CN210837199U - Waste heat discharge system and nuclear power system - Google Patents
Waste heat discharge system and nuclear power system Download PDFInfo
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- CN210837199U CN210837199U CN201921784982.2U CN201921784982U CN210837199U CN 210837199 U CN210837199 U CN 210837199U CN 201921784982 U CN201921784982 U CN 201921784982U CN 210837199 U CN210837199 U CN 210837199U
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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
Abstract
The embodiment of the utility model provides a waste heat discharge system and a nuclear power system, which relate to the technical field of nuclear power; wherein, above-mentioned waste heat removal system is applied to nuclear power system, and nuclear power system includes steam generator, and waste heat removal system includes: a condenser connected to the steam generator; the cooling water tank is internally provided with an accommodating cavity for accommodating the condenser, and the accommodating cavity is communicated with the external space through a first opening and a second opening which are arranged on the cooling water tank; the first opening is provided with a flow guide structure extending into the accommodating cavity, and the second opening is communicated with the first opening through the flow guide structure. The embodiment of the utility model provides a waste heat discharge system can in time derive the reactor core waste heat through the higher water-cooling mode of cooling efficiency in the early stage of the accident, and in the accident later stage, can not need extra moisturizing or use other active equipment, maintains the derivation of reactor core waste heat always through the air cooling mode, effectively guarantees the security of reactor.
Description
Technical Field
The utility model relates to a nuclear power technology field especially relates to a waste heat discharge system and nuclear power system.
Background
Pressurized water reactor nuclear power plants typically have a primary circuit for transferring heat generated by the core through a steam generator to a secondary circuit, thereby generating steam on the secondary side of the steam generator. In practical application, the pressurized water reactor nuclear power station may face accident conditions such as power failure of the whole plant, which causes a Loss of secondary side Main feedwater accident (Loss of Main fed wateraccount), and the heat transfer capacity of the steam generator is reduced, so that the reactor core waste heat is accumulated in a primary loop, and the safety of the pressurized water reactor nuclear power station is affected.
In order to discharge the core waste heat under the accident condition, a secondary side passive waste heat removal system (i.e., a waste heat removal system independent of an external power source is provided on the secondary side of the steam generator) is generally provided for the pressurized water reactor. In the prior art, the secondary side passive residual heat removal system mostly adopts a water cooling structure, but after the water amount in the water cooling structure is used up, the reactor core residual heat is difficult to continue to be derived, so that the continuity of the derived reactor core residual heat is poor, and the safety of the pressurized water reactor nuclear power station is difficult to fully guarantee.
SUMMERY OF THE UTILITY MODEL
The embodiment of the utility model provides a waste heat discharge system and nuclear power system to it is relatively poor to solve the passive waste heat discharge system reactor core waste heat derivation continuation of current secondary side, is difficult to fully guarantee the safe problem of pressurized water reactor nuclear power station.
In order to solve the technical problem, the utility model discloses a realize like this:
the embodiment of the utility model provides a waste heat discharge system is applied to nuclear power system, nuclear power system includes steam generator, waste heat discharge system includes:
the condenser is connected with the steam generator through a pipeline;
the cooling water tank is internally provided with an accommodating cavity for accommodating the condenser, and the accommodating cavity is communicated with an external space through a first opening and a second opening which are arranged on the cooling water tank; the first opening is provided with a flow guide structure extending into the accommodating cavity, and the second opening is communicated with the first opening through the flow guide structure; the condenser is at least partially positioned in a space enclosed by the flow guide structure.
Optionally, an air outlet channel located outside the cooling water tank is further arranged at the first opening, and the air outlet channel is communicated with a space surrounded by the flow guide structure.
Optionally, the first opening and the second opening are located at the top of the cooling water tank.
Optionally, the cross-sectional shape of the flow guiding structure is annular.
Optionally, the number of the second openings is multiple, and the multiple second openings are arranged around the flow guide structure at intervals.
Optionally, an air inlet structure is arranged at the second opening, and the air inlet structure comprises an air valve or a check valve.
Optionally, a thermometer is arranged on a pipe connecting the condenser and the steam generator.
Optionally, the number of the cooling water tanks is plural, and the plural cooling water tanks are communicated with each other through a communication line.
The embodiment of the utility model also provides a nuclear power system, including steam generator and the above-mentioned waste heat discharge system;
the steam generator is connected with the condenser through a pipeline.
The embodiment of the utility model provides a waste heat discharge system can in time derive the reactor core waste heat through the water-cooling mode in the early stage of the accident, and in the accident later stage, because be provided with first opening and the second opening through the water conservancy diversion structure intercommunication on the cooling water tank, along with the water level reduction in the cooling water tank, the air can be discharged from the first opening after the second opening gets into by the condenser heating, because the density difference drive air of the inside and outside cold and hot air of water conservancy diversion structure is continuous to flow through the condenser in the cooling water tank, thereby take away the heat of condenser. Therefore, the derivation of the reactor core waste heat can be always maintained through an air cooling mode in the later period of an accident, additional water supplement or other active devices are not needed, and the safety of the reactor is effectively guaranteed.
Drawings
Fig. 1 is a schematic structural view of a waste heat removal system provided in an embodiment of the present invention;
FIG. 2 is a thermal power variation curve of core decay of a certain pressurized water reactor nuclear power plant.
The figures show that: the system comprises a steam generator 1, a main steam pipeline 2, a main water supply pipeline 3, a first isolation valve 4, a first steam pipeline 5, a second isolation valve 6, a first containment penetration piece 7, a first thermometer 8, a third isolation valve 9, a second steam pipeline 10, a condenser 11, a first water return pipeline 12, a fourth isolation valve 13, a second thermometer 14, a second water return pipeline 15, a second containment penetration piece 16, a fifth isolation valve 17, a cooling water tank 18, a communication pipeline 19, a sixth isolation valve 20, a flow guide structure 21, a second opening 22, a first opening 23, a chimney 24, a main steam system 25 and an auxiliary water supply system 26.
Detailed Description
In order to make the technical problems, technical solutions and advantages to be solved by the present invention clearer, the following detailed description will be given with reference to the accompanying drawings and specific embodiments. In the following description, specific details are provided, such as specific configurations and components, merely to facilitate a thorough understanding of embodiments of the invention. Thus, it will be apparent to those skilled in the art that various changes and modifications may be made to the embodiments described herein without departing from the scope and spirit of the invention. In addition, descriptions of well-known functions and constructions are omitted for clarity and conciseness.
The embodiment of the utility model provides a residual heat removal system is applied to nuclear power system, as shown in FIG. 1, nuclear power system includes steam generator 1, residual heat removal system includes:
the condenser 11 is connected with the steam generator 1 through a pipeline;
a cooling water tank 18, wherein an accommodating cavity for accommodating the condenser 11 is arranged in the cooling water tank 18, and the accommodating cavity is communicated with an external space through a first opening 23 and a second opening 22 arranged in the cooling water tank 18; a flow guide structure 21 extending into the accommodating cavity is arranged at the first opening 23, and the second opening 22 is communicated with the first opening 23 through the flow guide structure 21; the condenser 11 is at least partially located in the space enclosed by the flow guide structure 21.
During the normal operation of the pressurized water reactor nuclear power station, the waste heat discharge system is in an isolated standby state. When a power outage accident of the whole plant occurs in the power station, the main pump stops running on one loop, and the residual heat of the reactor core is led out from the one loop through the feed water and the discharged steam on the secondary side of the steam generator 1 in a natural circulation mode; when the secondary side completely loses the water supply, the waste heat discharge system can be put into operation.
Similar to the secondary side passive waste heat removal system in the prior art, in the present embodiment, the flowing medium in the steam generator 1, the condenser 11 and the connecting pipe therebetween circulates naturally, so as to guide the waste heat from the secondary side of the steam generator 1 to the condenser. In this embodiment, the condenser 11 is a water-cooling and air-cooling dual-purpose condenser; the cooling water tank 18 is pre-stored with cooling water, and in the early stage of the operation of the waste heat discharge system, the condenser 11 is cooled by the cooling water, and the water vapor generated by boiling of the cooling water due to heat absorption is discharged to the atmosphere through the first opening 23; in the later stage of the operation of the waste heat discharging system, the water level in the cooling water tank 18 is reduced to a certain degree, cold air in the atmospheric environment or an external air source enters the cooling water tank 18 from the second opening 22, the air is led to the condenser 11 by the flow guide structure 21, then due to the steam heating effect in the heat transfer pipe of the condenser 11, the air in the inner channel and the outer channel of the flow guide structure 21 generates a density difference to form a natural circulation cooling mode, and the heated air is discharged to the atmospheric environment from the first opening 23. In addition, in the present embodiment, the whole or part of the condenser 11 is disposed in the space enclosed by the flow guide structure 21, so that the steam or the heating gas generated at the condenser 11 can be more easily discharged through the flow guide structure 21 and the first opening 23.
Fig. 2 shows the thermal power change law of the decay heat of the reactor core after a certain million kilowatt pressurized water reactor nuclear power station is shut down (the solid line in the figure is an equation curve formed by fitting all points), and it can be seen that the thermal power of the decay in the early stage of an accident is larger than the thermal power of the decay in the later stage. The embodiment of the utility model provides a waste heat discharge system can in time derive the reactor core waste heat through the higher water-cooling mode of cooling efficiency in the early stage of accident, and in the accident later stage, along with the reactor core waste heat is derived, its requirement to cooling efficiency reduces gradually, can not need extra moisturizing or use other active equipment, maintains the derivation of reactor core waste heat always through the air cooling mode, effectively guarantees the security of reactor. Therefore, the waste heat discharge system can be well applied to accident conditions such as power failure of the whole pressurized water reactor nuclear power station.
Optionally, an air outlet channel located outside the cooling water tank 18 is further disposed at the first opening 23, and a space enclosed by the air outlet channel and the flow guide structure 21 is communicated with each other.
The air outlet channel may be composed of a chimney 24 and a pipeline connecting the chimney 24 and the cooling water tank 18, so that when the steam or the heating gas generated in the cooling water tank 18 is exhausted to the atmosphere, the density height difference of the cold and hot channels is larger, and a better cooling effect is obtained.
Optionally, the first opening 23 and the second opening 22 are located at the top of the cooling water tank 18.
As shown in fig. 1, the first opening 23 and the second opening 22 are both located on the upper end surface of the cooling water tank 18; in addition, the flow guide structure 21 extends downwards from the first opening 23, and a certain gap is formed between the flow guide structure and the inner bottom surface of the cooling water tank 18; during the air cooling process, the outside air, such as air in the atmospheric environment, enters the cooling water tank 18 from the second opening 22, reaches the space enclosed by the flow guide structure 21 through the gap, absorbs the heat in the condenser 11, and is finally discharged through the first opening 23. The first opening 23 and the second opening 22 are arranged at the top, so that the flow path of the gas in the cooling water tank 18 can be increased, and the waste heat can be more fully absorbed and taken away.
Of course, in some possible embodiments, the second opening 22 may also be present on a side wall of the cooling water tank 18. Since the cooling water tank 18 is not normally completely filled with cooling water, the normal standby liquid level may be at a normal water level Ln as shown in fig. 1, and a certain distance exists between the normal water level Ln and the upper wall of the cooling water tank 18, and the second opening 22 may be provided at a side wall of the corresponding position. Of course, if a check valve is provided at the second opening 22, the second opening 22 may be located below the normal water level Ln.
Optionally, the cross-sectional shape of the flow guiding structure 21 is annular.
In this embodiment, the flow guide structure 21 is substantially a circular flow guide structure to facilitate installation and to match the shape of the condenser 11. Of course, in some alternative embodiments, the flow guiding structure 21 may also be a tubular structure with a polygonal cross section (e.g. rectangular, etc.), or a plate-like structure with a gap only with the inner bottom surface of the cooling water tank 18, which is selected according to actual needs.
Optionally, the number of the second openings 22 is multiple, and the multiple second openings 22 are arranged at intervals around the flow guide structure 21.
Through set up a plurality of second openings 22 around water conservancy diversion structure 21 for in the in-process of air cooling, outside gas can reach the different positions of condenser 11 more evenly and absorb heat, promotes waste heat emission effect.
In some possible embodiments, at least 1/2 of the condenser 11 extends into the space enclosed by the flow guiding structure 21, so that the gas can be effectively discharged from the first opening 23 through the flow guiding structure 21 in time after being heated.
Optionally, an air inlet structure is disposed at the second opening 22, and the air inlet structure includes an air valve or a check valve.
The arrangement of the air inlet structure can effectively reduce the evaporation loss of the cooling water in the cooling water tank 18 under the normal operation condition. In the operation process of the waste heat discharging system, when the water amount in the cooling water tank 18 is reduced to a certain degree, the air inlet structure is in an open state due to the action of pressure difference, and external air enters the cooling water tank 18. Further optionally, the air intake structure may further include an air filtering device and the like, which are configured according to actual needs.
Optionally, a thermometer is provided on the pipe connecting the condenser 11 and the steam generator 1.
The temperature on the pipeline can be monitored by arranging the thermometer, so that the condition that the residual heat removal system is started by steam leakage or misoperation can be found in time.
In this embodiment, the steam generator 1 is connected with a main steam pipeline 2 and a main water supply pipeline 3, wherein: the main steam pipeline 2 is connected with a main steam system 25 and used for doing work on a steam turbine and the like; the main water supply pipe 3 is connected to an auxiliary water supply system 26 for supplying water to the steam generator 1, and the main water supply pipe 3 is further provided with a first isolation valve 4.
The above-mentioned pipe connecting the condenser 11 and the steam generator 1 includes a heat-discharging steam line and a condensed water return line; the two ends of the heat-extraction steam pipeline are respectively connected with the main steam pipeline 2 and the first interface of the condenser 11, and the two ends of the condensed water return pipeline are respectively connected with the main water supply pipeline 3 and the second interface of the condenser 11.
The nuclear power system also comprises a containment; the heat rejection vapor line comprises a first vapor line 5 and a second vapor line 6 in communication with each other; the condensed water return pipeline comprises a first return pipeline 12 and a second return pipeline 15 which are communicated with each other; wherein, the first steam line 5 penetrates the containment through the first containment penetration piece 7, and the second water return line 15 penetrates the containment through the second containment penetration piece 16; the second steam line 10 and the first return line 12 are respectively connected to a first port of the condenser 11 and a second port of the condenser 11.
The first steam pipeline 5 and the second steam pipeline 10 are respectively connected to two ends of the second isolation valve 6, a third isolation valve 9 is arranged on the second steam pipeline 10, and a first thermometer 8 is arranged between the second isolation valve 6 and the third isolation valve 9. The first water return pipeline 12 and the second water return pipeline 15 are respectively connected to two ends of the fourth isolation valve 13, a fifth isolation valve 17 is arranged on the second water return pipeline 15, and a second thermometer 14 is arranged between the containment vessel and the fourth isolation valve 13. Optionally, the third isolation valve 9 is a normally closed flow regulating isolation valve, the fifth isolation valve 17 being a check valve. Whether the residual heat removal system is activated due to the occurrence of a steam leak or a malfunction can be monitored by the first thermometer 8 and the second thermometer 14.
In practical application, the number and the positions of the thermometers can be adjusted according to actual needs.
In order to better realize the natural circulation of flowing media in a heat extraction steam pipeline and a condensed water return pipeline, the arrangement of the pipelines has height difference and gradient change; in a possible embodiment, as shown in figure 1, the local high point of the above-mentioned line is located between the third isolation valve 9 and the cooling water tank 18, and the local low point is located between the fourth isolation valve 13 and the second thermometer 14. Of course, in practical applications, the local high points and the local low points may be determined according to actual needs.
Alternatively, the number of the cooling water tanks 18 is plural, and the plural cooling water tanks 18 are communicated with each other through a communication line 19.
In this embodiment, three cooling water tanks 18 are provided and connected two by two via communication lines 19, and a sixth isolation valve 20 is provided on the communication line 19, and the sixth isolation valve 20 may be a normally closed isolation valve. Each cooling water tank 18 is provided with a corresponding condenser 11 for connecting and conducting heat to the different steam generators 1. Through the communicating pipe 19, the water levels in different cooling water tanks 18 can be balanced, accident conditions such as heat exchange abnormity of a certain steam generator 1 can be effectively responded, and the waste heat can be effectively discharged.
Of course, in practical applications, the number of the cooling water tanks 18 can be selected according to practical needs.
In a possible embodiment, a reserve tank can also be provided, which serves only for storing water, wherein the condenser 11 or the like is not provided, which communicates with the cooling water tank 18 and serves to replenish the cooling water tank 18 after the cooling water in the cooling water tank 18 has been consumed.
The embodiment of the utility model provides a waste heat discharge system can take place the outage of whole factory simultaneously and lose completely under the accident operating mode of initiative water supply function, through the long-term steady operation of passive mode, derives the reactor core waste heat, maintains that the reactor is in the safe state.
The embodiment of the utility model also provides a nuclear power system, including steam generator 1 and the above-mentioned waste heat discharge system; the steam generator 1 is connected with the condenser 11 through a pipe.
In particular, the nuclear power system further comprises a main steam pipe 2 and a main water feed pipe 3 connected to the steam generator 1, wherein: the main steam pipeline 2 is connected with a main steam system 25 and used for doing work on a steam turbine and the like; the main water feed pipe 3 is connected to an auxiliary water feed system 26. The inlet and outlet of the condenser 11 are connected to the main steam line 2 of the steam generator 1 by means of pipes, respectively.
In practical application, after the power outage accident of the whole plant occurs in the power station, the main pump stops running, the residual heat of the reactor core is derived from the water supply and the discharged steam of the primary circuit through the secondary side of the steam generator 1 in a natural circulation mode, and when the water supply is completely lost, the secondary side of the steam generator triggers the steam discharge atmosphere valve to close due to low liquid level, so that the residual heat discharge system is started.
The embodiment of the utility model provides a nuclear power system can take place the whole power plant outage simultaneously the power plant loses under the Design Extension Condition (DEC) of all active reactor core waste heat discharge ability, utilizes the steam/water of secondary side or the density difference of cold and hot air as drive power, moves with passive mode, passes through the water-cooling mode when the early reactor core decay heat of accident is big, cools off steam in the condenser to derive the reactor core decay heat; after the water in the cooling water tank is evaporated, the valves of the air inlet (corresponding to the second opening) and the air outlet (corresponding to the first opening) are opened, so that the steam in the condenser is continuously cooled in an air cooling mode, the long-term derivation of the waste heat of the reactor core under the DEC working condition is ensured, and the reactor is maintained in a safe state.
On the basis of the waste heat discharge system, the following waste heat discharge method can be applied:
when a preset accident condition signal is acquired, waste heat is conducted from the steam generator 1 to the condenser 11;
the condenser 11 is cooled by the cooling water in the cooling water tank 18, and the water vapor generated by heating the cooling water is discharged from the first opening 23 along the flow guide structure 21;
when the water level in the cooling water tank 18 drops to a water level threshold, the condenser 11 is cooled by the cold air introduced from the second opening 22, and the hot air generated by heating the cold air is discharged from the first opening 23 along the flow guide structure 21.
When a preset accident condition signal is acquired, the release valves on the heat-extraction steam pipeline and the condensed water return pipeline can be controlled to be opened, and the waste heat is guided to the condenser 11 from the steam generator 1.
It should be noted that the water level threshold may be a water level value exposing a gap between the diversion structure 21 and the inner bottom surface of the cooling water tank 18, or may not be a specific water level value, in practical applications, when the water level in the cooling water tank 18 drops to a certain depth to form a negative pressure, the external air may enter the cooling water tank 18 through the second opening 22.
The waste heat discharge method can timely discharge the reactor core waste heat in the early stage of the accident condition through the water cooling mode, and the derivation of the reactor core waste heat is maintained in the middle and later stages through the air cooling mode, so that the safety of the reactor is ensured.
The following describes a specific application embodiment of the waste heat removal system:
during the normal operation of the power station, the whole waste heat discharge system is in an isolation standby state. At this time, the containment isolation valve (second isolation valve 6) and the flow regulating isolation valve (third isolation valve 9) respectively positioned on the first steam pipeline 5 and the second steam pipeline are in a closed state, the containment isolation valve (fourth isolation valve 13) on the second water return pipeline 15 is in a closed state, the second steam pipeline 10 is in a nitrogen micro-positive pressure protection state, and the inside of the heat transfer pipe of the water-cooling and air-cooling dual-purpose condenser 11 and the inside of the first water return pipeline 12 and the second water return pipeline 15 are in a water filling state. The out-of-containment cooling water tank 18 is filled to a normal standby level (as shown in fig. 1), the air inlet (second opening 22) and the air outlet (first opening 23) are in a closed state, and the sixth isolation valve 20 on the communication line 19 is in a closed state. Whether the system starts the residual heat removal system due to steam leakage or malfunction can be monitored through the first thermometer 8 and the second thermometer 14 on the second steam line 10 and the second water return line 15.
When the power station has a station blackout accident, the main pump is shut down, the residual heat of the reactor core is led out from a primary loop through the feed water and the exhaust steam on the secondary side of the steam generator 1 in a natural circulation mode, when the feed water is completely lost, the steam exhaust atmosphere valve is closed by triggering the low liquid level on the secondary side of the steam generator, the residual heat exhaust system is started, at this time, the out-of-containment isolation valve on the first steam pipeline 5 and the flow regulating isolation valve on the second steam pipeline 10 are firstly opened, the out-of-containment isolation valve on the second water return pipeline 15 is opened after about 20 seconds, the secondary side supplementary water amount of the water storage steam generator 1 is returned in the heat transfer pipe of the dual-purpose condenser 11, the reserved first water return pipeline 12 and the reserved second water return pipeline 15, and the. The heat is conducted to the water in the cooling water tank 18, at the early stage of the operation of the waste heat discharge system, the water in the cooling water tank 18 is boiled into steam and discharged to the atmospheric environment through the air outlet, when the water amount in the cooling water tank 18 is reduced to a certain degree, the air inlet at the top of the cooling water tank 18 is in an open state due to the action of pressure difference, the water-cooling and air-cooling dual-purpose condenser 11 is in an air cooling mode, the air in the atmospheric environment enters the cooling water tank 18 from the air inlet, the air is introduced into the bottom of the dual-purpose condenser 11 by the flow guide structure 21, then due to the steam heating effect inside the heat transfer pipe of the dual-purpose condenser 11, the air in the inner channel and the outer channel of the flow guide structure 21 generates density difference to drive the. Since the air cooling mode uses air, it is possible to maintain cooling for a long period of time without any other active equipment during the mid-to-long period of the accident.
Fig. 2 shows a reactor core decay heat power change curve of a certain one million kilowatt pressurized water reactor nuclear power station, according to the reactor core decay heat power change rule shown in fig. 2 and the cooling performance of a water-cooling-air cooling dual-purpose condenser, the better cooling effect in the water-cooling stage is just right matched with the early-stage larger decay heat level of an accident, along with the accident process, the reactor core decay heat becomes smaller and smaller, the water capacity in the cooling water tank 18 is also reduced and reduced, and finally the complete evaporation is performed, at the moment, the smaller decay heat power in the later stage of the accident can be just met, at the moment, the waste heat discharge system can operate without additional water supplement and other active devices, the derivation of the reactor core waste heat can be always maintained, and the integrity of the reactor.
The foregoing is directed to the preferred embodiments of the present invention, and it will be understood by those skilled in the art that various changes and modifications may be made without departing from the principles of the invention, and that such changes and modifications are intended to be included within the scope of the invention.
Claims (9)
1. The utility model provides a waste heat removal system, is applied to nuclear power system, nuclear power system includes steam generator, its characterized in that, waste heat removal system includes:
the condenser is connected with the steam generator through a pipeline;
the cooling water tank is internally provided with an accommodating cavity for accommodating the condenser, and the accommodating cavity is communicated with an external space through a first opening and a second opening which are arranged on the cooling water tank; the first opening is provided with a flow guide structure extending into the accommodating cavity, and the second opening is communicated with the first opening through the flow guide structure; the condenser is at least partially positioned in a space enclosed by the flow guide structure.
2. The residual heat removal system according to claim 1, wherein an air outlet channel located outside the cooling water tank is further arranged at the first opening, and a space enclosed by the air outlet channel and the flow guide structure is communicated with each other.
3. The residual heat removal system according to claim 1, wherein the first opening and the second opening are located at a top of the cooling water tank.
4. The residual heat removal system according to claim 1, wherein the flow guide structure is annular in cross-sectional shape.
5. The residual heat removal system according to claim 4, wherein the number of the second openings is multiple, and the multiple second openings are arranged around the flow guide structure at intervals.
6. The residual heat removal system according to claim 1, wherein an air inlet structure is arranged at the second opening, and the air inlet structure comprises an air valve or a check valve.
7. The heat removal system of claim 1, wherein a temperature gauge is disposed on tubing connecting the condenser and the steam generator.
8. The residual heat removal system according to claim 1, wherein the number of the cooling water tanks is plural, and the plural cooling water tanks are communicated with each other through a communication line.
9. A nuclear power system comprising a steam generator and a residual heat removal system as claimed in any one of claims 1 to 8;
the steam generator is connected with the condenser through a pipeline.
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| CN201921784982.2U CN210837199U (en) | 2019-10-22 | 2019-10-22 | Waste heat discharge system and nuclear power system |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113053548A (en) * | 2021-03-17 | 2021-06-29 | 西安热工研究院有限公司 | High-temperature gas cooled reactor with natural circulation reactor core waste heat derivation function |
| CN113140338A (en) * | 2021-03-26 | 2021-07-20 | 中广核工程有限公司 | Emergency waste heat discharging and water supplementing system for nuclear power plant |
| CN114082247A (en) * | 2021-11-05 | 2022-02-25 | 中广核研究院有限公司 | Steam-water separator and waste heat deriving system |
-
2019
- 2019-10-22 CN CN201921784982.2U patent/CN210837199U/en active Active
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113053548A (en) * | 2021-03-17 | 2021-06-29 | 西安热工研究院有限公司 | High-temperature gas cooled reactor with natural circulation reactor core waste heat derivation function |
| CN113140338A (en) * | 2021-03-26 | 2021-07-20 | 中广核工程有限公司 | Emergency waste heat discharging and water supplementing system for nuclear power plant |
| WO2022198826A1 (en) * | 2021-03-26 | 2022-09-29 | 中广核工程有限公司 | Emergency residual heat removal and water replenishing system for nuclear power plant |
| CN114082247A (en) * | 2021-11-05 | 2022-02-25 | 中广核研究院有限公司 | Steam-water separator and waste heat deriving system |
| CN114082247B (en) * | 2021-11-05 | 2023-02-03 | 中广核研究院有限公司 | Steam-water separator and waste heat deriving system |
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