CN112071454A - Passive combined heat removal system with integrated heat release trap - Google Patents
Passive combined heat removal system with integrated heat release trap Download PDFInfo
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- CN112071454A CN112071454A CN202010965740.4A CN202010965740A CN112071454A CN 112071454 A CN112071454 A CN 112071454A CN 202010965740 A CN202010965740 A CN 202010965740A CN 112071454 A CN112071454 A CN 112071454A
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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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/093—Concrete vessels
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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
- G21C15/243—Promoting flow of the coolant for liquids
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
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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 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 pipelines and one-way valves for communicating the integrated heat release trap with the containment internal air space are arranged on the top wall surface of the integrated heat release trap, 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. The invention simplifies the reactor system arrangement of the nuclear power plant, reduces the volume of the safety shell and provides a feasible scheme for improving the economy and passive safety of the advanced nuclear power plant.
Description
Technical Field
The invention relates to a passive safety system in an advanced nuclear power plant, in particular to a 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 during the operation of nuclear power plants, the safety of the nuclear power plants is always highly concerned by the people in the industry, particularly by developers.
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 the 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 the third generation nuclear power generating units.
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 these systems can effectively resist nuclear power plant blackout accidents and provide operators with 72 hours of non-intervention time.
With respect to advanced nuclear power technology, prior patents disclose passive safety systems. The patents with publication numbers of CN111128414A and CN111383782A provide a plurality of passive safety systems, including a passive containment heat removal system, a secondary-side passive residual heat removal system, and a passive safety injection system, the patents with publication numbers of CN209149827U and CN110021447A provide passive secondary-side residual heat removal systems, and the patents 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 tanks/reservoirs at different spatial locations inside/outside the containment, which is detrimental to the simplification of the complex circuits of the nuclear power plant and the reduction of construction costs.
In the aspect of containment heat derivation, according to the process of accident development, 2 pressure peak values are formed in the air space in the containment, namely a first pressure peak value with higher amplitude is formed in the containment within tens of seconds at the initial stage of large-crevasse blowing, and a second pressure peak value is formed in the process of long-term cooling after the reactor core is submerged again. 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 two points: firstly, how to effectively deal with the first pressure peak value of a large breach accident under the condition of smaller containment volume; and secondly, how to simplify the system arrangement and reduce the equipment redundancy by effectively integrating heat release traps of different passive systems.
Therefore, it is necessary to invent a passive combined heat removal system with an integrated heat release trap to simplify the arrangement of a reactor system, reduce the volume of a safety shell, reduce the volume of a replacement hot water tank outside a PCS and the water load, and finally provide a feasible scheme for the economy and passive safety of an advanced nuclear power plant.
Disclosure of Invention
The invention aims to provide a 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 and providing a feasible scheme for improving the economy and passive safety of an advanced nuclear power plant.
The purpose of the invention is realized as follows: the integrated heat release trap is arranged at the middle lower part of the double-layer coagulated containment interlayer air space, the integrated heat release trap is an annular water pool surrounded by corrosion-resistant metal plates, at least one group of pipelines and one-way valves for communicating the integrated heat release trap with the containment internal air space are arranged on the top wall surface of the integrated heat release trap, the integrated heat release trap is connected with a containment rapid 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 and a filtering and discharging system, and the number of the containment rapid pressure release system, the automatic pressure release system, the passive residual heat removal system, the passive low-pressure safety injection system, the passive reactor cavity water injection system and the filtering and discharging system is the same as the number of the pipelines and the one-way valve groups for communicating the integrated heat release trap with the containment internal air space.
The invention also includes such structural features:
1. the passive containment heat exporting system comprises heat exchangers which are respectively arranged in a double-layer coagulated containment interlayer and in the containment, the inlet end of each heat exchanger is connected with an inlet isolation valve and a cold pipe section, the outlet end of each heat exchanger is connected with an outlet isolation valve and a heat pipe section, and the end part of each cold pipe section and the end part of each heat pipe section are communicated with an external heat exchange water tank of the containment.
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) 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.
3) 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 can cut down the volume and the water storage capacity of the external water tank of the PCS in practice. 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.
4) The PCS heat exchanger arranged in the passive containment heat exporting system and the PCS heat exchanger arranged in the containment interlayer 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 arranged in the containment vessel, the PCS heat exchanger arranged in the containment vessel interlayer and the rapid containment vessel pressure relief system can effectively cope with two pressure peaks in the containment vessel.
5) The pressure among the heat release trap, the air space of the safety shell interlayer and the air space inside the safety shell can be effectively balanced on the basis of ensuring that each system performs a passive safety function by arranging the communication pipeline and the one-way valve which are communicated with the air space on the upper part of the safety shell interlayer on the wall surface of the top of the air space of the heat release trap and arranging the communication pipeline and the one-way valve which are communicated with the air space inside the safety shell on the upper part of the safety shell interlayer.
6) 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 a schematic view of the overall structure of the present invention;
FIG. 2 is a schematic illustration of the series mode of operation of the present invention;
FIG. 3 is a schematic diagram of the single loop stand alone operation 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 passive combined heat removal system with an integrated heat release trap, which comprises the integrated heat release trap, a rapid containment 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, a passive containment heat export system (PCS) and a filtering discharge 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 water pool surrounded by a stainless steel plate or other corrosion-resistant metal plates 2, the interior of the large-scale annular water pool is divided into an upper air space 3 and a lower water space 4, a communication pipeline 7 and a one-way valve 8 which are communicated with the upper air space 6 of the containment interlayer are arranged on the top wall surface 5 of the upper air space 3 of the heat release trap, and a communication pipeline 11 and a one-way valve 12 which are communicated with the inner air space 10 of the containment interlayer are arranged on the inner containment wall surface 9 in the upper air space 6 of the containment. The communication pipeline 7 and the one-way valve 8 positioned at the top of the gas space only allow gas to be discharged from the integrated heat release trap gas space 3 to the upper gas space 6 of the containment interlayer, and the communication pipeline 11 and the one-way valve 12 positioned at the upper gas space 6 of the containment interlayer only allow gas to be discharged from the containment interlayer gas space 6 to the inner gas space 10 of the containment.
The rapid pressure relief system of the containment comprises 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 an air space 10 in the containment, the pipeline penetrates through the wall surface of the inner containment and extends into the air space of the integrated heat release trap, and the outlet end of the pressure relief pipeline is positioned in a water space 4 below 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 water space 4 below the integrated heat release trap. This 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 an 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 a reactor accident alarm signal.
The passive residual heat removal system is preferably arranged in a reactor main coolant loop 17 and comprises 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 arranged at a main coolant loop heat pipe section at the front end of the steam generator, the outlet pipeline is arranged at 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 residual 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 one-way 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 one-way 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 a reactor pressure vessel and the inner wall surface 31 of a heat insulation layer.
The passive containment heat exporting system comprises an external containment heat exchange water tank 33, a cold pipe section 34, a containment interlayer PCS heat exchanger 35, an internal containment PCS heat exchanger 36, a heat pipe section 37, an inlet isolation valve 38 and an outlet isolation valve 39. The in-containment PCS heat exchanger 36 and the in-containment sandwich PCS heat exchanger 35 can form a parallel operation mode or a series operation mode together with the PCS cold pipe section 34 and the heat pipe section 37. The PCS heat exchanger 36 arranged in the containment can form single-loop independent operation with the cold and hot pipe sections 34 and 37, and can also form double-loop combined operation with the containment interlayer heat exchanger 35.
The filtering and discharging system consists of a containment 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 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 15 is opened, and high-temperature steam in the gas space 16 of the pressure stabilizer is introduced into the water space 4 of the integrated heat release trap 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 molten pile accident, the passive pile cavity water injection system is started to operate, the check 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 pile 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 passive residual heat removal system isolation valves 19 and 22 are automatically opened under the triggering of an accident signal, the coolant of the reactor main cooling water loop heat pipe section 23 enters the passive residual heat removal system heat exchanger 20 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 vessel is increased. According to the development process of accidents, 2 pressure peak values are formed in the air space in the containment, namely a first pressure peak value with higher amplitude is formed in the containment within tens of seconds at the initial stage of the blowout of the breach, and a second pressure peak value is formed in the process of long-term cooling after the reactor core is submerged again.
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 7 and a one-way valve 8 which are communicated with an upper gas space 6 of a containment interlayer are arranged on the top wall surface 5 of a gas space 3 of the heat release trap, and a communication pipeline 11 and a one-way valve 12 which are communicated with an inner gas space 10 of the containment interlayer are arranged on the inner containment wall surface 9 of the upper gas space 5 of the containment interlayer.
Aiming at the second pressure peak value, the passive containment heat exporting system is arranged and consists of a containment external heat exchange water tank 33, a cold pipe section 34, a containment interlayer PCS heat exchanger 35, a containment internal PCS heat exchanger 36, a heat pipe section 37, an inlet isolation valve 38 and an outlet isolation valve 39. The in-containment heat exchanger 36 is arranged in the in-containment gas space 10, the in-containment interlayer PCS heat exchanger 35 is arranged in the interlayer gas space 6 between the inner containment 9 and the outer containment 45, and the in-containment PCS heat exchanger 36 and the in-containment interlayer PCS heat exchanger 35 can form a parallel operation mode (as shown in figure 1) or a series operation mode (as shown in figure 2) with the PCS cold and hot pipe sections 34 and 37. The PCS heat exchanger 36 arranged in the containment can form single-loop independent operation with the cold and hot pipe sections 34 and 37 (as shown in figure 3), and can also form double-loop combined operation with the containment interlayer heat exchanger 35 (as shown in figure 1).
During the long-term development of an accident, the in-containment PCS heat exchanger 36 relieves the increase in pressure in the containment by condensing the vapor in the in-containment gas space 10 during the pressurization phase of the containment gas space 10. Under the action of higher pressure in the containment gas space 10, gas enters the integrated heat release trap water space 4 through the rapid pressure relief pipeline 13. When a certain pressure difference is formed between the integrated heat release trap air space 3 and the containment interlayer air space 6, mixed air in the air space enters the containment interlayer air space 6 through a communication pipeline 7 and a one-way valve 8 on the top wall surface of the heat release trap air space 3, and carried heat is led out through a containment interlayer PCS heat exchanger 35.
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 gas 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. Similarly, under the action of a certain pressure difference, the gas in the integrated heat release trap gas space 3 enters the containment interlayer gas space 6 through the communication pipeline 7 and the one-way valve 8 which are positioned on the top wall surface of the integrated heat release trap gas space 3, and finally the pressure balance between the containment interlayer gas space 6 and the containment internal gas space 10 is realized.
In the event of an unexpected accident condition, which leads to an excessive pressure in the interior of the containment gas space 10, the filtered venting valve 40 is opened, which initiates the containment high-pressure signal and the containment filtered venting system is started. 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 through the communication pipeline 7 and the one-way valve 8 which are positioned on the top wall surface 5 of the integrated heat release trap gas space 3, and then enters the filtering and discharging device 42 through the filtering and discharging pipeline 41, and finally the gas subjected to radioactive filtering is discharged to the external environment.
In summary, an object of the present invention is to provide a passive combined heat removal system with an integrated heat release well, which mainly comprises an integrated heat release well, a rapid pressure relief system for containment, an automatic pressure relief system, a passive residual heat removal system, a passive low-pressure safety injection system, a passive reactor cavity water injection system, a passive containment heat export system (PCS), and a filtering discharge system. The integrated heat release trap is used as a key cold source under various reactor accidents, is arranged at the middle lower part of the annular interlayer of the double-layer concrete containment, is surrounded by stainless steel plates to form a large-scale annular water pool, and is internally divided into a lower water space and an upper gas space. 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 severe accident condition caused by a large-breach loss of coolant accident, the integrated heat release trap is combined with the rapid pressure relief pipeline of the containment vessel to effectively resist a first pressure peak value in the containment vessel, and the integrated heat release trap and the PCS system and the filtering and discharging device jointly act to effectively relieve a second pressure peak value in the containment vessel and realize the radioactive residence. The design of the integrated heat release trap fully utilizes the interlayer space of the double-layer concrete containment vessel, can provide sufficient cold sources for various passive safety systems, is favorable for greatly reducing the volume of the gas space of the containment vessel and the volume and the water charge of the PCS external replacement hot water tank, and further provides a feasible scheme for improving the economy and the passive safety of the advanced nuclear power plant.
Claims (8)
1. A passive combined heat removal system with integrated heat release traps, characterized by: the integrated heat release trap is arranged at the middle lower part of the double-layer coagulated containment interlayer air space, the integrated heat release trap is an annular water pool surrounded by corrosion-resistant metal plates, at least one group of pipelines and one-way valves for communicating the integrated heat release trap with the containment internal air space are arranged on the top wall surface of the integrated heat release trap, the integrated heat release trap is connected with a containment rapid 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 and a filtering and discharging system, and the number of the containment rapid pressure release system, the automatic pressure release system, the passive residual heat removal system, the passive low-pressure safety injection system, the passive reactor cavity water injection system and the filtering and discharging system is the same as the number of the pipelines and the one-way valve groups for communicating the integrated heat release trap with the containment internal air space.
2. A passive combined heat removal system with integrated heat release trap according to claim 1, characterized in that: the passive containment heat exporting system comprises heat exchangers which are respectively arranged in a double-layer coagulated containment interlayer and in the containment, the inlet end of each heat exchanger is connected with an inlet isolation valve and a cold pipe section, the outlet end of each heat exchanger is connected with an outlet isolation valve and a heat pipe section, and the end part of each cold pipe section and the end part of each heat pipe section are communicated with an external heat exchange water tank of the containment.
3. A passive combined heat removal system with integrated heat release trap according to claim 1 or 2, characterized in that: 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.
4. A passive combined heat removal system with integrated heat release trap according to claim 3, characterized in that: 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.
5. A passive combined heat removal system with integrated heat release trap 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 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 passive combined heat removal system with integrated heat release 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 passive combined heat removal system with integrated heat release traps according to claim 7, characterized in that: 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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Cited By (3)
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| CN112820425A (en) * | 2021-02-08 | 2021-05-18 | 上海核工程研究设计院有限公司 | Systematic passive special safety system suitable for multipurpose reactor |
| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
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