CN112053791B - Non-time-limit passive combined heat removal system with integrated heat release trap - Google Patents
Non-time-limit passive combined heat removal system with integrated heat release trap Download PDFInfo
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/257—Promoting flow of the coolant using heat-pipes
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
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- 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
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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
- 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
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Abstract
The invention provides a non-time-limit passive combined heat removal system with an integrated heat release trap, wherein the integrated heat release trap is arranged at the middle lower part of a double-layer coagulated containment interlayer air space, the integrated heat release trap is an annular water pool surrounded by a corrosion-resistant metal plate, at least one group of communication pipelines and one-way valves leading to the air space in a containment are arranged on the inner containment wall surface of the air space at the upper part of the containment interlayer, and the integrated heat release trap is connected with a containment rapid pressure release system, an automatic pressure release system, a passive waste heat discharge system, a passive low-pressure safety injection system, a passive reactor cavity water injection system and a filtering discharge system.
Description
Technical Field
The invention relates to a passive safety system in an advanced nuclear power plant, in particular to a non-time-limit passive combined heat removal system with an integrated heat release trap.
Background
Since the nuclear energy of the sixties and seventies of the last century realizes large-scale commercial use, the nuclear energy supply system provides clean and efficient energy for human beings for a long time. Due to the potential radioactive risks in the operation of nuclear power plants, the safety of the nuclear power plants is always highly concerned by the people in the industry, particularly research and development personnel.
To date, three more serious accidents have occurred in the nuclear power field: the first is the accident of the three li island, the second is the accident of the soviet chernobiles and the third is the accident of the japanese fukushima. The profound lessons summarized from the three nuclear accidents are that human misoperation is likely to cause serious accidents of the reactor; the active safety facilities have greater potential safety hazards under the condition of the power failure accident of the whole plant. How to adopt a passive safety system to derive the residual heat in the reactor/containment for a long time so as to enhance the inherent safety of the nuclear power plant and provide sufficient judgment time for the intervention of an operator becomes one of the key points of the development of a third-generation nuclear power unit.
The Hualongyi nuclear power generating unit of the third generation with completely independent property rights in China introduces a design concept of combining active and passive according to the innovation of potential reactor accidents. In the aspect of a passive safety system, a passive safety injection system, a passive waste heat discharge system and a passive reactor cavity water injection system are arranged aiming at a main coolant loop and a secondary side. A passive containment heat exporting system is arranged for a last safety barrier of a nuclear power plant, namely a double-layer concrete containment. The coordinated operation of the systems can effectively resist the power failure accident of the whole nuclear power plant and provide 72 hours of non-intervention time for operators.
With respect to advanced nuclear power technology, prior patents disclose passive safety systems. The patent with publication numbers of CN111128414A and CN111383782A provides a plurality of passive safety systems, including passive containment heat removal systems, secondary side passive waste heat removal systems, passive safety injection systems and the like, the patent with publication number of CN209149827U and the patent with publication number of CN110021447A provide passive secondary side waste heat removal systems, and the patent with publication numbers of CN110400644A and CN106024077A respectively disclose a passive containment heat removal system. These patents are characterized by focusing mainly on the arrangement scheme of each passive system, and the design does not consider the interrelation between different passive safety systems. Typically, there are separate heat traps in different passive safety systems, which results in the need to arrange multiple cooling water/storage tanks at different spatial locations inside/outside the containment, which is detrimental to the simplification of complex circuits in nuclear power plants and the reduction of construction costs.
In the aspect of containment heat export, according to the process of accident development, 2 pressure peak values are formed in the internal air space of the containment, namely a first pressure peak value with higher amplitude formed in the containment within tens of seconds in the initial stage of large-crevasse spraying and a second pressure peak value formed in the process of long-term cooling after the reactor core is re-submerged. Regarding the solution of containment gas space pressure relief, the published patent is mainly directed to the second pressure peak, and no effective solution is formed in relieving the first pressure peak of the containment, and the buffering capacity of the containment gas space is enhanced mainly by enlarging the volume of the containment as much as possible, which increases the volume and construction cost of the containment of the nuclear power plant.
It can be seen that further developments of existing passive safety systems are mainly limited to the following three points: firstly, how to effectively deal with the first pressure peak value of a large breach accident under the condition of smaller containment volume; secondly, how to simplify the system arrangement and reduce the equipment redundancy by effectively integrating heat release traps of different passive systems; and thirdly, how to finish the non-time-limit heat output of the containment.
Therefore, a non-time-limit passive combined heat removal system with an integrated heat release trap is needed to be invented, so that the arrangement of a reactor system is simplified, the volume of a safety shell is reduced, non-time-limit heat export is provided for a safety shell, and a feasible scheme is finally provided for the economy and passive safety of an advanced nuclear power plant.
Disclosure of Invention
The invention aims to provide a non-time-limit passive combined heat removal system with an integrated heat release trap, which is used for simplifying the arrangement of a reactor system of a nuclear power plant, reducing the volume of a safety shell, providing non-time-limit heat export for the safety shell and finally providing a feasible scheme for improving the economy and the passive safety of an advanced nuclear power plant.
The purpose of the invention is realized as follows: the integrated heat release trap is an annular water pool surrounded by corrosion-resistant metal plates, at least one group of communication pipelines and one-way valves leading to the air space in the containment are arranged on the wall surface of an inner containment of the air space on the upper portion of the containment interlayer, and the integrated heat release trap is connected with a rapid containment pressure release system, an automatic pressure release system, a passive residual heat discharge system, a passive low-pressure passive safety injection system, a passive reactor cavity water injection system and a filtering and discharging system, wherein the rapid containment pressure release system, the automatic pressure release system, the passive residual heat discharge system, the passive low-pressure safety injection system, the passive reactor cavity water injection system and the filtering and discharging system are the same in number as the communication pipelines and the one-way valve groups leading to the air space in the containment.
The invention also includes such structural features:
1. the system comprises an external natural ventilation type air cooler, a cooling pipe section, a containment interlayer PCS heat exchanger and a heat pipe section, wherein the containment interlayer PCS heat exchanger is arranged in a double-layer concrete containment interlayer, the external natural ventilation type air cooler comprises an umbrella-mounted baffle, an air inlet, an air outlet and a reducing pipe, the filter is connected with the cooling pipe section, the end part of the cooling pipe section is connected with the lower end of the containment interlayer PCS heat exchanger, one end of the heat pipe section is connected with the air outlet, and the other end of the heat pipe section is connected with the containment interlayer PCS heat exchanger.
2. The quick containment pressure relief system comprises a quick pressure relief pipeline arranged in the lower water space of the integrated heat release trap, and the inlet end of the quick pressure relief pipeline penetrates through the inner shell of the double-layer shell and extends into the air space inside the containment.
3. The automatic pressure relief system comprises an automatic pressure relief pipeline and an automatic pressure relief valve arranged on the automatic pressure relief pipeline, wherein the inlet end of the automatic pressure relief pipeline is communicated with the air cavity of the pressure stabilizer positioned on the main coolant loop, and the outlet end of the automatic pressure relief pipeline extends into the lower water space of the integrated heat release trap.
4. The passive residual heat removal system is arranged on a reactor main coolant loop and comprises an inlet pipeline, a passive residual heat removal heat exchanger and an outlet pipeline which are sequentially connected, valves are arranged on the inlet pipeline and the outlet pipeline, the inlet pipeline is connected with a main coolant loop heat pipe section at the front end of the steam generator, the outlet pipeline is connected with a main coolant loop cold pipe section at the rear end of the steam generator, and the passive residual heat removal heat exchanger is immersed in a lower water space of the integrated heat release trap.
5. The passive low-pressure safety injection system comprises a passive low-pressure safety injection pipeline and a one-way valve, wherein the inlet section of the passive low-pressure safety injection pipeline is positioned in the lower water space of the integrated heat release trap, the outlet section of the passive low-pressure safety injection pipeline is connected to the wall surface of the reactor pressure vessel, and the one-way valve only allows cooling water to flow from the lower water space of the integrated heat release trap to the interior of the reactor pressure vessel.
6. The passive reactor cavity water injection system comprises a reactor cavity water injection pipeline and a one-way water injection valve, wherein the inlet end of the reactor cavity water injection pipeline is immersed in the lower water space of the integrated heat release trap, and the outlet end of the reactor cavity water injection pipeline is connected in an interlayer flow channel formed by the outer wall surface of the reactor pressure vessel and the inner wall surface of the heat insulation layer.
7. The filtering and discharging system comprises a primary washing and filtering system and a secondary filtering and discharging system, the primary washing and filtering system comprises a quick pressure relief pipeline and an integrated heat release trap, the secondary filtering and discharging system comprises a filtering and discharging valve, a filtering and discharging pipeline and a filtering and discharging device, and the end of the filtering and discharging pipeline extends into the air space on the upper part of the containment interlayer and the other end of the filtering and discharging pipeline is connected with the filtering and discharging device.
Compared with the prior art, the invention has the beneficial effects that:
1) The integrated heat release trap designed by the invention fully utilizes the larger space volume of the interlayer area of the double-layer concrete safety shell, and the compact arrangement scheme can avoid arranging a plurality of cooling water sources such as a built-in refueling water tank, a passive reactor cavity water injection tank and the like in the air space in the safety shell and can effectively simplify the arrangement of a reactor system on the basis of ensuring the inherent safety of the reactor.
2) An external natural ventilation type air cooling structure arranged in the non-time-limit passive containment heat exporting system can avoid arranging a large heat exchange water tank outside the containment. Compared with a heat exchange water tank, the natural ventilation type air cooling structure can realize the heat export of the containment without time limit, has good swinging resistance and shock resistance under the condition of ship or earthquake, and has the advantages of small environmental pollution, long service life of equipment, low maintenance cost and the like.
3) The design that the PCS heat exchanger of the containment interlayer is directly positioned above the integrated heat release trap can recycle and reuse the condensed water. The water condensed by the steam falls back into the water space inside the integrated heat release trap, and the recovery and the reutilization of the condensed water are fully realized on the basis of ensuring the heat exchange capability of the heat exchanger.
4) The rapid containment pressure relief system composed of the rapid containment pressure relief pipeline and the integrated heat release trap can effectively resist a first pressure peak value formed in the containment under the condition of a large reactor breach accident, so that the defect that the pressure peak value is relieved by increasing the volume of the containment as much as possible in the existing third-generation pressurized water reactor nuclear power technology is avoided, the volume of the containment is greatly reduced, and the construction cost of the containment is reduced.
5) The integrated heat release trap positioned in the interlayer area of the double-layer concrete safety shell can provide sufficient cooling water source for an automatic pressure release system, a passive residual heat removal system, a passive low-pressure safety injection system and a passive reactor cavity water injection system. Sufficient cooling water in the heat release trap and an external natural ventilation type air cooling structure can replace the existence of the external water tank of the PCS. In addition, the integrated heat release trap with a compact structure is combined with various passive heat removal systems, so that the economy of the nuclear power plant can be improved on the basis of ensuring the safety of the nuclear power plant.
6) The PCS heat exchanger arranged in the non-time-limit passive containment heat exporting system can effectively cope with various accident conditions. Under the condition of a secondary side accident of the steam emitter, the PCS interlayer heat exchanger of the containment can discharge heat in the reactor in combination with the passive waste heat discharge system. Under the condition of a breach accident, the combined action of the PCS heat exchanger of the containment interlayer and the rapid pressure relief system of the containment can effectively cope with two pressure peaks in the containment.
7) The pressure among the integrated heat release trap, the containment interlayer air space and the containment internal air space can be effectively balanced on the basis of ensuring that each system performs a passive safety function by arranging a communication pipeline and a one-way valve which are communicated with the containment internal air space in the containment interlayer.
8) The primary washing filtering system formed by the quick pressure relief pipeline of the containment and the integrated heat release trap water space can realize the residence of most of water-soluble radioactive substances in the operation process, and can effectively reduce the filtering load of the secondary filtering and discharging device.
Drawings
Fig. 1 is an overall structural view of the present invention.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
Because different passive systems in the existing design scheme of the passive safety system of the nuclear power plant have respective cooling water tanks/hot traps, the simplification of system equipment in a containment vessel is not facilitated, and the space in the containment vessel is not fully utilized. In addition, the existing passive containment heat removal system is mainly used for relieving the second pressure peak in the containment under the condition of a breach accident, and an effective scheme is not formed in the aspect of relieving the first pressure peak. The invention is based on the larger available space in the interlayer of the double-layer concrete safety shell, and the integrated heat release trap is arranged in the interlayer air space and can provide a cooling water source for a plurality of passive safety systems, thereby being beneficial to simplifying the system arrangement. The rapid pressure relief system of the containment vessel, which is composed of the rapid pressure relief pipeline and the integrated heat release trap, can effectively resist a first pressure peak value in the containment vessel under a breach accident, so that the volume of the containment vessel can be remarkably reduced, and the construction cost of a nuclear power plant can be reduced.
The invention provides a non-time-limit passive combined heat removal system with an integrated heat release trap, which comprises the integrated heat release trap, a rapid containment pressure relief system, an automatic pressure relief system, a passive waste heat removal system, a passive low-pressure safety injection system, a passive reactor cavity water injection system, a non-time-limit passive containment heat export system (PCS) and a filtering and discharging system.
The integrated heat release trap is positioned at the middle lower part of a double-layer coagulated containment interlayer air space 1, specifically is a large-scale annular pool surrounded by a stainless steel plate or other corrosion-resistant metal plates 2, the inside of the pool is a water space 4, and a communication pipeline 11 and a one-way valve 12 leading to a containment internal air space 10 are arranged on the inner containment wall surface 9 in a containment interlayer upper air space 6. The communication line 11 and one-way valve 12 located in the upper containment compartment gas space 6 only allow gas to vent from the containment compartment gas space 6 to the interior containment gas space 10.
The rapid containment pressure relief system is composed of a rapid pressure relief pipeline 13 and an integrated heat release trap, wherein the inlet end of the pressure relief pipeline 13 is positioned in the air space 10 in the containment, the pipeline penetrates through the wall surface of the inner containment and extends into the air space on the upper part of the containment interlayer, and the outlet end of the pressure relief pipeline is positioned in the water space 4 of the integrated heat release trap.
The automatic pressure relief system consists of an automatic pressure relief pipeline 14, an automatic pressure relief valve 15 and an integrated heat release trap, wherein the inlet end of the automatic pressure relief pipeline 14 is connected to a pressure stabilizer air chamber 16, and the outlet end of the automatic pressure relief pipeline is positioned in the integrated heat release trap water space 4, and the automatic pressure relief system can also be described as follows: the inlet end of the pressure relief pipeline is connected with the top of the reactor pressure stabilizer and communicated with the air cavity inside the pressure stabilizer, the outlet end of the pressure relief pipeline extends into the integrated heat release trap and is immersed in the internal water space, and the automatic pressure relief valve is arranged on the pressure relief pipeline and controlled by the reactor accident alarm signal.
The passive residual heat removal system is preferably arranged in a reactor main coolant loop 17 and consists of an inlet pipeline 18, a valve 19, a passive residual heat removal heat exchanger 20, an outlet pipeline 21 and a valve 22, wherein the inlet pipeline is positioned in a main coolant loop heat pipe section at the front end of the steam generator, the outlet pipeline is positioned in a main coolant loop cold pipe section at the rear end of the steam generator, and the passive residual heat removal heat exchanger is immersed in a water space inside the integrated heat release trap, specifically speaking: the inlet line 18 is connected to the primary-side cooling water circuit hot section 23, and the outlet line 21 is connected to the primary-side cooling water circuit cold section 24. The passive waste heat removal system can also be applied to the secondary side of the steam generator in a similar arrangement mode.
The passive low-pressure safety injection system is composed of an integrated heat release trap, a passive low-pressure safety injection pipeline 25 and a check valve 26, wherein the inlet section of the passive low-pressure safety injection pipeline 25 is located in the water space 4 of the integrated heat release trap, the outlet section of the passive low-pressure safety injection pipeline 25 is connected to the wall surface of a reactor pressure vessel 27, and the check valve 26 only allows cooling water to flow from the water space 4 of the integrated heat release trap to the interior of the reactor pressure vessel 27.
The passive reactor cavity water injection system consists of an integrated heat release trap, a reactor cavity water injection pipeline 28 and a one-way water injection valve 29, wherein the inlet end of the reactor cavity water injection pipeline 28 is immersed in the integrated heat release trap water space 4, and the outlet end of the reactor cavity water injection pipeline is connected in an interlayer flow channel 32 formed by the outer wall surface 30 of the pressure vessel and the inner wall surface 31 of the heat insulation layer.
The non-time-limit passive containment heat exporting system comprises an external natural ventilation type air cooling machine 33, a cooling pipe section 34, a containment interlayer PCS heat exchanger 35 and a heat pipe section 37. The containment sandwich PCS heat exchanger 35 is preferably arranged in a double-layer concrete containment sandwich in a ring shape.
The external natural ventilation type air cooler 33 comprises an umbrella-shaped baffle 36, an air inlet 5, an air outlet 3, a reducer 39 and a filter 38. The umbrella-mounted damper 36 can effectively protect the air-cooling structure in rainy and snowy weather, and the filter 38 can be used for preventing external living things and impurities from entering the air-cooling structure 33.
The filtering and discharging system consists of a containment vessel rapid pressure relief pipeline 13, an integrated heat release trap, a filtering and discharging valve 40, a filtering and discharging pipeline 41 and a filtering and discharging device 42, wherein the inlet end of the filtering and discharging pipeline 41 extends into the air space 6 at the upper part of the containment vessel interlayer, the other end of the filtering and discharging pipeline is connected with the filtering and discharging device 42, the rapid pressure relief pipeline 13 and the integrated heat release trap form a primary washing and filtering system, and the filtering and discharging valve 40, the filtering and discharging pipeline 41 and the filtering and discharging device 42 form a secondary filtering and discharging system.
The method is mainly used for relieving main cooling water loop break accidents, main steam pipeline break accidents, secondary side water supply accidents of the steam generator and the like which may occur in the operation process of the nuclear power plant. Under the condition that the reactor has a loss of coolant accident, particularly a small-break accident, the reactor main coolant loop needs to be subjected to rapid depressurization so that external cooling water can be passively injected into the reactor main coolant loop 17 under the low-pressure condition. Under such accident conditions, the automatic pressure relief system located on the upper portion of the main coolant loop regulator 43 is activated. Under the action of an accident trigger signal, the automatic pressure release valve 16 is opened, and high-temperature steam in the pressure stabilizer air space 16 is introduced into the integrated heat release trap water space 4 through the pressure release pipeline 14 to complete the pressure release process of the main coolant loop. A large amount of cooling water in the integrated heat release trap can effectively contain energy released in the automatic pressure release process. When the pressure in the reactor main coolant loop 17 is reduced to be close to the normal pressure, the passive low-pressure safety injection system is started to operate, and the cooling water in the integrated heat release trap water space 4 is introduced into the reactor pressure vessel 27 through the low-pressure safety injection pipeline 25 to ensure that the reactor core is in a submerged state.
Under the condition of a melting accident, the passive reactor cavity water injection system is started to operate, the one-way valve 29 is automatically opened, and cooling water in the integrated heat release trap water space 4 flows into an interlayer flow channel 32 formed by an outer wall surface 30 of the pressure container and an inner wall surface 31 of a heat insulation layer through the reactor cavity water injection pipeline 29 so as to cool the pressure container 27 and prevent the pressure container from being melted through.
When a primary steam pipe break accident occurs in the steam generator 44 or the water supply system is operating abnormally, the secondary side of the steam generator loses heat removal capability. In order to ensure the effective conduction of the heat of the reactor main cooling water loop 17 under the accident condition, the passive residual heat removal system provided by the invention is started to operate. The isolation valves 19 and 22 of the passive residual heat removal system are automatically opened under the triggering of an accident signal, and the coolant of the heat pipe section 23 of the reactor main cooling water loop enters the heat exchanger 20 of the passive residual heat removal system through the inlet pipeline 18 and returns to the main coolant loop 17 through the outlet pipeline 21 after being cooled. The passive residual heat removal system heat exchanger 20 is immersed in the water space 4 of the integrated heat release trap, and sufficient water capacity in the integrated heat release trap can provide a long-term heat trap for the operation of the passive residual heat removal system.
When a large breach loss of coolant accident occurs in the reactor, a large amount of high-temperature steam is sprayed into the containment gas space 10, so that the pressure in the containment is increased. According to the process of accident development, 2 pressure peak values are formed in the air space in the containment vessel, namely a first pressure peak value with higher amplitude value formed in the containment vessel within tens of seconds in the initial stage of the crevasse spraying, and a second pressure peak value formed in the process of long-term cooling after the reactor core is re-submerged.
The present invention relieves the first pressure spike by a rapid pressure relief system consisting of a rapid pressure relief line 13 and an integrated heat sink. Under the condition of a large-break loss of coolant accident, high-pressure steam-air mixed gas in the containment 10 enters the integrated heat release trap water space 4 through the rapid pressure relief pipeline 13, and cooling water effectively relieves the first pressure peak value of the containment by condensing steam in the mixed gas. In order to balance the pressure between the integrated heat release trap and other gas areas in the long-term development process of an accident, a communication pipeline 11 and a one-way valve 12 which are communicated with the gas space 10 in the containment are arranged on the inner containment wall surface 9 of the gas space 5 on the upper part of the containment interlayer.
Aiming at the second pressure peak value, the invention is provided with a non-time-limit passive containment heat exporting system which is composed of an external natural ventilation type air cooling structure 33, a cooling pipe section 34, a containment interlayer PCS heat exchanger 35 and a heat pipe section 37. Wherein, the containment interlayer PCS heat exchanger 35 is arranged in the interlayer air space 6 between the inner containment 9 and the outer containment 45.
In the long-term development process of accidents, the natural ventilation type air cooling structure 33 is adopted outside the containment, so that no time limit heat conduction can be provided for the containment. When the containment gas space 10 reaches a higher pressure, gas may enter the integrated heat sink water space 4 through the fast pressure relief line 13. Therefore, gas enters the containment interlayer gas space 6, the carried heat is led out through the containment interlayer PCS heat exchanger 35, and condensed water falls back into the integrated heat release trap, so that the recovery and the reutilization of condensed water can be realized.
During the depressurization phase of the containment plenum 10, the pressure of the containment sandwich plenum 6 is higher. When a certain pressure difference is formed between the containment interlayer air space 6 and the containment internal air space 10, the air in the containment interlayer is discharged to the containment internal air space 10 through the communication pipeline 11 of the containment interlayer upper air space 6 and the one-way valve 12, and finally the pressure balance between the containment interlayer air space 6 and the containment internal air space 10 is realized.
In the event of an unexpected accident condition that leads to an excessive pressure inside the containment gas space 10, the filtered venting valve 40 opens upon the initiation of a containment high pressure signal and the containment filtered venting system starts to operate. The high-temperature high-pressure gas with radioactive substances in the containment gas space 10 firstly enters a primary water washing and filtering system formed by a quick pressure relief pipeline 13 and the integrated heat release trap, and most of the water-soluble radioactive substances are retained in the water space 4 of the integrated heat release trap in the process. After the first-stage washing and filtering, the mixed gas enters the containment interlayer gas space 6 from the integrated heat release trap, and then enters the filtering and discharging device 42 through the filtering and discharging pipeline 41, so that the gas subjected to radioactive filtering is finally discharged to the external environment.
In summary, an object of the present invention is to provide a non-time-limited passive combined heat removal system with an integrated heat release well, which mainly comprises the integrated heat release well, a rapid containment pressure release system, an automatic pressure release system, a passive residual heat removal system, a passive low-pressure safety injection system, a passive reactor cavity water injection system, a non-time-limited passive containment heat export system (PCS), and a filtering and discharging system. The integrated heat release trap is used as a key cold source under various reactor accidents and is arranged at the middle lower part of the annular interlayer of the double-layer concrete containment, and the bottom and the side surfaces of the integrated heat release trap are enclosed into a large-scale annular water pool by adopting stainless steel plates. The non-time-limit passive containment heat exporting system consists of an external natural ventilation type air cooling structure, a heat exchanger arranged in an upper air space of a double-layer concrete containment interlayer, and inlet and outlet pipelines. Under the conditions of loss of coolant accident of the reactor and failure of the secondary side of the steam generator, the integrated heat release trap can provide a heat release heat trap for the automatic pressure release system and the passive residual heat removal system heat exchanger, and provide a sufficient cooling water source for the passive low-pressure safety injection system and the passive reactor cavity water injection system. Under the condition of serious accidents caused by large-break-port loss-of-coolant accidents, the first pressure peak value in the containment can be effectively resisted by combining the integrated heat release trap with the rapid pressure release pipeline of the containment, and the second pressure peak value in the containment can be effectively relieved and radioactive residence can be realized under the combined action of the non-time-limit passive containment heat export system and the filtering and discharging device. The design of the integrated heat release trap and the non-time-limit passive containment heat exporting system fully utilizes the interlayer space of the double-layer concrete containment, can provide sufficient cold sources for various passive safety systems, is favorable for greatly reducing the volume of the containment gas space, has strong shock resistance, can export the heat in the containment without time limit, and further provides a feasible scheme for improving the economy and the passive safety of the advanced nuclear power plant.
Claims (8)
1. A non-time-limited passive combined heat removal system with an integrated heat release trap is characterized in that: the integrated heat release trap is an annular water pool surrounded by corrosion-resistant metal plates, at least one group of communication pipelines and one-way valves leading to the internal gas space of the containment are arranged on the inner containment wall surface of the gas space on the upper part of the containment interlayer, and the integrated heat release trap is connected with a rapid containment pressure release system, an automatic pressure release system, a passive residual heat discharge system, a passive low-pressure passive reactor injection system, a passive reactor cavity water injection system and a filtering and discharging system, wherein the number of the rapid containment pressure release system, the automatic pressure release system, the passive residual heat discharge system, the passive low-pressure passive reactor injection system, the passive reactor cavity water injection system and the filtering and discharging system is the same as the number of the communication pipelines and the one-way valve groups leading to the internal gas space; the integrated heat release trap and the non-time-limit passive containment heat derivation system are combined to effectively resist a first pressure peak in the containment according to the process of accident development, and effectively relieve a second pressure peak in the containment and realize radioactive residence under the combined action of the integrated heat release trap, the non-time-limit passive containment heat derivation system and the filtering and discharging system.
2. A non-time-limited passive combined heat removal system with integrated heat sink according to claim 1, wherein: the number of the non-time-limit passive containment heat leading-out systems is the same as that of communication pipelines and check valve groups leading to a containment internal air space, a containment interlayer PCS heat exchanger is arranged in a double-layer concrete containment interlayer, an external natural ventilation type air cooler comprises an umbrella-mounted baffle, an air inlet, an air outlet, a reducing pipe and a filter, the filter is connected with a cold pipe section, the end part of the cold pipe section is connected with the lower end of the containment interlayer PCS heat exchanger, one end of the hot pipe section is connected with the air outlet, and the other end of the hot pipe section is connected with the containment interlayer PCS heat exchanger.
3. A non-time-limited passive combined heat rejection system with integrated heat rejection trap according to claim 1 or 2, characterized in that: the quick pressure relief system of the containment comprises a quick pressure relief pipeline arranged in the lower water space of the integrated heat release trap, and the inlet end of the quick pressure relief pipeline penetrates through the inner shell of the double-layer shell and extends into the air space inside the containment.
4. A non-time-limited passive combined heat removal system with integrated heat sink according to claim 3, wherein: the automatic pressure relief system comprises an automatic pressure relief pipeline and an automatic pressure relief valve arranged on the automatic pressure relief pipeline, wherein the inlet end of the automatic pressure relief pipeline is communicated with the air cavity of the pressure stabilizer on the main coolant loop, and the outlet end of the automatic pressure relief pipeline extends into the lower water space of the integrated heat release trap.
5. A non-time-limited passive combined heat rejection system with integrated heat release traps according to claim 1 or 4, characterized in that: the passive residual heat removal system is arranged on a reactor main coolant loop and comprises an inlet pipeline, a passive residual heat removal heat exchanger and an outlet pipeline which are sequentially connected, valves are arranged on the inlet pipeline and the outlet pipeline, the inlet pipeline is connected with a main coolant loop heat pipe section at the front end of the steam generator, the outlet pipeline is connected with a main coolant loop cold pipe section at the rear end of the steam generator, and the passive residual heat removal heat exchanger is immersed in a lower water space of the integrated heat release trap.
6. A non-time-limited passive combined heat removal system with integrated heat release traps according to claim 5, characterized in that: the passive low-pressure safety injection system comprises a passive low-pressure safety injection pipeline and a one-way valve, wherein the inlet section of the passive low-pressure safety injection pipeline is positioned in the lower water space of the integrated heat release trap, the outlet section of the passive low-pressure safety injection pipeline is connected to the wall surface of the reactor pressure vessel, and the one-way valve only allows cooling water to flow from the lower water space of the integrated heat release trap to the interior of the reactor pressure vessel.
7. A non-time-limited passive combined heat rejection system with integrated heat rejection trap according to claim 1 or 6, characterized in that: the passive reactor cavity water injection system comprises a reactor cavity water injection pipeline and a one-way water injection valve, wherein the inlet end of the reactor cavity water injection pipeline is immersed in the lower water space of the integrated heat release trap, and the outlet end of the reactor cavity water injection pipeline is connected in an interlayer flow channel formed by the outer wall surface of the reactor pressure vessel and the inner wall surface of the heat insulation layer.
8. A non-time-limited passive combined heat removal system with integrated heat sink according to claim 7, wherein: the filtering and discharging system comprises a primary washing and filtering system and a secondary filtering and discharging system, the primary washing and filtering system comprises a quick pressure relief pipeline and an integrated heat release trap, the secondary filtering and discharging system comprises a filtering and discharging valve, a filtering and discharging pipeline and a filtering and discharging device, and the end of the filtering and discharging pipeline extends into the air space on the upper part of the containment interlayer and the other end of the filtering and discharging pipeline is connected with the filtering and discharging device.
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