CN214279618U - Nuclear power station cooling system - Google Patents
Nuclear power station cooling system Download PDFInfo
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- CN214279618U CN214279618U CN202120365367.9U CN202120365367U CN214279618U CN 214279618 U CN214279618 U CN 214279618U CN 202120365367 U CN202120365367 U CN 202120365367U CN 214279618 U CN214279618 U CN 214279618U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model provides a nuclear power station cooling system is applied to the nuclear power station, the nuclear power station includes containment and reactor pressure vessel, reactor pressure vessel set up in the containment, last heat pipe section and the cold pipe section of being provided with of reactor pressure vessel, nuclear power station cooling system includes: a first cooling subsystem located within the containment vessel and in communication with the heated and/or cold tube sections; a second cooling subsystem located outside the containment vessel and in communication with the heat pipe section and the cold pipe section, respectively. The embodiment of the utility model provides a simplify and carried out refrigerated control mode to the reactor, and made control mode more reliable and stable.
Description
Technical Field
The utility model relates to a nuclear power technology field, in particular to nuclear power station cooling system.
Background
With the development of nuclear power technology, the power generation of nuclear power stations occupies more and more important position in the life of people. When a nuclear power plant has an accident, in the existing nuclear power plant, water is supplemented to the reactor and heat is led out through an active system, so that the cooling function of the reactor is completed. But the control mode of the active system for cooling the reactor is complex.
SUMMERY OF THE UTILITY MODEL
An object of the embodiment of the utility model is to provide a nuclear power station cooling system has solved the current active system and has carried out the comparatively complicated problem of refrigerated control mode to the reactor.
In order to achieve the above object, an embodiment of the present invention provides a nuclear power station cooling system, which is applied to a nuclear power station, the nuclear power station includes a containment and a reactor pressure vessel, the reactor pressure vessel set up in the containment, be provided with a heat pipe section and a cold pipe section on the reactor pressure vessel, the nuclear power station cooling system includes:
a first cooling subsystem located within the containment vessel and in communication with the heated and/or cold tube sections;
a second cooling subsystem located outside the containment vessel and in communication with the heat pipe section and the cold pipe section, respectively;
wherein the height of the first cooling subsystem and the second cooling subsystem in the containment vessel is higher than the height of the reactor pressure vessel in the containment vessel.
Optionally, the nuclear power plant further comprises a pressurizer in communication with the heat pipe section.
Optionally, the first cooling subsystem includes a core makeup tank and a first isolation valve, a water inlet of the core makeup tank is communicated with the pressurizer, and a water outlet of the core makeup tank is communicated with the cold leg section through the first isolation valve.
Optionally, the first cooling subsystem comprises a safety injection tank and a second isolation valve, and a water outlet of the safety injection tank is communicated with the cold pipe section through the second isolation valve.
Optionally, the first cooling subsystem comprises a refueling water tank, a water outlet of the refueling water tank is communicated with the cold pipe section, and/or the water outlet of the refueling water tank is arranged towards the outer surface of the reactor pressure vessel.
Optionally, the first cooling subsystem still includes first pressure relief valve, the one end of first pressure relief valve with the stabiliser intercommunication, the other end of first pressure relief valve with the water tank intercommunication reloads.
Optionally, the first pressure relief valve comprises at least two pressure relief valve banks in parallel.
Optionally, the first cooling subsystem further comprises a second pressure relief valve, one end of the second pressure relief valve is communicated with the heat pipe section, and the other end of the second pressure relief valve is communicated with the external environment in the containment and/or the refueling water tank.
Optionally, the nuclear power plant cooling system further comprises a heat exchange water tank, the heat exchange water tank is arranged on the outer surface of the containment, a first heat exchanger is further arranged in the containment, and a water outlet and a water inlet of the first heat exchanger are respectively communicated with the heat exchange water tank.
Optionally, the second cooling subsystem further includes a second heat exchanger, the second heat exchanger is located in the heat exchange water tank, a water inlet of the second heat exchanger is communicated with the hot pipe section, and a water outlet of the second heat exchanger is communicated with the cold pipe section.
One of the above technical solutions has the following advantages or beneficial effects:
the embodiment of the utility model provides an in, nuclear power station cooling system is applied to the nuclear power station, the nuclear power station includes containment and reactor pressure vessel, reactor pressure vessel set up in the containment, last heat pipe section and the cold pipe section of being provided with of reactor pressure vessel, nuclear power station cooling system includes: a first cooling subsystem located within the containment vessel and in communication with the heated and/or cold tube sections; a second cooling subsystem located outside the containment vessel and in communication with the heat pipe section and the cold pipe section, respectively; wherein the height of the first cooling subsystem and the second cooling subsystem in the containment vessel is higher than the height of the reactor pressure vessel in the containment vessel. Therefore, the first cooling subsystem and the second cooling subsystem are higher than the reactor pressure vessel in the containment, when the reactor pressure vessel has an accident, the first cooling subsystem and the second cooling subsystem can inject water into the reactor pressure vessel under the action of gravity, so that the reactor in the reactor pressure vessel is cooled, the control mode of cooling the reactor is simplified, and the control mode is more reliable and stable.
Drawings
Fig. 1 is a schematic structural diagram of a cooling system of a nuclear power plant according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, of the embodiments of the present invention. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts belong to the protection scope of the present invention.
Referring to fig. 1, fig. 1 is a schematic structural diagram of a cooling system of a nuclear power station, as shown in fig. 1, the cooling system of the nuclear power station is applied to a nuclear power station, the nuclear power station includes a containment vessel 100 and a reactor pressure vessel 200, the reactor pressure vessel 200 is disposed in the containment vessel 100, a heat pipe section 201 and a cold pipe section 202 are disposed on the reactor pressure vessel 200, and the cooling system of the nuclear power station includes:
a first cooling subsystem located within the containment vessel 100 and in communication with the heated tube section 201 and/or the cold tube section 202;
a second cooling subsystem, which is located outside the containment vessel 100 and is respectively communicated with the hot pipe section 201 and the cold pipe section 202;
wherein the height of the first cooling subsystem and the second cooling subsystem in the containment vessel 100 is higher than the height of the reactor pressure vessel 200 in the containment vessel 100.
Wherein, the utility model discloses the theory of operation of embodiment can see following expression:
because the heights of the first cooling subsystem and the second cooling subsystem in the containment vessel 100 are higher than the height of the reactor pressure vessel 200 in the containment vessel 100, when an accident occurs to the reactor pressure vessel 200, the first cooling subsystem and the second cooling subsystem can inject water into the reactor pressure vessel 200 under the action of gravity or form natural circulation in the heat exchanger (see the following related expressions about the first heat exchanger 80 and the second heat exchanger 90 specifically), so that the cooling of the reactor in the reactor pressure vessel 200 is realized, the control mode of cooling the reactor is simplified, and the control mode is more reliable and stable.
It should be noted that the cooling system formed by the first cooling subsystem and the second cooling subsystem in the embodiment of the present invention may be referred to as a passive cooling system.
Where the hot pipe section 201 may be referred to as a primary circuit hot pipe section and the cold pipe section 202 may be referred to as a primary circuit cold pipe section. In addition, referring to fig. 1, a steam generator 203 may also be disposed on the heat pipe section 201.
It should be noted that, in the embodiment of the present invention, the first cooling subsystem and the second cooling subsystem are both directly connected to at least one of the existing heat pipe section 201 and the existing cold pipe section 202 of the nuclear power plant, so that it is not necessary to separately add an additional pipeline to the opening on the reactor pressure vessel 200, thereby further enhancing the safety performance of the reactor pressure vessel 200, and simultaneously, the use cost is also reduced.
As an alternative embodiment, the nuclear power plant further comprises a voltage stabilizer 40, and the voltage stabilizer 40 is communicated with the heat pipe section 201. In this way, the pressure regulator 40 can ensure that the pressure within the heat pipe section 201 is stable.
As an alternative embodiment, referring to fig. 1, the first cooling subsystem includes a core makeup tank 10 and a first isolation valve 11, the inlet of the core makeup tank 10 is communicated with the pressurizer 40, and the outlet of the core makeup tank 10 is communicated with the cold leg 202 through the first isolation valve 11.
Wherein, because the water inlet of reactor core makeup water tank 10 communicates with stabiliser 40, like this, stabiliser 40 can guarantee that the pressure of the water inlet of reactor core makeup water tank 10 is higher, after the nuclear power station takes place the accident, the pressure in reactor pressure vessel 200, heat pipe section 201 and cold leg 202 drops, first isolation valve 11 between reactor core makeup water tank 10 and the cold leg 202 is opened, because the water inlet department pressure of reactor core makeup water tank 10 is higher, under the high pressure effect, the cooling water in reactor core makeup water tank 10 pours into cold leg 202 into through the delivery port, thereby realize the water injection to reactor pressure vessel 200 and the cooling to the reactor in reactor pressure vessel 200.
It should be noted that the opening and closing of the first isolation valve 11 can be controlled by a wire, for example: the controller may be electrically connected to the first isolation valve 11, and when the nuclear power plant has no accident, the controller may control the first isolation valve 11 to close; when an accident occurs in the nuclear power plant, the controller may control the first isolation valve 11 to be opened.
In addition, the opening and closing of the first isolation valve 11 may be controlled wirelessly, for example: the controller may be wirelessly connected to the first isolation valve 11, and when no accident occurs in the nuclear power plant, the controller may send a first signal to the first isolation valve 11 to control the first isolation valve 11 to close; in case of an accident in the nuclear power plant, the controller may send a second signal to the first isolation valve 11 to control the first isolation valve 11 to open. Or, when the nuclear power plant has not suffered an accident, the controller does not send a signal to the first isolation valve 11, and only when the nuclear power plant has suffered an accident, the controller sends a control signal to the first isolation valve 11 to control the first isolation valve 11 to open.
The utility model discloses in the embodiment, first cooling subsystem includes reactor core makeup tank 10 and first isolation valve 11, and like this, when the nuclear power station accident, reactor core makeup tank 10 can realize the cooling to reactor pressure vessel 200 reactor to the security performance of reactor in reactor pressure vessel 200 has been improved.
It should be noted that, as an alternative embodiment, referring to fig. 1, the first isolation valve 11 and the cold pipe segment 202 may be communicated through the first check valve 12, so that the phenomenon that cold water in the cold pipe segment 202 flows back to the core makeup tank 10 may be avoided, thereby enhancing the safety performance of the core makeup tank 10.
After the water level in the pressurizer 40 is lowered, the steam in the pressurizer 40 can also enter the core makeup tank 10, so that the cooling water in the core makeup tank 10 is injected into the cold leg 202 at a high speed by the steam to cool the reactor in the reactor pressure vessel 200. That is to say: under the effect of the voltage stabilizer 40, the water injection requirement under various accident working conditions can be met, and the reactor can be cooled better.
As an alternative embodiment, referring to fig. 1, the first cooling subsystem includes a safety injection tank 20 and a second isolation valve 21, and the water outlet of the safety injection tank 20 is communicated with the cold pipe section 202 through the second isolation valve 21.
The safety injection box 20 may include inert gas, such as: the nitrogen gas can be contained in the safety injection tank 20, and the nitrogen gas can be generated by or required by other parts of the nuclear power plant, so that the nitrogen gas can be reused by the safety injection tank 20 and other parts of the nuclear power plant, the use cost of the nuclear power plant is further reduced, and the economic performance of the nuclear power plant is improved.
In addition, because the safety injection tank 20 contains inert gas, the pressure in the safety injection tank 20 can be higher, when the pressure of the cold pipe section 202 is reduced to the pressure in the safety injection tank 20, the second isolation valve 21 between the safety injection tank 20 and the cold pipe section 202 is automatically opened, cooling water in the safety injection tank 20 is injected into the cold pipe section 202, and water injection to the reactor pressure vessel 200 and cooling to the reactor are realized.
In the embodiment of the present invention, the safety injection box 20 can further enhance the cooling effect on the reactor pressure vessel 200.
It should be noted that, as an alternative embodiment, referring to fig. 1, the second isolation valve 21 may also communicate with the cold pipe section 202 through the second check valve 22, and a specific description of the second check valve 22 may refer to the corresponding description of the first check valve 12, which has the corresponding beneficial technical effects.
As an alternative embodiment, the safety injection tank 20 and the cold pipe section 202 can be communicated through a regulating valve or a regulating orifice plate, so that the flow rate of the injection water from the safety injection tank 20 to the cold pipe section 202 can be controlled and regulated through the regulating valve or the regulating orifice plate, so as to better meet the requirement of the injection water in the accident condition.
It should be noted that the nitrogen pressure and the amount of the safety injection tank 20 can be designed according to the requirements of different nuclear power plants, and the requirements of accident analysis need to be met.
As an alternative embodiment, referring to fig. 1, the first cooling subsystem includes a refueling water tank 30, the water outlet of the refueling water tank 30 is communicated with the cold pipe section 202, and/or the water outlet of the refueling water tank 30 is disposed toward the outer surface of the reactor pressure vessel 200.
The utility model discloses in the embodiment, when pressure in the cold tube section 202 reduces to the pressure in the refueling water tank 30, the refueling water tank 30 can be through cold tube section 202 to the inside cooling water that injects into of reactor pressure vessel 200, also can be directly to reactor pressure vessel 200's surface injection cooling water to strengthened the inside and the outside cooling effect of reactor pressure vessel 200 to reactor pressure vessel 200, simultaneously, still make cooling method and the cooling position to reactor pressure vessel 200 more diversified and flexible activation.
It should be noted that the refueling water tank 30 may also be referred to as an in-containment refueling water tank, the water outlet of the refueling water tank 30 may be communicated with the cold pipe section 202 through a third isolation valve 31, and the control principle of the third isolation valve 31 may refer to the above-mentioned related description of the control principle of the first isolation valve 11 and the second isolation valve 21, and has the same beneficial technical effects, and details thereof are not repeated herein.
For example: the third isolation valve 31 may be provided with a sensor, and when the sensor detects that the temperature value of the third isolation valve 31 is greater than a preset temperature value, and/or the pressure value is greater than a preset pressure value, the controller may control the third isolation valve 31 to be opened, otherwise, the controller may control the third isolation valve 31 to be closed.
In addition, as an alternative embodiment, referring to fig. 1, the third isolation valve 31 may communicate with the cold pipe section 202 through the third check valve 32.
As an alternative embodiment, referring to fig. 1, the first cooling subsystem further includes a first pressure relief valve 50, one end of the first pressure relief valve 50 is communicated with the pressure stabilizer 40, and the other end of the first pressure relief valve 50 is communicated with the refueling water tank 30.
In this way, the first pressure relief valve 50 can reduce the pressure in the loop consisting of the hot pipe section 201 and the cold pipe section 202 to a pressure (which may also be referred to as a head) at which the cooling water in the safety injection tank 20 or the change water tank 30 can be injected into the cold pipe section 202, thereby facilitating the injection of the cooling water in the change water tank 30 into the cold pipe section 202.
It should be noted that the first pressure relief valve 50 may be a safety valve or a burst valve, so as to enhance the diversity of the first pressure relief valve 50 and, at the same time, enhance the safety of the first pressure relief valve 50. Additionally, the first pressure relief valve 50 may also be referred to as an active on-regulator pressure relief valve.
It should be noted that, as an alternative embodiment, the first pressure relief valve 50 may include at least two pressure relief valve banks connected in parallel, so that different pressure relief valve banks may be opened to relieve pressure according to the accident process and the pressure inside the pressure stabilizer 40, thereby enhancing the usability of the first pressure relief valve 50; meanwhile, the other end of the first pressure relief valve 50 is connected with the refueling water tank 30, so that the fluid medium in the pressure stabilizer 40 can be released into the refueling water tank 30, the direct release into the containment vessel 100 is avoided, and the pollution to the environment in the containment vessel 100 is reduced.
As an alternative embodiment, referring to fig. 1, the first cooling subsystem further comprises a second pressure relief valve 60, one end of the second pressure relief valve 60 is in communication with the heat pipe section 201, and the other end of the second pressure relief valve 60 is in communication with the external environment inside the containment vessel 100 and/or the refueling water tank 30. In this way, the medium in the second pressure relief valve 60 can be released into the containment vessel 100 or the refueling water tank 30, so that a rapid depressurization of the heat pipe section 201 can be achieved.
It should be noted that, since the second pressure relief valve 60 is directly communicated with the heat pipe section 201, the valve caliber and the discharge flow of the second pressure relief valve 60 can be larger than those of the first pressure relief valve 50, so that the pressure of the heat pipe section 201 can be reduced more rapidly.
As an optional implementation manner, referring to fig. 1, the cooling system for a nuclear power plant further includes a heat exchange water tank 70, the heat exchange water tank 70 is disposed on an outer surface of the containment vessel 100, a first heat exchanger 80 is further disposed in the containment vessel 100, and a water outlet and a water inlet of the first heat exchanger 80 are respectively communicated with the heat exchange water tank 70.
The height of the first heat exchanger 80 in the containment vessel 100 may also be greater than the height of the reactor pressure vessel 200 in the containment vessel 100, and correspondingly, the height of the heat exchange water tank 70 may also be greater than the height of the first heat exchanger 80.
The utility model discloses in the embodiment, at the nuclear power station accident, under the condition that leads to temperature and pressure rise in the containment 100, the heat in the containment 100 is absorbed to the medium in the first heat exchanger 80, and the medium flows after being heated and gets into heat transfer water tank 70, is cooled off by the cooling water in the heat transfer water tank 70, and the medium after the cooling gets into again in the first heat exchanger 80, so forms natural circulation and derives the heat in the containment 100, and then guarantees the reactor cooling.
It should be noted that the first heat exchanger 80 may be referred to as an in-containment heat exchanger, and the heat exchange water tank 70 may be referred to as an out-of-containment water tank.
In addition, through the heat transfer between the first heat exchanger 80 and the heat exchange water tank 70, the heat of the reactor (which may also be understood as the reactor pressure vessel 200) can be finally led out of the containment vessel 100, so that the integrity of the containment vessel 100 is ensured, and the heat conduction performance of the containment vessel 100 is not depended on.
As an alternative embodiment, referring to fig. 1, the second cooling subsystem includes a second heat exchanger 90, the second heat exchanger 90 is located in the heat exchange water tank 70, a water inlet of the second heat exchanger 90 is communicated with the hot pipe section 201, and a water outlet of the second heat exchanger 90 is communicated with the cold pipe section 202.
It should be noted that, referring to fig. 1, the water outlet of the second heat exchanger 90 is denoted by a, and the connection position of the cold pipe section 202 and the water outlet of the second heat exchanger 90 is also denoted by a. In addition, a fourth isolation valve and a fourth check valve may also be disposed between the water outlet of the second heat exchanger 90 and the cold pipe section 202, which may specifically refer to corresponding descriptions of the first isolation valve 11 and the first check valve 12 in the foregoing embodiments, and details are not described here again.
The utility model discloses in the embodiment, second heat exchanger 90 is located heat exchange water tank 70, and second heat exchanger 90's water inlet is connected with hot pipe section 201, and second heat exchanger 90's delivery port and cold pipe section 202 intercommunication. When an accident occurs in a nuclear power plant, for example: when a secondary side accident of a steam generator occurs in a nuclear power plant, the second heat exchanger 90 can be started immediately, high-temperature steam in the heat pipe section 201 enters the second heat exchanger 90 and is cooled by a cooling medium in the heat exchange water tank 70, the cooled cooling medium (such as cooling water) enters the second heat exchanger 90 and flows into the cold pipe section 202 through a water outlet of the second heat exchanger 90, and a reactor (such as the reactor pressure vessel 200) is cooled through natural circulation. Thereby further enhancing the cooling effect on the reactor pressure vessel 200.
The second heat exchanger 90 may also be referred to as a passive waste heat removal heat exchanger.
In addition, the number of the second heat exchangers 90 can be selectively set according to the number of the cold pipe sections 202 and the hot pipe sections 201, for example: including 3 cold pipe sections 202 and 3 heat pipe sections 201 in the nuclear power station primary circuit, then can set up 3 second heat exchangers 90, say that every 1 can set up 1 second heat exchanger 90 in cold pipe section 202 and the heat pipe section 201, and then the thermal effective derivation of better assurance.
The above description is only for the specific embodiments of the present invention, but the protection scope of the present invention is not limited thereto, and any person skilled in the art can easily think of the changes or substitutions within the technical scope of the present invention, and all should be covered within the protection scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (10)
1. A nuclear power plant cooling system is applied to a nuclear power plant, the nuclear power plant comprises a containment vessel and a reactor pressure vessel, the reactor pressure vessel is arranged in the containment vessel, a heat pipe section and a cold pipe section are arranged on the reactor pressure vessel, and the nuclear power plant cooling system comprises:
a first cooling subsystem located within the containment vessel and in communication with the heated and/or cold tube sections;
a second cooling subsystem located outside the containment vessel and in communication with the heat pipe section and the cold pipe section, respectively;
wherein the height of the first cooling subsystem and the second cooling subsystem in the containment vessel is higher than the height of the reactor pressure vessel in the containment vessel.
2. The nuclear power plant cooling system of claim 1, further comprising a pressurizer in communication with the heat pipe section.
3. The nuclear power plant cooling system of claim 2, wherein the first cooling subsystem includes a core makeup tank having an inlet in communication with the pressurizer and a first isolation valve having an outlet in communication with the cold leg through the first isolation valve.
4. The nuclear power plant cooling system of claim 1, wherein the first cooling subsystem includes a safety injection tank and a second isolation valve, and a water outlet of the safety injection tank communicates with the cold pipe section through the second isolation valve.
5. The nuclear power plant cooling system of claim 2, wherein the first cooling subsystem includes a refueling water tank having a water outlet in communication with the cold pipe section and/or a water outlet disposed toward an exterior surface of the reactor pressure vessel.
6. The nuclear power plant cooling system of claim 5, wherein the first cooling subsystem further comprises a first pressure relief valve, one end of the first pressure relief valve being in communication with the pressurizer and the other end of the first pressure relief valve being in communication with the refueling water tank.
7. The nuclear power plant cooling system of claim 6, wherein the first pressure relief valve comprises at least two pressure relief valve banks in parallel.
8. The nuclear power plant cooling system of claim 5, wherein the first cooling subsystem further comprises a second pressure relief valve, one end of the second pressure relief valve being in communication with the heat pipe section, the other end of the second pressure relief valve being in communication with the external environment within the containment and/or the refueling water tank.
9. The nuclear power plant cooling system according to claim 1, further comprising a heat exchange water tank disposed on an outer surface of the containment, wherein a first heat exchanger is further disposed in the containment, and a water outlet and a water inlet of the first heat exchanger are respectively communicated with the heat exchange water tank.
10. The nuclear power plant cooling system of claim 9, wherein the second cooling subsystem includes a second heat exchanger, the second heat exchanger being located within the heat exchange water tank, a water inlet of the second heat exchanger being in communication with the hot pipe section and a water outlet of the second heat exchanger being in communication with the cold pipe section.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202120365367.9U CN214279618U (en) | 2021-02-07 | 2021-02-07 | Nuclear power station cooling system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202120365367.9U CN214279618U (en) | 2021-02-07 | 2021-02-07 | Nuclear power station cooling system |
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| Publication Number | Publication Date |
|---|---|
| CN214279618U true CN214279618U (en) | 2021-09-24 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN202120365367.9U Active CN214279618U (en) | 2021-02-07 | 2021-02-07 | Nuclear power station cooling system |
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| CN (1) | CN214279618U (en) |
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2021
- 2021-02-07 CN CN202120365367.9U patent/CN214279618U/en active Active
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