CN220189254U - Leakage detection device for nuclear power station - Google Patents
Leakage detection device for nuclear power station Download PDFInfo
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- CN220189254U CN220189254U CN202320173301.9U CN202320173301U CN220189254U CN 220189254 U CN220189254 U CN 220189254U CN 202320173301 U CN202320173301 U CN 202320173301U CN 220189254 U CN220189254 U CN 220189254U
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- gas supply
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- 238000001514 detection method Methods 0.000 title claims abstract description 62
- 238000002955 isolation Methods 0.000 claims description 18
- 230000001105 regulatory effect Effects 0.000 claims description 14
- 230000007704 transition Effects 0.000 claims description 13
- 229910000831 Steel Inorganic materials 0.000 claims description 9
- 239000010959 steel Substances 0.000 claims description 9
- 230000001276 controlling effect Effects 0.000 claims description 3
- 210000002445 nipple Anatomy 0.000 claims description 3
- 239000007789 gas Substances 0.000 abstract description 111
- 238000000034 method Methods 0.000 abstract description 16
- 238000007789 sealing Methods 0.000 abstract description 14
- 230000008569 process Effects 0.000 abstract description 10
- 239000002901 radioactive waste Substances 0.000 abstract description 10
- 230000000737 periodic effect Effects 0.000 abstract description 8
- 238000012360 testing method Methods 0.000 abstract description 6
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 9
- 239000002912 waste gas Substances 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 238000012423 maintenance Methods 0.000 description 4
- 229910052757 nitrogen Inorganic materials 0.000 description 4
- 230000002285 radioactive effect Effects 0.000 description 4
- 230000004308 accommodation Effects 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000000338 in vitro Methods 0.000 description 2
- 230000010354 integration Effects 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 238000012795 verification Methods 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 229910001873 dinitrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
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- Examining Or Testing Airtightness (AREA)
Abstract
The embodiment of the utility model discloses a leakage detection device for a nuclear power station. According to the leakage detection device for the nuclear power station, after a proper amount of gas passes through a system or equipment to be detected, the sealing performance of the system or equipment to be detected can be intuitively reflected through parameters such as pressure, temperature and the like displayed by the multi-pass display meter; the periodic tightness test requirement of the nuclear power station on the radioactive waste gas system can be met; the quick leak detection when personnel suspects leakage can be realized; the purpose of verifying the sealing performance of the device in advance under the condition of not connecting other process systems after personnel overhauls the exhaust gas system device can be achieved. The method solves the requirement that the staff of the nuclear power station needs to rapidly and conveniently verify the sealing performance of the radioactive waste gas system or the device.
Description
Technical Field
The embodiment of the utility model relates to the technical field of nuclear power equipment overhaul and maintenance, in particular to a leak detection device for a nuclear power station
Background
Pressurized water reactor and boiling water reactor nuclear power station are equipped with high-level hydrogen-containing radioactive waste gas system and low-level oxygen-containing radioactive waste gas system, and when the waste gas produced by power station is treated by classification, the waste gas can be discharged to environment by means of these two systems. In order to ensure that the periodic tightness test of the exhaust gas system is effectively developed or the personnel judge that the system and the components possibly have quick leakage detection when the risk of external leakage exists or the personnel carry out quick leakage detection after overhauling the components of the system, the tightness of the system needs to be verified by quick leakage detection equipment so as to prevent radioactive air from leaking after the system is put into operation. At present, ventilation leakage detection is mainly carried out by accessing a power station compressed air or nitrogen process system, which increases the burden of a pressure air and nitrogen system; the problem of difficult connection between the compressed air or nitrogen process system and the exhaust system also exists; there is also a pain point that the system or the component can not be quickly leaked because personnel can judge that the system or the component is likely to leak, and the system or the component is leaked again after the gas is introduced into the system or the component, so that maintenance and rework are caused.
Disclosure of Invention
The present utility model aims to solve at least one of the technical problems existing in the prior art or related art.
Therefore, the utility model provides a leak detection device for a nuclear power station, which comprises the following components:
a gas containment device;
a gas supply pipe, one end of which is connected to an output end of the gas accommodating device;
the connector is arranged at the other end of the gas supply pipe and is used for being connected with a system to be detected of the nuclear power station;
a control valve assembly provided on the gas supply pipe for controlling an opening degree, opening and closing of the gas supply pipe;
the multi-range display meter is arranged on the gas supply pipe and is used for displaying the pressure and the temperature of the gas in the gas supply pipe.
In one possible embodiment, the control valve assembly comprises: a pressure reducing valve, a needle-shaped regulating valve, and a check valve arranged in this order on the gas supply pipe in a direction from the gas accommodating device to the joint;
wherein the multi-pass display gauge is located between the check valve and the nipple.
In one possible embodiment, the control valve assembly further comprises:
the pressure relief isolation valve is communicated between the multi-range display meter and the connector.
In a possible embodiment, the leak detection device for a nuclear power plant further includes:
the pressure relief pipe, the pressure relief pipe intercommunication extremely the gas supply pipe, the pressure relief isolation valve sets up on the pressure relief pipe.
In a possible embodiment, the leak detection device for a nuclear power plant further includes:
the pressure gauge is communicated with the gas supply pipe and is positioned between the pressure reducing valve and the needle-shaped regulating valve.
In a possible embodiment, the leak detection device for a nuclear power plant further includes:
and one end of the transition joint is connected with the gas accommodating device, and the other end of the transition joint is connected with the gas supply pipe.
In one possible embodiment, the transition joint is a rotary joint.
In one possible embodiment, the gas supply pipe is made of an explosion-proof steel pipe.
In one possible embodiment, the gas supply pipe is arranged in an explosion-proof steel pipe.
In a possible embodiment, the gas-containing device is a portable gas cylinder.
Compared with the prior art, the utility model at least comprises the following beneficial effects:
the leakage detection device for the nuclear power station provided by the embodiment of the utility model comprises the gas accommodating device, the gas supply pipe, the connector, the control valve assembly and the multi-way display meter, and in the use process, when a system or a component of the nuclear power station is required to be detected, such as when a radioactive exhaust system of the nuclear power station is subjected to a periodic tightness test, after necessary system and component switching and isolation are established or personnel judge that the exhaust system is likely to have leakage through power station parameters and phenomena, the leakage detection device has the use condition when the sealing function of the system is required to be verified on line after the necessary system and component switching and isolation are established or after personnel overhaul the exhaust system device. When the connector on the gas supply pipe is connected with a system or equipment to be detected, the gas containing device can supply gas, and the gas exhausted by the gas containing device passes through the control valve assembly first, and a person can ensure that the system or equipment to be detected can reach the expected pressure and flow rate through observing the multi-range display meter. When the multi-range display table displays that the pressure of the supplied gas reaches a required value, the control valve assembly is immediately closed; at the moment, personnel judge the leakage condition through the pressure parameter change trend of the multi-process display meter; if the pressure is always maintained at a constant value, the tightness of the system or the equipment to be detected is satisfied. If the pressure slowly drops or quickly drops under the condition of leakage of the removing device, the system or equipment to be detected is indicated that the tightness is not satisfied, at the moment, the device is reused to continuously introduce gas and to utilize leakage detection liquid to generally check leakage points, and the device is reused for pressure maintaining verification after the leakage points are treated. After the integration and combination are completed in vitro, the leak detection device for the nuclear power station provided by the embodiment of the utility model introduces gas to perform periodic leak detection on a radioactive exhaust gas system of the nuclear power station or perform off-line leak detection under the condition that other process systems are not connected after personnel suspects that the exhaust gas system and a part person possibly have leakage risks or the personnel overhauls the exhaust gas system part. Can improve detection efficiency and can reduce the probability of maintaining reworking, can not increase the burden of pressing air, nitrogen gas system, be convenient for nuclear power station with leak hunting device with wait to detect the connection of system or part through setting up of joint.
Drawings
Various other advantages and benefits will become apparent to those of ordinary skill in the art upon reading the following detailed description of the preferred embodiments. The drawings are only for purposes of illustrating the preferred embodiments and are not to be construed as limiting the utility model. Also, like reference numerals are used to designate like parts throughout the figures. In the drawings:
fig. 1 is a schematic structural diagram of a leak detection device for a nuclear power station according to an embodiment of the present utility model.
The correspondence between the reference numerals and the component names in fig. 1 is:
1 transition joint, 2-relief valve, 3 manometer, 4 needle governing valve, 5 check valves, 6 multi-way display table, 7 joints, 8 pressure release isolation valves, 9 gas accommodation device, 10 gas supply pipe.
Detailed Description
In order to better understand the above technical solutions, the following detailed description of the technical solutions of the embodiments of the present utility model is made by using the accompanying drawings and the specific embodiments, and it should be understood that the specific features of the embodiments of the present utility model are detailed descriptions of the technical solutions of the embodiments of the present utility model, and not limit the technical solutions of the present utility model, and the technical features of the embodiments of the present utility model may be combined with each other without conflict.
As shown in fig. 1, the present utility model provides a leak detection device for a nuclear power station, including: a gas containing device 9; a gas supply pipe 10, one end of the gas supply pipe 10 being connected to an output end of the gas accommodating device 9; a joint 7, the joint 7 is arranged at the other end of the gas supply pipe 10, and the joint 7 is used for being connected to a system to be detected of the nuclear power station; a control valve assembly provided on the gas supply pipe 10 for controlling the opening degree, opening and closing of the gas supply pipe 10; the multi-pass display gauge 6 is provided on the gas supply pipe 10, and the multi-pass display gauge 6 is used for displaying the gas pressure and the temperature in the gas supply pipe 10.
The leak detection device for the nuclear power station provided by the embodiment of the utility model comprises the gas containing device 9, the gas supply pipe 10, the joint 7, the control valve assembly and the multi-pass display table 6, and in the use process, when a system or a component of the nuclear power station is required to be detected, such as when a radioactive waste gas system of the nuclear power station is subjected to a periodic tightness test, after necessary system and component switching and isolation are established or personnel judge that the waste gas system is likely to leak through power station parameters and phenomena, the leak detection device has the use condition when the sealing function of the waste gas system is required to be verified on line after necessary system and component switching and isolation are established or personnel overhaul waste gas system devices. When the connector 7 on the gas supply pipe 10 is connected with a system or equipment to be detected, the gas containing device 9 can supply gas, and the gas discharged by the gas containing device 9 passes through the control valve assembly first, so that a person can ensure that the system or equipment to be detected can reach the expected normal pressure and flow by observing the multi-range display meter 6. When the multi-pass display table 6 shows that the pressure of the supplied gas reaches the required value, the control valve assembly is immediately closed; at this time, personnel judge the leakage condition through the pressure parameter change trend of the multi-process display table 6; if the pressure is always maintained at a constant value, the tightness of the system or the equipment to be detected is satisfied. If the pressure slowly drops or quickly drops under the condition of leakage of the removing device, the system or equipment to be detected is indicated that the tightness is not satisfied, at the moment, the device is reused to continuously introduce gas and to utilize leakage detection liquid to generally check leakage points, and the device is reused for pressure maintaining verification after the leakage points are treated. After the integration and combination are completed in vitro, the leak detection device for the nuclear power station provided by the embodiment of the utility model introduces gas to perform periodic leak detection on a radioactive exhaust gas system of the nuclear power station or perform off-line leak detection under the condition that other process systems are not connected after personnel suspects that the exhaust gas system and a part person possibly have leakage risks or the personnel overhauls the exhaust gas system part. The detection efficiency can be improved, the maintenance reworking probability can be reduced, the burden of a pressure air and nitrogen system can not be increased, and the leakage detection device for the nuclear power station is convenient to be connected with a system or a component to be detected through the arrangement of the joint 7.
It can be understood that, by the leakage detection device for the nuclear power station provided by the embodiment of the utility model, after a proper amount of gas passes through the system or equipment to be detected, the sealing performance of the system or equipment to be detected can be intuitively reflected through the parameters such as pressure, temperature and the like displayed by the multi-range display table 6; the periodic tightness test requirement of the nuclear power station on the radioactive waste gas system can be met; the quick leak detection when personnel suspects leakage can be realized; the purpose of verifying the sealing performance of the device in advance under the condition of not connecting other process systems after personnel overhauls the exhaust gas system device can be achieved. The method solves the requirement that the staff of the nuclear power station needs to rapidly and conveniently verify the sealing performance of the radioactive waste gas system or the device.
It can be understood that by setting the multi-range display table 6, the air supply pressure and flow can be displayed during air supply, and parameters such as pressure, temperature and the like can be displayed during pressure maintenance and leakage detection.
In one possible embodiment, the control valve assembly includes: a pressure reducing valve 2, a needle-shaped regulating valve, and a check valve 5 arranged in this order along the direction from the gas accommodating device 9 to the joint 7 on the gas supply pipe 10; wherein the multi-way indicator 6 is located between the check valve 5 and the nipple 7.
In this technical solution, there is further provided a structural composition of a control valve assembly, which may include a pressure reducing valve 2, a needle-shaped regulating valve and a check valve 5 sequentially arranged on a gas supply pipe 10 in a direction from a gas accommodating device 9 to a joint 7, based on which the gas discharged from the gas accommodating device 9 can be reduced in pressure by the arrangement of the pressure reducing valve 2, preventing the gas pressure from damaging downstream equipment beyond a limit value; the pressure and the flow of the gas fed into downstream equipment can be adjusted through the arrangement of the needle-shaped regulating valve, so that the equipment is prevented from being damaged due to too high gas supply speed; the back flow of the gas can be effectively prevented by the arrangement of the check valve 5.
In one possible embodiment, the control valve assembly further comprises: the pressure release isolation valve 8, the pressure release isolation valve 8 is communicated between the multi-display meter 6 and the joint 7.
In this technical scheme, control valve subassembly can also include pressure release isolation valve 8, through pressure release isolation valve 8's setting, can be after the leak hunting is accomplished the pressure release or discharge the comdenstion water in the device when there is the demand, the equipment or the system of being convenient for accomplish the recovery after the leak hunting detects.
In a possible embodiment, the leak detection device for a nuclear power plant further includes: the pressure release pipe, pressure release pipe intercommunication is to gas supply pipe 10, and pressure release isolation valve 8 sets up on the pressure release pipe.
In this technical scheme, nuclear power station is with leaking hunting device can also include the pressure release pipe, through the setting of pressure release pipe, is convenient for after leaking hunting is accomplished the pressure release or discharge the comdenstion water in the device when there is the demand, especially the drainage of comdenstion water of being convenient for.
In a possible embodiment, the leak detection device for a nuclear power plant further includes: the pressure gauge 3, the pressure gauge 3 communicates with the gas supply pipe 10, and the pressure gauge 3 is located between the pressure reducing valve 2 and the needle regulating valve.
In this technical scheme, the leak detection device for a nuclear power station may further include a pressure gauge 3, the pressure gauge 3 being disposed between the pressure reducing valve 2 and the needle-shaped regulating valve, based on which the pressure gauge 3 may detect the gas pressure after the pressure reduction via the pressure reducing valve 2 to improve the safety of the gas supply.
In a possible embodiment, the leak detection device for a nuclear power plant further includes: the transition joint 1, one end of the transition joint 1 is connected to the gas accommodating device 9, and the other end is connected to the gas supply pipe 10.
In this technical scheme, leak hunting device for nuclear power station can also include transition joint 1, through the setting of transition joint 1, is convenient for gas accommodating device 9 and gas supply tube 10's connection, is convenient for the quick assembly of leak hunting device for nuclear power station.
In one possible embodiment, the transition joint 1 is a rotary joint.
In this technical solution, the transition joint 1 may be a rotary joint, on the basis of which a degree of freedom is provided between the gas containing device 9 and the gas supply pipe 10, so that the use of the leak detection device for a nuclear power station is safer.
In one possible embodiment, the gas supply tube 10 is made of explosion-proof steel tube.
In this solution, the gas supply pipe 10 may be made of an explosion-proof material, so that the composition of the leak detection device for a nuclear power station is provided on the one hand, and on the other hand, the operation of the leak detection device for a nuclear power station is made safer.
In one possible embodiment, the gas supply tube 10 is disposed within an explosion-proof steel tube.
In this embodiment, the gas supply pipe 10 may be provided in the explosion-proof steel pipe, and thus the safety of the operation of the leak detection device for the nuclear power plant can be ensured.
In one possible embodiment, the gas-containing device 9 is a portable gas cylinder.
In this technical scheme, further provided gas accommodation device 9 is portable gas bomb, based on this gas accommodation device 9 can be a plurality of, and can store different grade type gas among a plurality of portable gas bomb to be applicable to the different demands that leak hunting of nuclear power station.
Example 1
As shown in fig. 1, the leakage detection device for the nuclear power station of the utility model comprises a rotary joint 7, a pressure reducing valve 2, a pressure gauge 3, a needle type regulating valve 4, a check valve 5, a multi-range display gauge 6, a joint 7, a pressure relief isolation valve 8, a gas accommodating device 9 and an explosion-proof steel pipe.
As shown in fig. 1, the gas supply pipe 10 may be made of an explosion-proof steel pipe on which a rotary joint 7, a pressure reducing valve 2, a pressure gauge 3, a needle type regulating valve 4, a check valve 5, a multi-pass display gauge 6, and a joint 7 are sequentially provided in series.
As shown in fig. 1, a pressure relief isolation valve 8 is arranged in front of the joint 7; the system or equipment to be detected can be freely connected in front of and behind the joint 7.
As shown in fig. 1, the exhaust line of the gas containing device 9 is connected to the front of the swivel joint 7.
The working process of the leak detection device for the nuclear power station is as follows:
firstly, the staff of the nuclear power station needs to create conditions for using the device, namely, firstly, the radioactive waste gas system and equipment needing to be verified for tightness are subjected to necessary switching or isolation, so that an external air source can be introduced. Before the device is used, the device is checked to be connected reliably, the pressure reducing valve 2, the needle type regulating valve 4 and the pressure relief isolating valve 8 are all in a closed state, and the user after the joint 7 is connected reliably. At the moment, the pressure reducing valve 2 is slowly opened, and the pressure supplying and meeting requirements are ensured by observing the pressure parameter of the pressure gauge 3; then slowly adjusting the needle type regulating valve 4, and ensuring that the pressure and the flow of the gas supplied to a downstream user meet the requirements through the multi-process display table 6; when the multi-pass display table 6 shows that the feeding pressure meets the leak detection limit value, the needle type regulating valve 4 is closed immediately; then, personnel continuously observe the pressure of the multi-range display meter 6 to monitor the sealing condition of the user to be tested in real time, and if the pressure of the multi-range display meter 6 is always maintained at a required constant value, the sealing performance of the downstream user is good; if the pressure of the multi-pass display table 6 is slowly reduced or rapidly reduced, the sealing performance of the downstream user is not good; at the moment, after the gas is continuously introduced and the device is discharged, the external leakage point and the internal leakage point of a downstream user are subjected to major screening; if the locking leakage range is larger, the leakage detection areas can be properly reduced for one-by-one detection, or the necessary leakage detection liquid can be matched with the leakage detection to rapidly lock leakage points, and after the leakage points are treated, the pressure is maintained by re-inflation until the pressure of the multi-pass display meter 6 is stable. After the leak detection is finished, the pressure reducing valve 2 is closed, then the pressure releasing isolation valve 8 is slowly opened until the pressure of the multi-way display table 6 is zero, and the device can be recovered.
According to the leak detection device for the nuclear power station, after a proper amount of gas is passed through a system or equipment to be detected, the sealing performance of the system or equipment to be detected can be intuitively reflected through parameters such as pressure, temperature and the like; the periodic tightness test requirement of the nuclear power station on the radioactive waste gas system can be met; the quick leak detection when personnel suspects leakage can be realized; the purpose of verifying the sealing performance of the device in advance under the condition of not connecting other process systems after personnel overhauls the exhaust gas system device can be achieved. The method solves the requirement that the staff of the nuclear power station needs to rapidly and conveniently verify the sealing performance of the radioactive waste gas system or the device.
In the present utility model, the terms "first," "second," "third," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance; the term "plurality" means two or more, unless expressly defined otherwise. The terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; "coupled" may be directly coupled or indirectly coupled through intermediaries. The specific meaning of the above terms in the present utility model can be understood by those of ordinary skill in the art according to the specific circumstances.
In the description of the present utility model, it should be understood that the directions or positional relationships indicated by the terms "upper", "lower", "left", "right", "front", "rear", etc. are based on the directions or positional relationships shown in the drawings, are merely for convenience of describing the present utility model and simplifying the description, and do not indicate or imply that the devices or units referred to must have a specific direction, be constructed and operated in a specific direction, and thus should not be construed as limiting the present utility model.
In the description of the present specification, the terms "one embodiment," "some embodiments," "particular embodiments," and the like, mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present utility model. In this specification, schematic representations of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
The above is only a preferred embodiment of the present utility model, and is not intended to limit the present utility model, but various modifications and variations can be made to the present utility model by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present utility model should be included in the protection scope of the present utility model.
Claims (10)
1. A leak detection device for a nuclear power plant, comprising:
a gas containment device;
a gas supply pipe, one end of which is connected to an output end of the gas accommodating device;
the connector is arranged at the other end of the gas supply pipe and is used for being connected with a system to be detected of the nuclear power station;
a control valve assembly provided on the gas supply pipe for controlling an opening degree, opening and closing of the gas supply pipe;
the multi-range display meter is arranged on the gas supply pipe and is used for displaying the pressure and the temperature of the gas in the gas supply pipe.
2. The leak detection apparatus for a nuclear power plant as defined in claim 1, wherein the control valve assembly includes: a pressure reducing valve, a needle-shaped regulating valve, and a check valve arranged in this order on the gas supply pipe in a direction from the gas accommodating device to the joint;
wherein the multi-pass display gauge is located between the check valve and the nipple.
3. The leak detection apparatus for a nuclear power plant as defined in claim 2, wherein the control valve assembly further comprises:
the pressure relief isolation valve is communicated between the multi-range display meter and the connector.
4. A leak detection apparatus for a nuclear power plant as defined in claim 3, further comprising:
the pressure relief pipe, the pressure relief pipe intercommunication extremely the gas supply pipe, the pressure relief isolation valve sets up on the pressure relief pipe.
5. The leak detection apparatus for a nuclear power plant according to claim 2, further comprising:
the pressure gauge is communicated with the gas supply pipe and is positioned between the pressure reducing valve and the needle-shaped regulating valve.
6. The leak detection apparatus for a nuclear power plant according to claim 1, further comprising:
and one end of the transition joint is connected with the gas accommodating device, and the other end of the transition joint is connected with the gas supply pipe.
7. The leak detection apparatus for a nuclear power plant according to claim 6, wherein,
the transition joint is a rotary joint.
8. The leak detection apparatus for a nuclear power plant according to any one of claims 1 to 7,
the gas supply pipe is made of an explosion-proof steel pipe.
9. The leak detection apparatus for a nuclear power plant according to any one of claims 1 to 7,
the gas supply pipe is arranged in the explosion-proof steel pipe.
10. The leak detection apparatus for a nuclear power plant according to any one of claims 1 to 7,
the gas containing device is a portable gas storage bottle.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320173301.9U CN220189254U (en) | 2023-02-09 | 2023-02-09 | Leakage detection device for nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320173301.9U CN220189254U (en) | 2023-02-09 | 2023-02-09 | Leakage detection device for nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN220189254U true CN220189254U (en) | 2023-12-15 |
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ID=89115444
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202320173301.9U Active CN220189254U (en) | 2023-02-09 | 2023-02-09 | Leakage detection device for nuclear power station |
Country Status (1)
| Country | Link |
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| CN (1) | CN220189254U (en) |
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2023
- 2023-02-09 CN CN202320173301.9U patent/CN220189254U/en active Active
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