CA2954136A1 - Containment cooling system and containment and reactor pressure vessel joint cooling system - Google Patents
Containment cooling system and containment and reactor pressure vessel joint cooling system Download PDFInfo
- Publication number
- CA2954136A1 CA2954136A1 CA2954136A CA2954136A CA2954136A1 CA 2954136 A1 CA2954136 A1 CA 2954136A1 CA 2954136 A CA2954136 A CA 2954136A CA 2954136 A CA2954136 A CA 2954136A CA 2954136 A1 CA2954136 A1 CA 2954136A1
- Authority
- CA
- Canada
- Prior art keywords
- containment
- water
- cooling
- cooler
- cooling system
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 238000001816 cooling Methods 0.000 title claims abstract description 143
- 239000000498 cooling water Substances 0.000 claims abstract description 78
- 238000002955 isolation Methods 0.000 claims abstract description 40
- 230000000630 rising effect Effects 0.000 claims abstract description 17
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 187
- 238000002347 injection Methods 0.000 claims description 26
- 239000007924 injection Substances 0.000 claims description 26
- 238000009825 accumulation Methods 0.000 claims description 19
- 238000004891 communication Methods 0.000 claims description 9
- 238000012546 transfer Methods 0.000 claims description 9
- 230000001105 regulatory effect Effects 0.000 claims description 3
- 230000007774 longterm Effects 0.000 abstract description 8
- 238000013461 design Methods 0.000 description 12
- 230000007423 decrease Effects 0.000 description 4
- 239000000155 melt Substances 0.000 description 4
- 239000000243 solution Substances 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 239000000941 radioactive substance Substances 0.000 description 3
- 230000018044 dehydration Effects 0.000 description 2
- 238000006297 dehydration reaction Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 230000008020 evaporation Effects 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention provides a containment cooling system and a containment and reactor pressure vessel joint cooling system, wherein the containment cooling system is mainly formed by connecting an internal heat exchanger (1), a rising pipeline (2), a falling pipeline (3), isolation valves (4, 5), a cooling water tank (6) and an air cooling condenser-cooler (7). The containment and reactor pressure vessel joint cooling system includes the containment cooling system and a reactor pressure vessel cooling system. The cooling system does not need to power provided externally, and can provide long-term effective cooling for a containment and a reactor pressure vessel at the same time in the case of an accident, thereby ensuring that when the accident occurs, under the condition of no human intervention and no input of other external cooling measures, the reactor containment and the pressure vessel are always in a safe state.
Description
CONTAINMENT COOLING SYSTEM AND CONTAINMENT
AND REACTOR PRESSURE VESSEL JOINT COOLING
SYSTEM
Technical Field The present invention relates to a containment cooling system, and also relates to a containment and reactor pressure vessel joint cooling system, which belong to the field of nuclear safety and thermal hydraulic technology.
Background A containment and a reactor pressure vessel are both important safety barriers for preventing the leakage of a radioactive substance in the case of an accident of a nuclear power plant. In the case of LOCA, MSLB and other serious accidents, the containment will be quickly filled with a large amount of steam so as to result in a sharp rise of the temperature and the pressure in the containment. Once the temperature and the pressure exceed a design allowable range, the containment may be damaged, resulting in the leakage of the radioactive substance; and meanwhile, the cooling capacity of a reactor core drops significantly because of severe dehydration.
Once the reactor core is melt down, the melt may collapse to a lower seal head of the pressure vessel, and if the lower seal head is burnt through by excessive heat load, the integrity of the containment will be seriously threatened, resulting in the leakage of the melt of the reactor core. Therefore, to ensure the safety of the nuclear power plant, it is necessary to set up a special system for cooling the containment and the reactor pressure vessel.
At present, design solutions of some cooling systems are proposed for a double-layer concrete containment and the reactor pressure vessel.
The solution proposed for the concrete containment mainly includes internally arranging a heat exchanger and removing heat in a natural circulation mode by a height difference of an external water tank and the internal heat exchanger, but a lot of water in the water tank will be evaporated at the same time. (C S Byun, D W
Jerng, N
E Todreas, et al. Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment. Nuclear Engineering and Design, 2000,199:227-242; S J Cho, B S Kim, M G Kang et at. The development of passive design features for the Korean Next Generation Reactor. Nuclear Engineering and Design, 2000,201: 259-271; S W Lee, W P Baek, S H Chang. Assessment of passive containment cooling concepts for advanced pressurized water reactors. Ann.
Nucl.
Energy, 1997, 24(6):467-475). Therefore, the above designs of the containment heat removal system have a major issue, that is, the temperature and the pressure of the containment can be only guaranteed to not exceed the design reference within a certain period of time, the longest cooling time of 72 hours is provided, and if the time limit is exceeded, the system will become invalid as the water in the water tank is used up. After 72 hours, water needs to be injected into the water tank by external power, and then the system plays the same role again. In order to extend the cooling time in the absence of human intervention, one can only further increase the volume of the water tank, but the influence brought by an earthquake will be greatly increased due to the increase of the volume of the water tank.
External reactor cooling systems proposed for the reactor pressure vessel almost simultaneously adopt active and passive water injection ways, such as technical solutions disclosed in patent documents with Publication Nos.CN201681637, CN203366760U and CN202887747U, as well as Nos.CN103632736A, CN102163469A, CN103310856A and the like. However, the external reactor cooling systems in the aforementioned design have a common drawback, that is, the utilization rate of the cooling water is relatively low. After a reactor pit is filled with water, a water injection system will still continue to inject water (no matter large or small flow) if a water valve or a control valve in a passive system is not manually closed, and water will overflow from the pit to cause waste. Therefore, in order to ensure an adequate cooling time, in the absence of human intervention, the water tank of the aforementioned passive cooling system needs to provide a large water storage capacity, which will significantly increase the volume of the water tank. If the water injection flow is too small, the water level in the reactor pit may be reduced, and even the reactor pressure vessel cannot be completely submerged, such that the reactor pressure vessel cannot be sufficiently cooled, thus threatening the integrity of the reactor pressure vessel. Therefore, if it is expected to provide continuous cooling for
AND REACTOR PRESSURE VESSEL JOINT COOLING
SYSTEM
Technical Field The present invention relates to a containment cooling system, and also relates to a containment and reactor pressure vessel joint cooling system, which belong to the field of nuclear safety and thermal hydraulic technology.
Background A containment and a reactor pressure vessel are both important safety barriers for preventing the leakage of a radioactive substance in the case of an accident of a nuclear power plant. In the case of LOCA, MSLB and other serious accidents, the containment will be quickly filled with a large amount of steam so as to result in a sharp rise of the temperature and the pressure in the containment. Once the temperature and the pressure exceed a design allowable range, the containment may be damaged, resulting in the leakage of the radioactive substance; and meanwhile, the cooling capacity of a reactor core drops significantly because of severe dehydration.
Once the reactor core is melt down, the melt may collapse to a lower seal head of the pressure vessel, and if the lower seal head is burnt through by excessive heat load, the integrity of the containment will be seriously threatened, resulting in the leakage of the melt of the reactor core. Therefore, to ensure the safety of the nuclear power plant, it is necessary to set up a special system for cooling the containment and the reactor pressure vessel.
At present, design solutions of some cooling systems are proposed for a double-layer concrete containment and the reactor pressure vessel.
The solution proposed for the concrete containment mainly includes internally arranging a heat exchanger and removing heat in a natural circulation mode by a height difference of an external water tank and the internal heat exchanger, but a lot of water in the water tank will be evaporated at the same time. (C S Byun, D W
Jerng, N
E Todreas, et al. Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment. Nuclear Engineering and Design, 2000,199:227-242; S J Cho, B S Kim, M G Kang et at. The development of passive design features for the Korean Next Generation Reactor. Nuclear Engineering and Design, 2000,201: 259-271; S W Lee, W P Baek, S H Chang. Assessment of passive containment cooling concepts for advanced pressurized water reactors. Ann.
Nucl.
Energy, 1997, 24(6):467-475). Therefore, the above designs of the containment heat removal system have a major issue, that is, the temperature and the pressure of the containment can be only guaranteed to not exceed the design reference within a certain period of time, the longest cooling time of 72 hours is provided, and if the time limit is exceeded, the system will become invalid as the water in the water tank is used up. After 72 hours, water needs to be injected into the water tank by external power, and then the system plays the same role again. In order to extend the cooling time in the absence of human intervention, one can only further increase the volume of the water tank, but the influence brought by an earthquake will be greatly increased due to the increase of the volume of the water tank.
External reactor cooling systems proposed for the reactor pressure vessel almost simultaneously adopt active and passive water injection ways, such as technical solutions disclosed in patent documents with Publication Nos.CN201681637, CN203366760U and CN202887747U, as well as Nos.CN103632736A, CN102163469A, CN103310856A and the like. However, the external reactor cooling systems in the aforementioned design have a common drawback, that is, the utilization rate of the cooling water is relatively low. After a reactor pit is filled with water, a water injection system will still continue to inject water (no matter large or small flow) if a water valve or a control valve in a passive system is not manually closed, and water will overflow from the pit to cause waste. Therefore, in order to ensure an adequate cooling time, in the absence of human intervention, the water tank of the aforementioned passive cooling system needs to provide a large water storage capacity, which will significantly increase the volume of the water tank. If the water injection flow is too small, the water level in the reactor pit may be reduced, and even the reactor pressure vessel cannot be completely submerged, such that the reactor pressure vessel cannot be sufficiently cooled, thus threatening the integrity of the reactor pressure vessel. Therefore, if it is expected to provide continuous cooling for
2 the pressure vessel without causing additional loss of the cooling water, the cooling system (no matter the active system or the passive system) needs to be continuously adjusted or started and stopped manually, which brings great difficulty for the actual operation of the system.
In addition, the aforementioned solutions are only proposed for the double-layer concrete containment or the reactor pressure vessel, the double-layer concrete containment and the reactor pressure vessel are independent from each other.
However, in the case of serious accidents, cooling of the containment and the reactor pressure vessel needs to be provided at the same time generally, and if the two systems run independently, the condensed water produced by the internal heat exchanger is lost in vain.
Summary The object of the present invention is to provide a containment cooling system, which does not require power externally provided, consumes little cooling water and can realize long-term cooling for the interior of a containment. The object of the present invention is to further provide a containment and reactor pressure vessel joint cooling system, which can simultaneously provide long-term effective cooling for the containment and a reactor pressure vessel in an accident working condition to enable the reactor containment and the pressure vessel to be in a safe state all the time.
The containment cooling system of the present invention includes an internal heat exchanger, a rising pipeline, a falling pipeline, isolation valves, a cooling water tank and an air cooling condenser-cooler, wherein the internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment, the cooling water tank is located on an outer side of an outer layer concrete containment, a relative position of the cooling water tank is higher than that of the internal heat exchanger, the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop, the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, the other part is
In addition, the aforementioned solutions are only proposed for the double-layer concrete containment or the reactor pressure vessel, the double-layer concrete containment and the reactor pressure vessel are independent from each other.
However, in the case of serious accidents, cooling of the containment and the reactor pressure vessel needs to be provided at the same time generally, and if the two systems run independently, the condensed water produced by the internal heat exchanger is lost in vain.
Summary The object of the present invention is to provide a containment cooling system, which does not require power externally provided, consumes little cooling water and can realize long-term cooling for the interior of a containment. The object of the present invention is to further provide a containment and reactor pressure vessel joint cooling system, which can simultaneously provide long-term effective cooling for the containment and a reactor pressure vessel in an accident working condition to enable the reactor containment and the pressure vessel to be in a safe state all the time.
The containment cooling system of the present invention includes an internal heat exchanger, a rising pipeline, a falling pipeline, isolation valves, a cooling water tank and an air cooling condenser-cooler, wherein the internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment, the cooling water tank is located on an outer side of an outer layer concrete containment, a relative position of the cooling water tank is higher than that of the internal heat exchanger, the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop, the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, the other part is
3 arranged in a steam space, an air side inlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to a bottom surface and communicates an external atmospheric environment with a lower seal head of the air cooling condenser-cooler by a pipeline, and an air side outlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to an upper surface and communicates an upper seal head of the air cooling condenser-cooler with an annular space formed by the inner layer concrete containment and the outer layer concrete containment by a pipeline.
The containment cooling system of the present invention can further include:
1. a water seal device is connected to the side wall of the cooling water tank, an upper connecting tube of the water seal device is communicated with the air space of the cooling water tank, a lower connecting tube of the water seal device is communicated with the water space of the cooling water tank, and the upper connecting tube and the lower connecting tube are in bridge connection by a pipeline.
2. Internal and external isolation valve sets are arranged on both of the rising pipeline and the falling pipeline.
The containment and reactor pressure vessel joint cooling system of the present invention includes a containment cooling system and a reactor pressure vessel cooling system; the containment cooling system includes an internal heat exchanger, a rising pipeline, a falling pipeline, isolation valves, a cooling water tank and an air cooling condenser-cooler, wherein the internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment, the cooling water tank is located on an outer side of an outer layer concrete containment, a relative position of the cooling water tank is higher than that of the internal heat exchanger, the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop, the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, the other part is arranged in a steam space, an air side inlet of the air cooling condenser-cooler is formed in a position on
The containment cooling system of the present invention can further include:
1. a water seal device is connected to the side wall of the cooling water tank, an upper connecting tube of the water seal device is communicated with the air space of the cooling water tank, a lower connecting tube of the water seal device is communicated with the water space of the cooling water tank, and the upper connecting tube and the lower connecting tube are in bridge connection by a pipeline.
2. Internal and external isolation valve sets are arranged on both of the rising pipeline and the falling pipeline.
The containment and reactor pressure vessel joint cooling system of the present invention includes a containment cooling system and a reactor pressure vessel cooling system; the containment cooling system includes an internal heat exchanger, a rising pipeline, a falling pipeline, isolation valves, a cooling water tank and an air cooling condenser-cooler, wherein the internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment, the cooling water tank is located on an outer side of an outer layer concrete containment, a relative position of the cooling water tank is higher than that of the internal heat exchanger, the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop, the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, the other part is arranged in a steam space, an air side inlet of the air cooling condenser-cooler is formed in a position on
4 the side wall of the water tank close to a bottom surface and communicates an external atmospheric environment with a lower seal head of the air cooling condenser-cooler by a pipeline, and an air side outlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to an upper surface and communicates an upper seal head of the air cooling condenser-cooler with an annular space formed by the inner layer concrete containment and the outer layer concrete containment by a pipeline; and the reactor pressure vessel cooling system includes a water storage tank, a pressure balance tube, a water injection tube, an isolation pool, a control valve, a communication tube, a condensate collection pool, a water accumulation tank and an exhaust tube, the water storage tank is located above the isolation pool, the water storage tank is connected with the isolation pool by the pressure balance tube and the water injection tube, the isolation pool is connected with a reactor pit by the communication tube, a reactor pressure vessel is located in the reactor pit, the condensate collection pool is located below the internal heat exchanger, and the condensate collection pool is sequentially connected with the water accumulation tank, a regulating valve and the isolation pool through a pipeline.
The containment and reactor pressure vessel joint cooling system of the present invention can further include:
1. An upper end of the pressure balance tube is located in the air space of the water storage tank, and the relative position of a lower end of the pressure balance tube is higher than the upper edge of the reactor pressure vessel.
2. The upper end of the water injection tube is connected with the lowest point of the water storage tank, and the relative position of the lower end of the water injection tube is lower than the lower edge of the pressure balance tube.
3. A water outlet in the lower end of the water injection tube is S-shaped.
4. The control valve is arranged on the water injection tube.
The containment and reactor pressure vessel joint cooling system of the present invention can further include:
1. An upper end of the pressure balance tube is located in the air space of the water storage tank, and the relative position of a lower end of the pressure balance tube is higher than the upper edge of the reactor pressure vessel.
2. The upper end of the water injection tube is connected with the lowest point of the water storage tank, and the relative position of the lower end of the water injection tube is lower than the lower edge of the pressure balance tube.
3. A water outlet in the lower end of the water injection tube is S-shaped.
4. The control valve is arranged on the water injection tube.
5. The upper part of the water accumulation tank is communicated with the condensate collection pool by the exhaust tube, and a blowdown valve is arranged at the lower part of the water accumulation tank.
The present invention has the following beneficial effects: in the case of LOCA, MSLB and other serious accidents, long-term cooling can be simultaneously provided for the containment and the reactor pressure vessel to enable the reactor containment and the pressure vessel to be in the safe state all the time. The system can achieve the following effects: (1) in the accident working condition, the internal heat exchanger and the water tank can directly generate natural circulation by a density difference of single-phase water and a steam-water mixture without human intervention; (2) the air cooling condenser-cooler and the external atmosphere can achieve natural circulation of the air and remove the heat in the water tank in time to greatly prolong the operation time of a heat removal system, when an added value of the heat in the water tank is smaller than or equal to the heat exchange capability of the air cooling condenser-cooler, the system can realize the long-term cooling of the interior of the containment; (3) the air cooling condenser-cooler can simultaneously cool the water and the steam in the cooling water tank to greatly reduce the consumption of the cooling water, improve the utilization rate of the cooling water and greatly decrease the water capacity of the water cooling tank; (4) the air cooling condenser-cooler can cool the water in the cooling water tank to reduce the temperature of the water, so that the density difference in the falling pipeline and the rising pipeline is greatly increased, the driving force of the natural circulation is reinforced, the flow of the cooling water in the internal heat exchanger is increased, the heat exchange power of the heat exchanger is improved, and the heat in the containment can be removed more effectively; (5) due to the arrangement of the water seal device, the pollution of the external environment to the cooling water tank can be avoided, and the water seal device can also automatically open when the pressure in the water tank is higher, in order to prevent the cooling water tank from being damaged by overpressure;
The present invention has the following beneficial effects: in the case of LOCA, MSLB and other serious accidents, long-term cooling can be simultaneously provided for the containment and the reactor pressure vessel to enable the reactor containment and the pressure vessel to be in the safe state all the time. The system can achieve the following effects: (1) in the accident working condition, the internal heat exchanger and the water tank can directly generate natural circulation by a density difference of single-phase water and a steam-water mixture without human intervention; (2) the air cooling condenser-cooler and the external atmosphere can achieve natural circulation of the air and remove the heat in the water tank in time to greatly prolong the operation time of a heat removal system, when an added value of the heat in the water tank is smaller than or equal to the heat exchange capability of the air cooling condenser-cooler, the system can realize the long-term cooling of the interior of the containment; (3) the air cooling condenser-cooler can simultaneously cool the water and the steam in the cooling water tank to greatly reduce the consumption of the cooling water, improve the utilization rate of the cooling water and greatly decrease the water capacity of the water cooling tank; (4) the air cooling condenser-cooler can cool the water in the cooling water tank to reduce the temperature of the water, so that the density difference in the falling pipeline and the rising pipeline is greatly increased, the driving force of the natural circulation is reinforced, the flow of the cooling water in the internal heat exchanger is increased, the heat exchange power of the heat exchanger is improved, and the heat in the containment can be removed more effectively; (5) due to the arrangement of the water seal device, the pollution of the external environment to the cooling water tank can be avoided, and the water seal device can also automatically open when the pressure in the water tank is higher, in order to prevent the cooling water tank from being damaged by overpressure;
(6) the external reactor cooling system can realize complete passive operation to submerge the pressure vessel, and the water supplement amount can be automatically adjusted by the pressure balance tube without human intervention and adjustment; (7) the S-shaped design can effectively prevent reverse flow of the two phases of steam and water and avoid flow oscillation, and thus the water injection flow is stable;
(8) the utilization rate of cooling water by the passive external reactor cooling system is high, no loss waste is generated, compared with the existing passive technology, in the case of the same cooling time, the consumption of the cooling water is significantly reduced, and the volume of the water storage tank is significantly reduced.
(9) The design of the isolation pool effectively prevents the steam produced by boiling in the pit from reversely flowing into the water storage tank and ensures the reliable and stable operation of the system.
Brief Description of the Drawings Fig.1 is a schematic diagram of a containment cooling system of the present invention.
Fig.2 is a schematic diagram of a containment and reactor pressure vessel joint cooling system of the present invention.
Detailed Description of the Preferred Embodiments The present invention will be described below in more details in combination with the accompany drawings by examples.
First embodiment In combination with Fig.1, a containment cooling system of the present invention is mainly formed by connecting an internal heat exchanger 1, a rising pipeline 2, a falling pipeline 3, an isolation valve 4, an isolation valve 5, a cooling water tank 6 and an air cooling condenser-cooler 7. The internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment 12; the cooling water tank is located on an outer side of an outer layer concrete containment 13, a relative position of the cooling water tank is higher than that of the internal heat exchanger, and the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop; the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, and the other
(8) the utilization rate of cooling water by the passive external reactor cooling system is high, no loss waste is generated, compared with the existing passive technology, in the case of the same cooling time, the consumption of the cooling water is significantly reduced, and the volume of the water storage tank is significantly reduced.
(9) The design of the isolation pool effectively prevents the steam produced by boiling in the pit from reversely flowing into the water storage tank and ensures the reliable and stable operation of the system.
Brief Description of the Drawings Fig.1 is a schematic diagram of a containment cooling system of the present invention.
Fig.2 is a schematic diagram of a containment and reactor pressure vessel joint cooling system of the present invention.
Detailed Description of the Preferred Embodiments The present invention will be described below in more details in combination with the accompany drawings by examples.
First embodiment In combination with Fig.1, a containment cooling system of the present invention is mainly formed by connecting an internal heat exchanger 1, a rising pipeline 2, a falling pipeline 3, an isolation valve 4, an isolation valve 5, a cooling water tank 6 and an air cooling condenser-cooler 7. The internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment 12; the cooling water tank is located on an outer side of an outer layer concrete containment 13, a relative position of the cooling water tank is higher than that of the internal heat exchanger, and the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop; the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, and the other
7 part is arranged in a steam space for cooling water and steam in the cooling water tank, greatly reducing the consumption of cooling water, greatly prolonging the continuous operation time of a heat removal system and realizing long-term cooling of the containment; an air side inlet 9 of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to a bottom surface and communicates an external atmospheric environment with a lower seal head of the air cooling condenser-cooler by a pipeline; and an air side outlet 10 of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to an upper surface and communicates an upper seal head of the air cooling condenser-cooler with an annular space formed by the inner layer concrete containment and the outer layer concrete containment by a pipeline.
The internal heat exchanger employs an efficient enhanced heat transfer tube, such as an external finned tube, an integral pin-finned tube and the like to improve the heat transfer efficiency; and the external air cooling condenser-cooler employs an efficient enhanced heat transfer tube, such as an internal finned tube, an internal ribbed tube and the like to improve the heat transfer efficiency and reduce the volume of the heat exchanger.
Internal and external isolation valve sets 4, 5 are arranged on both the rising pipeline and the falling pipeline, in order to prevent the leakage of a radioactive substance of a passive heat removal system resulting from pipeline breakage.
A water seal device 8 is connected to the side wall of the cooling water tank to isolate the cooling water tank from the external environment in a non-operation working condition to prevent the water in the water tank from being polluted, so as to prevent congestion of the pipeline; in an accident working condition, since a working medium is heated, the pressure in the cooling water tank rises to break the water seal, so that the cooling water tank is communicated with the external atmosphere by the water seal device. An upper connecting tube of the water seal device is communicated with the air space of the cooling water tank, a lower connecting tube of the water seal device is communicated with the water space of the cooling water tank, and the upper connecting tube and the lower connecting tube are in bridge connection by a pipeline.
The internal heat exchanger employs an efficient enhanced heat transfer tube, such as an external finned tube, an integral pin-finned tube and the like to improve the heat transfer efficiency; and the external air cooling condenser-cooler employs an efficient enhanced heat transfer tube, such as an internal finned tube, an internal ribbed tube and the like to improve the heat transfer efficiency and reduce the volume of the heat exchanger.
Internal and external isolation valve sets 4, 5 are arranged on both the rising pipeline and the falling pipeline, in order to prevent the leakage of a radioactive substance of a passive heat removal system resulting from pipeline breakage.
A water seal device 8 is connected to the side wall of the cooling water tank to isolate the cooling water tank from the external environment in a non-operation working condition to prevent the water in the water tank from being polluted, so as to prevent congestion of the pipeline; in an accident working condition, since a working medium is heated, the pressure in the cooling water tank rises to break the water seal, so that the cooling water tank is communicated with the external atmosphere by the water seal device. An upper connecting tube of the water seal device is communicated with the air space of the cooling water tank, a lower connecting tube of the water seal device is communicated with the water space of the cooling water tank, and the upper connecting tube and the lower connecting tube are in bridge connection by a pipeline.
8 An air outlet 11 is formed above the middle part of a dome of the outer layer concrete containment to guide the air flow in the double-layer containment, the air flows out from the air outlet after flowing into the air cooling condenser-cooler and the outlet of the air cooling condenser-cooler from the inlet of the air cooling condenser-cooler, so as to form natural circulation of the air with the external atmospheric environment and provide enough air flow for the air cooling condenser-cooler.
The containment cooling system of the present invention is a passive containment heat removal system, and when operating singly, the working principle thereof is as follows: when the main pipeline of a reactor breaks or when a main steam pipeline breaks, a large amount of steam is released into the containment and is mixed with the air in the containment, so that the temperature and the pressure in the containment rise.
When the pressure in the containment reaches a certain threshold, a pressure sensor in the containment will send a high pressure signal to a main control room of a power station to start the containment heat removal system. After the containment heat removal system is started, the water in the cooling water tank flows into the internal heat exchanger 1 from the falling pipeline 3 and is gradually heated, the water in the falling pipeline and the rising pipeline generates natural circulation by the density difference to introduce the heat in the containment into the cooling water tank, so that the temperature in the cooling water tank 6 rises, the air cooling condenser-cooler is started to operate accordingly, the air enters the air cooling condenser-cooler 7 from the air side inlet 9 of the air cooling condenser-cooler and flows out from the air side outlet 10 of the air cooling condenser-cooler after sufficient heat exchange, and the air is finally exhausted to the atmosphere from the air outlet 11 through the annular space formed by the inner layer concrete containment 12 and the outer layer concrete containment 13, so as to realize natural circulation of the air to take away the heat in the cooling water tank.
At an early stage of an accident, since a lot of steam is discharged into the containment, the temperature in the containment rises quickly, the heat introduced by the internal heat exchanger into the cooling water tank may be higher than the heat exchange power of the air cooling condenser-cooler 7, thus steam is produced in the cooling water tank 6, the pressure in the water tank rises, when the pressure in the water tank is higher than an open pressure of the water seal device 8, the water seal
The containment cooling system of the present invention is a passive containment heat removal system, and when operating singly, the working principle thereof is as follows: when the main pipeline of a reactor breaks or when a main steam pipeline breaks, a large amount of steam is released into the containment and is mixed with the air in the containment, so that the temperature and the pressure in the containment rise.
When the pressure in the containment reaches a certain threshold, a pressure sensor in the containment will send a high pressure signal to a main control room of a power station to start the containment heat removal system. After the containment heat removal system is started, the water in the cooling water tank flows into the internal heat exchanger 1 from the falling pipeline 3 and is gradually heated, the water in the falling pipeline and the rising pipeline generates natural circulation by the density difference to introduce the heat in the containment into the cooling water tank, so that the temperature in the cooling water tank 6 rises, the air cooling condenser-cooler is started to operate accordingly, the air enters the air cooling condenser-cooler 7 from the air side inlet 9 of the air cooling condenser-cooler and flows out from the air side outlet 10 of the air cooling condenser-cooler after sufficient heat exchange, and the air is finally exhausted to the atmosphere from the air outlet 11 through the annular space formed by the inner layer concrete containment 12 and the outer layer concrete containment 13, so as to realize natural circulation of the air to take away the heat in the cooling water tank.
At an early stage of an accident, since a lot of steam is discharged into the containment, the temperature in the containment rises quickly, the heat introduced by the internal heat exchanger into the cooling water tank may be higher than the heat exchange power of the air cooling condenser-cooler 7, thus steam is produced in the cooling water tank 6, the pressure in the water tank rises, when the pressure in the water tank is higher than an open pressure of the water seal device 8, the water seal
9 device automatically opens, the cooling water tank 6 directly discharges the pressure to the air, and a water seal is established again after the pressure is released to isolate the cooling water tank 6 from the external environment.
At the middle and late stages of the accident, the steam discharged into the containment gradually becomes stable or decreases with the increase of time.
At this time, the heat introduced by the internal heat exchanger into the cooling water tank is smaller than or equal to the heat exchange capability of the air cooling condenser-cooler 7, the air cooling condenser-cooler 7 effectively cools and condenses the remaining water and the steam in the upper part of the cooling water tank 6 to avoid the dissipation of the cooling water, so as to realize the long-term cooling of the interior of the containment and greatly improve the safety of the containment.
Second embodiment In combination with Fig.2, a containment and reactor pressure vessel joint cooling system of the present invention mainly includes a containment cooling system and a reactor pressure vessel cooling system. The structure of the containment cooling system is the same as that in the first embodiment.
The reactor pressure vessel cooling system mainly includes a water storage tank 14, a pressure balance tube 15, a water injection tube 16, an isolation pool 17, control valves 18 and 24, a communication tube 19, a reactor pit 20, a reactor pressure vessel 21, a condensate collection pool 22, a water accumulation tank 23, an exhaust tube 25 and a blowdown valve 26. Wherein, the water storage tank is located above the isolation pool, the water storage tank is connected with the isolation pool by the pressure balance tube and the water injection tube, the isolation pool is connected with the reactor pit by the communication tube, the reactor pressure vessel is located in the reactor pit, the condensate collection pool is located below the internal heat exchanger and is sequentially connected with the water accumulation tank, a regulating valve and the isolation pool through a pipeline.
An upper end of the pressure balance tube is located in the air space of the water storage tank, the relative position of a lower end of the pressure balance tube is higher than the upper edge of the reactor pressure vessel, when the system is in a spare state, there is no water in the tube, and in the case of an accident, it is guaranteed the reactor pressure vessel is consistently submerged below the water level.
The upper end of the water injection tube is connected with the lowest point of the water storage tank, and the relative position of the lower end of the water injection tube is lower than the lower edge of the pressure balance tube.
A water outlet in the lower end of the water injection tube adopts an S-shaped design to prevent the air from entering the water storage tank from the water injection tube when the water outlet is exposed from the water level, resulting in a steam-liquid two-phase revere flow state in the tube, which increases the water injection resistance and causes flow vibration.
The isolation pool is a miniature pool, and the water in the pool consistently keeps a cold state to prevent the steam produced by boiling in the reactor pit in the accident working condition from entering the water storage tank.
The control valve is arranged on the water injection tube, when the system is in the spare state, the control valve is closed, and the isolation pool is in a no-water state, in the case of an accident, the control valve is opened, the water is injected into the isolation pool from the water storage tank, and the water enters the reactor pit from the communication tube to submerge the reactor pressure vessel.
The upper part of the water accumulation tank is communicated with the condensate collection pool by the exhaust tube, so that the water in the condensate collection pool can smoothly flow into the water accumulation tank to avoid the two-phase reverse flow phenomenon in the pipeline; and the blowdown valve is arranged at the lower part of the water accumulation tank, water can be periodically injected into the condensate collection pool to flush the condensate collection pool, the water accumulation tank and related pipelines, and the water is drained from the blowdown valve to guarantee a smooth loop and prevent blockage.
In the embodiment, the containment cooling system is a passive containment heat removal system, and the reactor pressure vessel cooling system belongs to a passive external reactor cooling system. The passive containment heat removal system and the passive external reactor cooling system can either operate jointly or operate independently. When the passive containment heat removal system operates independently, the control valve is in a closed state, the condensate generated by the internal heat exchanger is collected by the condensate collection pool and is injected into the water accumulation tank for storage. When the passive containment heat removal system and the passive external reactor cooling system can operate jointly, the control valve is opened, then the condensate flows into the isolation pool from the water accumulation tank to cool the reactor pressure vessel, so the water in the water storage tank can be saved, and the volume of the water storage tank can be effectively reduced.
When the passive containment heat removal system and the passive external reactor cooling system can operate jointly, the working principle is as follows: when the main pipeline of a reactor breaks or when a main steam pipeline breaks, a large amount of steam is released into the containment and is mixed with the air in the containment, so that the temperature and the pressure in the containment rise; meanwhile, a reactor core may be melt down by severe dehydration of the reactor core, the melt may collapse to the lower seal head of the pressure vessel, and if the lower seal head is burnt through by excessive heat load, the integrity of the containment may be threatened. To prevent the melt of the reactor core from burning through the lower seal head of the pressure vessel, water needs to be injected in the reactor pit 20. At this time, the passive containment heat removal system and the passive external reactor cooling system need to be started at the same time.
After the systems are started, the water in the cooling water tank flows into the internal heat exchanger 1 from the falling pipeline 3 and is gradually heated, the water in the falling pipeline and the rising pipeline generates natural circulation by the density difference to introduce the heat in the containment into the cooling water tank, so the temperature in the cooling water tank 6 rises, the air cooling condenser-cooler is started to operate accordingly, the air enters the air cooling condenser-cooler 7 from the air side inlet 9 of the air cooling condenser-cooler and flows out from the air side , , outlet 10 of the air cooling condenser-cooler after sufficient heat exchange, and the air is finally exhausted to the atmosphere from the air outlet 11 through the annular space formed by the inner layer concrete containment 12 and the outer layer concrete containment 13, so as to realize natural circulation of the air to take away the heat in the cooling water tank.
The condensed water generated on the surface of the internal heat exchanger 1 is collected by the condensate collection pool 22 and enters the isolation pool 17 after flowing by the water accumulation tank 23 and the control valve 24, and the condensed water is mixed with the water that inflows from the water storage tank 14 by the water injection tube 16 in the isolation pool 17 to serve as the cooling water of the reactor pressure vessel 21 together. After the water level in the isolation pool 17 is higher than a horizontal position where the communication tube 19 at the bottom is located, the water flows from the isolation pool 17 into the reactor pit 20 through the communication tube 19 to quickly submerge the reactor pressure vessel 21.
Since the isolation pool 17 and the reactor pit 20 are of a communicator structure, the water level therebetween is balanced. When the water level in the isolation pool 17 submerges the lower end of the pressure balance tube 15, the cooling water injected from the water storage tank 14 into the isolation pool 17 quickly reduces until stop.
With the release of a large amount of decay heat of the reactor core, the surface of the reactor pressure vessel 21 in a high temperature state continuously heats the cooling water in the reactor pit 20, so that the temperature of the water in the reactor pit 20 rises until boiling. At this time, the steam is also injected into the containment from the crevasse of the main pipeline. After the steam condenses on the surface of the internal heat exchanger 1, the condensed water is collected by the condensate collection pool 22 and is continuously injected into the reactor pit 20 to cool the surface of the reactor pressure vessel 21, if the amount of the condensed water on the surface of the internal heat exchanger 1 is larger than the amount of the water injected from the water accumulation tank 23 to the isolation pool 17, the condensed water is stored in the water accumulation tank 23.
At an early stage of an accident, since a lot of steam is discharged into the containment, the temperature in the containment rises quickly, the heat introduced by the internal heat exchanger into the cooling water tank may be higher than the heat exchange power of the air cooling condenser-cooler 7, thus steam is produced in the cooling water tank 6, the pressure in the water tank rises, when the pressure in the water tank is higher than an open pressure of the water seal device 8, the water seal device automatically opens, the cooling water tank 6 directly discharges the pressure to the air, and a water seal is established again after the pressure release to isolate the cooling water tank 6 from the external environment. In addition, the amount of the condensed water on the surface of the internal heat exchanger 1 is very large (the condensed water is mainly from massive condensation of the steam evaporated from the pit and jet out from the crevasse), and the condensed water will be continuously injected into the isolation pool 17 to ensure that the lower end of the pressure balance tube 15 is consistently submerged. Therefore, the water in the water storage tank 14 is nearly not additionally consumed except being initially injected into the isolation pool 17.
At the middle and late stages of the accident, the steam discharged into the containment gradually becomes stable or decreases with the increase of time.
At this time, the heat introduced by the internal heat exchanger into the cooling water tank is smaller than or equal to the heat exchange capability of the air cooling condenser-cooler 7, the air cooling condenser-cooler 7 effectively cools and condenses the remaining water and the steam in the upper part of the cooling water tank 6 to avoid the dissipation of the cooling water, so as to realize the long-term cooling of the interior of the containment and greatly improve the safety of the containment. In addition, due to the decrease of the amount of the condensed water on the surface of the internal heat exchanger 1, if the evaporation amount of the water in the reactor pit 20 is larger than the condensate collection amount, the water level will be lower than the lower end of the pressure balance tube 15 due to the evaporation, and the water storage tank 14 recovers the water injection, until the lower end of the pressure balance tube 15 is submerged again. And so forth, the reactor pressure vessel 21 is consistently guaranteed in a submerged state without human intervention.
The foregoing descriptions are merely preferred embodiments of the present invention, it should be noted that those of ordinary skill in the art can still make a variety of improvements and modifications without departing from the principle of the present , , invention, and these improvements and modifications should also be deemed as the protection scope of the present invention.
At the middle and late stages of the accident, the steam discharged into the containment gradually becomes stable or decreases with the increase of time.
At this time, the heat introduced by the internal heat exchanger into the cooling water tank is smaller than or equal to the heat exchange capability of the air cooling condenser-cooler 7, the air cooling condenser-cooler 7 effectively cools and condenses the remaining water and the steam in the upper part of the cooling water tank 6 to avoid the dissipation of the cooling water, so as to realize the long-term cooling of the interior of the containment and greatly improve the safety of the containment.
Second embodiment In combination with Fig.2, a containment and reactor pressure vessel joint cooling system of the present invention mainly includes a containment cooling system and a reactor pressure vessel cooling system. The structure of the containment cooling system is the same as that in the first embodiment.
The reactor pressure vessel cooling system mainly includes a water storage tank 14, a pressure balance tube 15, a water injection tube 16, an isolation pool 17, control valves 18 and 24, a communication tube 19, a reactor pit 20, a reactor pressure vessel 21, a condensate collection pool 22, a water accumulation tank 23, an exhaust tube 25 and a blowdown valve 26. Wherein, the water storage tank is located above the isolation pool, the water storage tank is connected with the isolation pool by the pressure balance tube and the water injection tube, the isolation pool is connected with the reactor pit by the communication tube, the reactor pressure vessel is located in the reactor pit, the condensate collection pool is located below the internal heat exchanger and is sequentially connected with the water accumulation tank, a regulating valve and the isolation pool through a pipeline.
An upper end of the pressure balance tube is located in the air space of the water storage tank, the relative position of a lower end of the pressure balance tube is higher than the upper edge of the reactor pressure vessel, when the system is in a spare state, there is no water in the tube, and in the case of an accident, it is guaranteed the reactor pressure vessel is consistently submerged below the water level.
The upper end of the water injection tube is connected with the lowest point of the water storage tank, and the relative position of the lower end of the water injection tube is lower than the lower edge of the pressure balance tube.
A water outlet in the lower end of the water injection tube adopts an S-shaped design to prevent the air from entering the water storage tank from the water injection tube when the water outlet is exposed from the water level, resulting in a steam-liquid two-phase revere flow state in the tube, which increases the water injection resistance and causes flow vibration.
The isolation pool is a miniature pool, and the water in the pool consistently keeps a cold state to prevent the steam produced by boiling in the reactor pit in the accident working condition from entering the water storage tank.
The control valve is arranged on the water injection tube, when the system is in the spare state, the control valve is closed, and the isolation pool is in a no-water state, in the case of an accident, the control valve is opened, the water is injected into the isolation pool from the water storage tank, and the water enters the reactor pit from the communication tube to submerge the reactor pressure vessel.
The upper part of the water accumulation tank is communicated with the condensate collection pool by the exhaust tube, so that the water in the condensate collection pool can smoothly flow into the water accumulation tank to avoid the two-phase reverse flow phenomenon in the pipeline; and the blowdown valve is arranged at the lower part of the water accumulation tank, water can be periodically injected into the condensate collection pool to flush the condensate collection pool, the water accumulation tank and related pipelines, and the water is drained from the blowdown valve to guarantee a smooth loop and prevent blockage.
In the embodiment, the containment cooling system is a passive containment heat removal system, and the reactor pressure vessel cooling system belongs to a passive external reactor cooling system. The passive containment heat removal system and the passive external reactor cooling system can either operate jointly or operate independently. When the passive containment heat removal system operates independently, the control valve is in a closed state, the condensate generated by the internal heat exchanger is collected by the condensate collection pool and is injected into the water accumulation tank for storage. When the passive containment heat removal system and the passive external reactor cooling system can operate jointly, the control valve is opened, then the condensate flows into the isolation pool from the water accumulation tank to cool the reactor pressure vessel, so the water in the water storage tank can be saved, and the volume of the water storage tank can be effectively reduced.
When the passive containment heat removal system and the passive external reactor cooling system can operate jointly, the working principle is as follows: when the main pipeline of a reactor breaks or when a main steam pipeline breaks, a large amount of steam is released into the containment and is mixed with the air in the containment, so that the temperature and the pressure in the containment rise; meanwhile, a reactor core may be melt down by severe dehydration of the reactor core, the melt may collapse to the lower seal head of the pressure vessel, and if the lower seal head is burnt through by excessive heat load, the integrity of the containment may be threatened. To prevent the melt of the reactor core from burning through the lower seal head of the pressure vessel, water needs to be injected in the reactor pit 20. At this time, the passive containment heat removal system and the passive external reactor cooling system need to be started at the same time.
After the systems are started, the water in the cooling water tank flows into the internal heat exchanger 1 from the falling pipeline 3 and is gradually heated, the water in the falling pipeline and the rising pipeline generates natural circulation by the density difference to introduce the heat in the containment into the cooling water tank, so the temperature in the cooling water tank 6 rises, the air cooling condenser-cooler is started to operate accordingly, the air enters the air cooling condenser-cooler 7 from the air side inlet 9 of the air cooling condenser-cooler and flows out from the air side , , outlet 10 of the air cooling condenser-cooler after sufficient heat exchange, and the air is finally exhausted to the atmosphere from the air outlet 11 through the annular space formed by the inner layer concrete containment 12 and the outer layer concrete containment 13, so as to realize natural circulation of the air to take away the heat in the cooling water tank.
The condensed water generated on the surface of the internal heat exchanger 1 is collected by the condensate collection pool 22 and enters the isolation pool 17 after flowing by the water accumulation tank 23 and the control valve 24, and the condensed water is mixed with the water that inflows from the water storage tank 14 by the water injection tube 16 in the isolation pool 17 to serve as the cooling water of the reactor pressure vessel 21 together. After the water level in the isolation pool 17 is higher than a horizontal position where the communication tube 19 at the bottom is located, the water flows from the isolation pool 17 into the reactor pit 20 through the communication tube 19 to quickly submerge the reactor pressure vessel 21.
Since the isolation pool 17 and the reactor pit 20 are of a communicator structure, the water level therebetween is balanced. When the water level in the isolation pool 17 submerges the lower end of the pressure balance tube 15, the cooling water injected from the water storage tank 14 into the isolation pool 17 quickly reduces until stop.
With the release of a large amount of decay heat of the reactor core, the surface of the reactor pressure vessel 21 in a high temperature state continuously heats the cooling water in the reactor pit 20, so that the temperature of the water in the reactor pit 20 rises until boiling. At this time, the steam is also injected into the containment from the crevasse of the main pipeline. After the steam condenses on the surface of the internal heat exchanger 1, the condensed water is collected by the condensate collection pool 22 and is continuously injected into the reactor pit 20 to cool the surface of the reactor pressure vessel 21, if the amount of the condensed water on the surface of the internal heat exchanger 1 is larger than the amount of the water injected from the water accumulation tank 23 to the isolation pool 17, the condensed water is stored in the water accumulation tank 23.
At an early stage of an accident, since a lot of steam is discharged into the containment, the temperature in the containment rises quickly, the heat introduced by the internal heat exchanger into the cooling water tank may be higher than the heat exchange power of the air cooling condenser-cooler 7, thus steam is produced in the cooling water tank 6, the pressure in the water tank rises, when the pressure in the water tank is higher than an open pressure of the water seal device 8, the water seal device automatically opens, the cooling water tank 6 directly discharges the pressure to the air, and a water seal is established again after the pressure release to isolate the cooling water tank 6 from the external environment. In addition, the amount of the condensed water on the surface of the internal heat exchanger 1 is very large (the condensed water is mainly from massive condensation of the steam evaporated from the pit and jet out from the crevasse), and the condensed water will be continuously injected into the isolation pool 17 to ensure that the lower end of the pressure balance tube 15 is consistently submerged. Therefore, the water in the water storage tank 14 is nearly not additionally consumed except being initially injected into the isolation pool 17.
At the middle and late stages of the accident, the steam discharged into the containment gradually becomes stable or decreases with the increase of time.
At this time, the heat introduced by the internal heat exchanger into the cooling water tank is smaller than or equal to the heat exchange capability of the air cooling condenser-cooler 7, the air cooling condenser-cooler 7 effectively cools and condenses the remaining water and the steam in the upper part of the cooling water tank 6 to avoid the dissipation of the cooling water, so as to realize the long-term cooling of the interior of the containment and greatly improve the safety of the containment. In addition, due to the decrease of the amount of the condensed water on the surface of the internal heat exchanger 1, if the evaporation amount of the water in the reactor pit 20 is larger than the condensate collection amount, the water level will be lower than the lower end of the pressure balance tube 15 due to the evaporation, and the water storage tank 14 recovers the water injection, until the lower end of the pressure balance tube 15 is submerged again. And so forth, the reactor pressure vessel 21 is consistently guaranteed in a submerged state without human intervention.
The foregoing descriptions are merely preferred embodiments of the present invention, it should be noted that those of ordinary skill in the art can still make a variety of improvements and modifications without departing from the principle of the present , , invention, and these improvements and modifications should also be deemed as the protection scope of the present invention.
Claims (9)
1. A containment cooling system, comprising an internal heat exchanger, a rising pipeline, a falling pipeline, isolation valves, a cooling water tank and an air cooling condenser-cooler, wherein the internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment, the cooling water tank is located on an outer side of an outer layer concrete containment, a relative position of the cooling water tank is higher than that of the internal heat exchanger, the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop, the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, the other part is arranged in a steam space, an air side inlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to a bottom surface and communicates an external atmospheric environment with a lower seal head of the air cooling condenser-cooler by a pipeline, and an air side outlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to an upper surface and communicates an upper seal head of the air cooling condenser-cooler with an annular space formed by the inner layer concrete containment and the outer layer concrete containment by a pipeline.
2. The containment cooling system of claim 1, wherein a water seal device is connected to the side wall of the cooling water tank, an upper connecting tube of the water seal device is communicated with the air space of the cooling water tank, a lower connecting tube of the water seal device is communicated with the water space of the cooling water tank, and the upper connecting tube and the lower connecting tube are in bridge connection by a pipeline.
3. The containment cooling system of claim 1 or 2, wherein internal and external isolation valve sets are arranged on both the rising pipeline and the falling pipeline.
4. A containment and reactor pressure vessel joint cooling system, comprising a containment cooling system and a reactor pressure vessel cooling system, wherein the containment cooling system comprises an internal heat exchanger, a rising pipeline, a falling pipeline, isolation valves, a cooling water tank and an air cooling condenser-cooler, the internal heat exchanger is located in an upper space close to a side wall in an inner layer concrete containment, the cooling water tank is located on an outer side of an outer layer concrete containment, a relative position of the cooling water tank is higher than that of the internal heat exchanger, the cooling water tank is connected with the internal heat exchanger by the rising pipeline and the falling pipeline to constitute a closed loop, the air cooling condenser-cooler is an unshelled heat exchanger and is located in the cooling water tank, the air cooling condenser-cooler is obliquely arranged, a part of a heat transfer tube of the air cooling condenser-cooler is arranged in a water space, the other part is arranged in a steam space, an air side inlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to a bottom surface and communicates an external atmospheric environment with a lower seal head of the air cooling condenser-cooler by a pipeline, and an air side outlet of the air cooling condenser-cooler is formed in a position on the side wall of the water tank close to an upper surface and communicates an upper seal head of the air cooling condenser-cooler with an annular space formed by the inner layer concrete containment and the outer layer concrete containment by a pipeline; and the reactor pressure vessel cooling system comprises a water storage tank, a pressure balance tube, a water injection tube, an isolation pool, a control valve, a communication tube, a condensate collection pool, a water accumulation tank and an exhaust tube, the water storage tank is located above the isolation pool, the water storage tank is connected with the isolation pool by the pressure balance tube and the water injection tube, the isolation pool is connected with a reactor pit by the communication tube, a reactor pressure vessel is located in the reactor pit, the condensate collection pool is located below the internal heat exchanger, and the condensate collection pool is sequentially connected with the water accumulation tank, a regulating valve and the isolation pool through a pipeline.
5. The containment and reactor pressure vessel joint cooling system of claim 4, wherein an upper end of the pressure balance tube is located in the air space of the water storage tank, and the relative position of a lower end of the pressure balance tube is higher than an upper edge of the reactor pressure vessel.
6. The containment and reactor pressure vessel joint cooling system of claim 4, wherein an upper end of the water injection tube is connected with a lowest point of the water storage tank, and the relative position of a lower end of the water injection tube is lower than a lower edge of the pressure balance tube.
7. The containment and reactor pressure vessel joint cooling system of claim 4, wherein a water outlet in a lower end of the water injection tube is S-shaped.
8. The containment and reactor pressure vessel joint cooling system of claim 4, wherein the control valve is arranged on the water injection tube.
9. The containment and reactor pressure vessel joint cooling system of claim 4, wherein the upper part of the water accumulation tank is communicated with the condensate collection pool by the exhaust tube, and a blowdown valve is arranged at a lower part of the water accumulation tank.
Applications Claiming Priority (5)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410353978.6A CN104091621B (en) | 2014-07-24 | 2014-07-24 | Passive out-pile cooling system |
| CN201410353537.6 | 2014-07-24 | ||
| CN201410353537.6A CN104103325B (en) | 2014-07-24 | 2014-07-24 | Heat derivation system for long-term passive containment |
| CN201410353978.6 | 2014-07-24 | ||
| PCT/CN2014/001003 WO2016011569A1 (en) | 2014-07-24 | 2014-11-13 | Containment cooling system, and containment and reactor pressure vessel joint cooling system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CA2954136A1 true CA2954136A1 (en) | 2016-01-28 |
| CA2954136C CA2954136C (en) | 2018-02-13 |
Family
ID=55162379
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA2954136A Active CA2954136C (en) | 2014-07-24 | 2014-11-13 | Containment cooling system and containment and reactor pressure vessel joint cooling system |
Country Status (5)
| Country | Link |
|---|---|
| JP (1) | JP6277322B2 (en) |
| KR (1) | KR102085983B1 (en) |
| CN (1) | CN106104701B (en) |
| CA (1) | CA2954136C (en) |
| WO (1) | WO2016011569A1 (en) |
Families Citing this family (32)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106782698B (en) * | 2016-11-28 | 2018-04-17 | 哈尔滨工程大学 | A kind of long-term efficient Passive containment cooling system using spraying technique |
| CN108630329B (en) * | 2017-03-24 | 2024-05-31 | 国家电投集团科学技术研究院有限公司 | Built-in heat exchanger of containment |
| CN108630327B (en) * | 2017-03-24 | 2023-08-25 | 国核示范电站有限责任公司 | Passive containment heat exchanger system |
| CN107833641A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | A kind of marine PWR seawater cools down Passive residual heat removal system |
| CN109765067A (en) * | 2017-11-10 | 2019-05-17 | 国核华清（北京）核电技术研发中心有限公司 | The large-scale passive core cooling system overall performance test platform of advanced pressurized water reactor nuclear power plant |
| CN107958712A (en) * | 2017-11-23 | 2018-04-24 | 中国核电工程有限公司 | A kind of heat pipe exchanging type passive containment thermal conduction system |
| CN109841289B (en) * | 2017-11-29 | 2024-07-26 | 国家电投集团科学技术研究院有限公司 | Test device for passive heat conduction system of containment |
| JP6994967B2 (en) | 2018-02-01 | 2022-02-04 | 本田技研工業株式会社 | Bearing equipment |
| CN108492892B (en) * | 2018-02-28 | 2020-04-07 | 哈尔滨工程大学 | Built-in containment filtering and discharging system |
| CN110491529A (en) * | 2018-05-15 | 2019-11-22 | 华龙国际核电技术有限公司 | A kind of cooling system |
| CN109341069A (en) * | 2018-10-26 | 2019-02-15 | 江苏永钢集团有限公司 | A kind of novel hot water case make-up water supply control system |
| CN109346196B (en) * | 2018-11-13 | 2022-04-15 | 中国核动力研究设计院 | Active and passive cooling combined molten material in-pile retention system |
| CN109585044B (en) * | 2018-12-18 | 2024-04-12 | 长江勘测规划设计研究有限责任公司 | Passive cooling system of underground nuclear power station chamber type containment |
| CN110489796B (en) * | 2019-07-17 | 2022-06-21 | 哈尔滨工程大学 | Effectiveness judgment method of heat pipe-based nuclear reactor heat exporting system |
| CN110570957B (en) * | 2019-09-06 | 2024-04-12 | 长江勘测规划设计研究有限责任公司 | Multistage reciprocating passive cooling system of underground nuclear power station |
| CN110580958B (en) * | 2019-09-06 | 2024-04-12 | 长江勘测规划设计研究有限责任公司 | Passive external pipe network cooling system for steel containment of underground nuclear power station |
| CN111599498B (en) * | 2020-04-14 | 2022-11-18 | 中国核电工程有限公司 | Passive containment air-water long-term cooling system |
| CN111599493B (en) * | 2020-05-09 | 2023-03-31 | 哈尔滨工程大学 | Press down pond |
| KR102437395B1 (en) | 2020-08-19 | 2022-08-30 | 한국원자력연구원 | Passive protection system for reactor |
| CN112053791B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Non-time-limit passive combined heat removal system with integrated heat release trap |
| CN112652413B (en) * | 2020-11-26 | 2024-01-23 | 中国核电工程有限公司 | Arrangement method of containment system and containment system arrangement structure |
| CN113035394B (en) * | 2021-03-05 | 2023-12-19 | 哈尔滨工程大学 | Adopt built-in high-efficient heat exchanger of containment of gas storage compartment formula |
| CN113593733A (en) * | 2021-07-02 | 2021-11-02 | 中国核电工程有限公司 | Passive steel containment heat exporting system |
| CN113704959B (en) * | 2021-07-12 | 2024-04-09 | 中国核电工程有限公司 | Simulation method and system for heat exchanger type passive containment cooling system |
| CN113707347A (en) * | 2021-07-12 | 2021-11-26 | 中国核电工程有限公司 | Method for preventing mistaken dosing of nuclear power plant containment spraying system and judgment module |
| CN113488214B (en) * | 2021-07-22 | 2024-01-23 | 中国核动力研究设计院 | Natural circulation cooling method for upper end socket of pressure vessel of nuclear power plant when steam exists |
| CN113865904B (en) * | 2021-09-24 | 2024-07-19 | 哈尔滨工程大学 | Multifunctional flowing heat exchange test device |
| CN114220573A (en) * | 2021-11-02 | 2022-03-22 | 中国核电工程有限公司 | Enhanced passive containment heat discharge system based on secondary evaporative cooling |
| CN114068049B (en) * | 2021-11-22 | 2024-09-17 | 中国核动力研究设计院 | Buffer device and passive waste heat discharging system |
| US20230395271A1 (en) * | 2022-06-02 | 2023-12-07 | Ge-Hitachi Nuclear Energy Americas Llc | Systems and methods for reducing noncondensable gas buildup in coolant systems |
| CN115240879B (en) * | 2022-07-05 | 2024-06-14 | 上海核工程研究设计院股份有限公司 | Double-deck containment reactor safety coefficient and reactor system |
| CN116598028B (en) * | 2022-11-28 | 2024-01-19 | 上海核工程研究设计院股份有限公司 | Prevention and relief system for serious accident of integrated nuclear reactor and control method thereof |
Family Cites Families (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59193395A (en) * | 1983-04-18 | 1984-11-01 | 株式会社東芝 | Device for cooling atmosphere in reactor container |
| JPH02253192A (en) * | 1989-03-28 | 1990-10-11 | Toshiba Corp | Cooling system for natural heat radiation type nuclear reactor containment |
| US5049353A (en) * | 1989-04-21 | 1991-09-17 | Westinghouse Electric Corp. | Passive containment cooling system |
| EP0667623A1 (en) * | 1994-02-14 | 1995-08-16 | FINMECCANICA S.p.A. AZIENDA ANSALDO | A system for passively dissipating heat from the interior of a nuclear reactor containment structure |
| JP4834349B2 (en) * | 2005-08-18 | 2011-12-14 | 株式会社東芝 | Reactor containment cooling equipment |
| CN102097139B (en) * | 2010-10-27 | 2013-01-16 | 华北电力大学 | Major accident mitigation system of nuclear power station on basis of nano fluid characteristic |
| KR101297101B1 (en) * | 2011-11-01 | 2013-08-19 | 한국원자력연구원 | Device for residual heat removal of integrated reactor and its method |
| CN202615805U (en) * | 2012-05-02 | 2012-12-19 | 哈尔滨工程大学 | Non-dynamic safety case cooling system |
| CN102737738B (en) * | 2012-06-25 | 2015-01-07 | 中国核电工程有限公司 | Passive direct evaporation type cooling system for double-layer concrete containment |
| CN202887748U (en) * | 2012-08-20 | 2013-04-17 | 中国核电工程有限公司 | Passive heat discharge device for dealing with plant switch-off accident |
| CN202855318U (en) * | 2012-09-04 | 2013-04-03 | 中科华核电技术研究院有限公司 | Passive starting cooling system for nuclear power plant and nuclear power plant system |
| KR101480046B1 (en) * | 2013-05-08 | 2015-01-09 | 한국원자력연구원 | Cooling system of emergency coolling tank and nuclear power plant having the same |
| CN104091621B (en) * | 2014-07-24 | 2016-08-03 | 哈尔滨工程大学 | Passive out-pile cooling system |
| CN104103325B (en) * | 2014-07-24 | 2017-01-25 | 哈尔滨工程大学 | Heat derivation system for long-term passive containment |
| KR101742644B1 (en) * | 2016-09-13 | 2017-06-07 | 한국원자력연구원 | Passive Auxiliary Feedwater Cooling System having Air-Cooled Double Containments |
-
2014
- 2014-11-13 WO PCT/CN2014/001003 patent/WO2016011569A1/en active Application Filing
- 2014-11-13 CA CA2954136A patent/CA2954136C/en active Active
- 2014-11-13 JP JP2017504086A patent/JP6277322B2/en active Active
- 2014-11-13 CN CN201480075917.6A patent/CN106104701B/en active Active
- 2014-11-13 KR KR1020167034756A patent/KR102085983B1/en active IP Right Grant
Also Published As
| Publication number | Publication date |
|---|---|
| CN106104701A (en) | 2016-11-09 |
| JP6277322B2 (en) | 2018-02-07 |
| WO2016011569A1 (en) | 2016-01-28 |
| JP2017521674A (en) | 2017-08-03 |
| KR20170039083A (en) | 2017-04-10 |
| CA2954136C (en) | 2018-02-13 |
| KR102085983B1 (en) | 2020-03-06 |
| CN106104701B (en) | 2018-06-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CA2954136C (en) | Containment cooling system and containment and reactor pressure vessel joint cooling system | |
| CN103903659B (en) | Floating nuclear power plant Heat Discharging System of Chinese | |
| US20120294407A1 (en) | Nuclear Power Plant, Fuel Pool Water Cooling Facility and Method Thereof | |
| CN202855316U (en) | Containment cooling system for PWR (pressurized water reactor) nuclear power plant | |
| CN104103325B (en) | Heat derivation system for long-term passive containment | |
| JP4675926B2 (en) | Boiling water reactor | |
| CN103377728B (en) | A kind of Flooded-type containment complete passive after-heat removal system | |
| CN104733060A (en) | Passive residual heat removal system of marine nuclear power device | |
| CN104361914A (en) | Passive safe cooling system | |
| CN109545401B (en) | Passive residual heat removal system outside lead-based fast reactor | |
| GB2520455A (en) | Secondary-side passive residual heat discharge system for nuclear power plant steam generator | |
| GB2531190A (en) | Passive concrete containment cooling system | |
| CN103617815A (en) | Passive residual heat exhausting system of pressurized water reactor nuclear power plant | |
| CN204242601U (en) | Non-passive safety cooling system | |
| CN202549316U (en) | Non-active safe shell cooling system with combination of water logging and air cooling | |
| CN106328223B (en) | A kind of novel passive containment energy management system | |
| CN102903402A (en) | Advanced secondary side core heat lead-out device | |
| KR101250479B1 (en) | Apparatus for safety improvement of passive type emergency core cooling system with a safeguard vessel and Method for heat transfer-function improvement using thereof | |
| CN104916334A (en) | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant | |
| RU152416U1 (en) | EMERGENCY HEAT REMOVAL SYSTEM | |
| CN205656860U (en) | Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear | |
| CN204178729U (en) | A kind of long-term passive containment thermal conduction system | |
| CN104091621B (en) | Passive out-pile cooling system | |
| AU2019101235A4 (en) | Lead-cooled fast reactor waste heat removal system and method | |
| CN210271804U (en) | Emergent waste heat discharge system of water injection formula lead bismuth fast reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EEER | Examination request |
Effective date: 20170103 |