present application. The nuclear island section of the nuclear power plant includes a reactor body 1, a reactor pit 2, a containment vessel 3, and a reactor hall 10. Containment vessel 3 is placed in pit 2, and pit 2 and containment vessel 3 are located with pile body 1. The reactor hall 10 is enclosed outside the containment vessel 3. The natural circulation heat removal system for the pit comprises a pit exhaust system and an air extraction chimney 9. The pit exhaust system comprises an air inlet pipeline, an air outlet pipeline, an air inlet fan 4, a first valve 5, a second valve 6, a third valve 7 and an exhaust fan 8. The air inlet fan 4 and the first valve 5 are sequentially arranged on the air inlet pipeline in series along the air inlet direction of the air inlet pipeline and positioned in the area between the containment vessel 3 and the reactor hall 10. The second valve 6 is arranged on a branch pipeline communicated with the air inlet pipeline and is positioned on one side of the first valve 5 close to the containment, and the second valve 6 and the branch pipeline are both positioned in the area between the containment 3 and the reactor hall 10. The third valve 7 and the exhaust fan 8 are sequentially arranged on the air outlet pipeline in series along the air outlet direction of the air outlet pipeline and positioned in the area between the containment vessel 3 and the reactor hall 10. The air outlet pipeline passes through the containment vessel 3 and then is connected with the stacking pit 2. The draft chimney 9 is connected with the air outlet of the air outlet pipeline and is positioned outside the reactor hall 10. The air intake pipe is connected with the pit 2 after passing through the side surface of the reactor hall 10 and the containment vessel 3.
It should be noted that, the nuclear power station reactor includes a natural circulation heat removal system for a pit in any of the above embodiments of the present application, which has corresponding technical features, and can achieve corresponding technical effects, and will not be described herein again.
The nuclear power station reactor provided by the embodiment of the application simplifies the design of the traditional pit ventilation system and the containment, and simultaneously ensures that the natural circulation heat removal system of the pit in the nuclear power station reactor has a part of auxiliary heat removal function. By the design of the draft chimney 9 of the communication pile pit 2, the requirements of a ventilation system under normal power operation working conditions and accident working conditions are reduced, and the passive safety of the reactor is improved.
The application also provides a heat removal method of the nuclear power station reactor, which comprises the following steps of.
And S100, when the reactor is in a normal power operation condition, opening a first valve 5 and a third valve 7 of the natural circulation heat removal system of the reactor pit, closing a second valve 6, and filtering and discharging air in the reactor pit 2 into the environment by an exhaust fan 8 and an air draft chimney 9.
And S200, when the reactor is in a shutdown and refueling working condition, the air inlet fan 4 and the air outlet fan 8 are closed, and a natural circulation mode is adopted to maintain the temperature and the negative pressure of the reactor pit 2.
And S300, under the accident condition of the reactor, the containment vessel 3 is automatically isolated, and then the third valve 7 is opened, and the second valve 6 is set at the valve opening of 5%.
The heat removal method of the nuclear power station reactor can refer to the specific description of the working principle of the natural circulation heat removal system of the nuclear power station reactor, and the description is omitted here. The heat removal method of the nuclear power station reactor uses the natural circulation heat removal system of the pit in the embodiment of the application, and the heat removal method comprises corresponding technical characteristics, so that corresponding technical effects can be realized, and the description is omitted here.
It should be noted that, the combination of the technical features in the embodiment of the present application is not limited to the combination described in the embodiment of the present application or the combination described in the specific embodiment, and all the technical features described in the present application may be freely combined or combined in any manner unless contradiction occurs between them.
As used in the specification and in the claims, the terms "a," "an," and/or "the" are not specific to a singular, but may include a plural number, unless the context clearly dictates otherwise. In general, the term "comprising" merely indicates that the explicitly identified steps and elements are included, and that these steps and elements do not constitute an exclusive list, as other steps or elements may be included in a method or apparatus.
The foregoing description of the preferred embodiments of the application is not intended to be limiting, but rather is to be construed as including any modifications, equivalents, and alternatives falling within the spirit and principles of the application.
Claims (8)
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| Application Number | Priority Date | Filing Date | Title |
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| CN202510465286.9A CN119993576B (en) | 2025-04-15 | 2025-04-15 | Pile pit natural circulation heat removal system, nuclear power station reactor and heat removal method thereof |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202510465286.9A CN119993576B (en) | 2025-04-15 | 2025-04-15 | Pile pit natural circulation heat removal system, nuclear power station reactor and heat removal method thereof |
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| CN119993576B CN119993576B (en) | 2025-06-20 |
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