CN215065114U - Nuclear power station containment check valve sealing test device - Google Patents
Nuclear power station containment check valve sealing test device Download PDFInfo
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- CN215065114U CN215065114U CN202120010440.0U CN202120010440U CN215065114U CN 215065114 U CN215065114 U CN 215065114U CN 202120010440 U CN202120010440 U CN 202120010440U CN 215065114 U CN215065114 U CN 215065114U
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Abstract
The utility model discloses a nuclear power station containment check valve leakproofness test device, it includes: the air bag is arranged in the pipeline opposite to the valve clack, is placed in the pipeline when not pressurized, and seals and blocks the pipeline after being pressurized; the axial balancing device is arranged in the air bag and used for balancing the axial force caused by the gas pressure of the valve cavity; and the valve cover is hermetically arranged on the valve seat, the valve clack and the air bag of the valve cover and the check valve jointly enclose a closed valve cavity space, the air bag is connected with the air bag pressurizing and monitoring device through an air bag pressurizing pipeline penetrating through the valve cover, and the valve cavity space is connected with the valve pressurizing and monitoring device through a valve body pressurizing pipeline penetrating through the valve cover. Compared with the prior art, the utility model discloses nuclear power station containment check valve leakproofness test device can realize the on-line measuring of the different diameter check valve leakage rates of nonspecific test window, has overcome the high and inflexible problem of test window of prior art operation risk.
Description
Technical Field
The utility model belongs to the technical field of the nuclear power, more specifically says, the utility model relates to a nuclear power station containment check valve leakproofness test device.
Background
The penetrating piece is a fluid transmission pipeline penetrating through a containment factory building of a nuclear power plant and is a part of a third barrier of the nuclear power plant, and containment isolation valves are arranged on the inner side and the outer side of the pipeline and play an important role in preventing reflective substances in the island from flowing out of the island from the island under the condition that a coolant loss accident occurs to the reactor. Before a containment vessel compression test, a penetration piece sealing test needs to be completed to ensure that the isolation valve can prevent radioactive gas and waste liquid in the island from flowing out of the island from the island when a reactor accident occurs. The containment vessel isolation valve is also a boundary of a containment vessel compression test, before the containment vessel compression test is started, a sealing surface test needs to be completed firstly to prove the integrity of the containment vessel compression test as the boundary, and meanwhile, a penetrating piece isolation valve test also needs to be performed during the overhaul period of a service unit.
The sealing test of the penetrating piece isolation valve relates to 82 groups of 263 accumulated containment isolation valves of 19 systems of a nuclear island and a conventional island, whether the sealing performance of the containment isolation valve meets the operation criterion is verified, if not, the containment isolation valve needs to be verified again after being disassembled and maintained by a contractor, the sealing test of the penetrating piece isolation valve is always a key path of the containment pressure test due to the fact that the quality of valves is uneven and the quantity of the valves is large in the finished preparation activity of the containment pressure test.
The safety injection system serves as a secondary barrier for the nuclear power plant to inject boron-containing water into the core in the event of a loss of coolant accident in the nuclear power plant, preventing the melting of the fuel cladding and maintaining the geometry and integrity in the event of an accident. According to the periodical test supervision outline of nuclear safety related systems and equipment issued by the national nuclear safety administration, in order to ensure the sealing performance of a part of check valves of a safety injection system of a primary circuit of a safety injection pipeline, the sealing performance of the check valves needs to be measured during a cold-state function test (hereinafter referred to as cold test) and a hot-state function test (hereinafter referred to as hot test) of a nuclear power plant, namely, the sealing performance of the check valves is tested by using high pressure in the system during the cold test and the hot test as backpressure.
However, the existing check valve tightness detection has the following defects:
1. fixing a test window: because of the directional characteristic of the check valve, the test can only be performed when back pressure exists in the system during cold test and hot test, and the test window is not flexible.
2. Influence on the critical path: if the sealing performance is not qualified, the pressure is relieved, the materials are disassembled, ground and then verified again. The hot test and the cold test are both nuclear power construction first-level milestones, the completion time of the hot test and the cold test is clearly checked, and the repeated maintenance and verification of the check valve influences the completion time of the hot test and the cold test, so that the hot test and the cold test are limited to be completed according to the period;
3. the operation risk is high: during the hot test and the cold test of the nuclear power station, the pressure in a loop can reach 228bar.g at most, and the method belongs to high-risk operation.
In view of the above, it is necessary to provide a simple and safe sealing test device for a containment check valve of a nuclear power plant.
SUMMERY OF THE UTILITY MODEL
The invention of the utility model aims to: the device overcomes the defects of the prior art and provides a simple and safe nuclear power station containment vessel check valve tightness test device.
In order to realize the above-mentioned invention purpose, the utility model provides a nuclear power station containment check valve leakproofness test device, it includes:
the air bag is arranged in the pipeline opposite to the valve clack, is placed in the pipeline when not pressurized, and seals and blocks the pipeline after being pressurized;
the axial balancing device is arranged in the air bag and used for balancing the axial force caused by the gas pressure of the valve cavity; and
the valve cover is hermetically arranged on the valve seat, the valve clack and the air bag of the valve cover and the check valve jointly enclose a closed valve cavity space, the air bag is connected with the air bag pressurizing and monitoring device through an air bag pressurizing pipeline penetrating through the valve cover, and the valve cavity space is connected with the valve pressurizing and monitoring device through a valve body pressurizing pipeline penetrating through the valve cover.
As the utility model discloses nuclear power station containment check valve leakproofness test device's an improvement, axial balancing unit is stainless steel cross support.
As an improvement of the sealing test device of the containment check valve of the nuclear power station, the size of the stainless steel cross-shaped bracket is 8-12mm larger than the diameter of the pipeline.
As the utility model discloses nuclear power station containment check valve leakproofness test device's an improvement, the internally mounted of gasbag has round stainless steel protecting wire net.
As the utility model discloses nuclear power station containment check valve leakproofness test device's an improvement, the gasbag is made by vulcanized rubber.
As the utility model discloses nuclear power station containment check valve leakproofness test device's an improvement, the valve gap passes through bolt demountable sealing and installs on the disk seat.
As an improvement of the sealing test device of the containment check valve of the nuclear power station, a sleeve is arranged between the valve cover and the bolt, and the length of the sleeve is 3-5 cm.
As an improvement of the sealing test device of the containment check valve of the nuclear power station, the air bag is connected with the SAT air source.
As the utility model discloses nuclear power station containment check valve leakproofness test device's an improvement, sealed when examining, the pressure of gasbag is not less than 1.5 bar.g.
Compared with the prior art, the utility model discloses nuclear power station containment check valve leakproofness test device has following advantage:
1) the valve cover, the air bag pressurizing and monitoring device, the valve pressurizing and monitoring device and the axial balancing device are adopted, the non-specific test window check valve plugging and the check valve sealing performance online detection are realized, and the problems of high risk and inflexible test window operation in the traditional scheme are solved; when the air bag is not pressurized, the air bag is placed in a valve pipeline to be measured, and then pressurization is carried out, so that pipeline plugging with different valve diameters can be realized.
2) The check valve tightness detection does not depend on cold test and hot test windows any more, so that the problem that the key path of a project is influenced due to unqualified valve tightness is avoided;
3) the axial balancing device is arranged in the air bag to prevent the main loop pipe from being scratched and foreign matters from being generated. By utilizing the axial balancing device, the risk that the high-pressure gas in the valve cavity presses the air bag into the pipeline to cause foreign matters during the check valve detection is prevented.
Drawings
The following description is given in detail in connection with the accompanying drawings and the specific embodiments, to the sealing test device for the containment check valve of the nuclear power station of the present invention, wherein:
FIG. 1 is the utility model discloses nuclear power station containment check valve leakproofness test device's schematic diagram.
Fig. 2 is the utility model discloses axial balancing unit's in nuclear power station containment check valve leakproofness test device structural schematic.
Wherein the content of the first and second substances,
10-a valve seat; 20-a valve flap; 30-valve cover; 300-bolt; 302-a sleeve; 40-air bag; 400-axial balancing means; 402-stainless steel protective net; 404-a cross-brace; 50-valve cavity; 60-valve body pressurization line; 70-balloon inflation line.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention clearer, the present invention will be further described in detail with reference to the accompanying drawings and specific embodiments. It should be understood that the detailed description and specific examples, while indicating the present invention, are given by way of illustration and not limitation.
Referring to fig. 1, the utility model provides a nuclear power station containment check valve leakproofness test device, it includes:
the air bag 40 is arranged in the pipeline opposite to the valve clack 20, the air bag 40 is placed in the pipeline when the air bag is not pressurized, and the pipeline is sealed and blocked after the air bag is pressurized;
an axial balancing device 400, which is arranged in the air bag 40 and is used for balancing the axial force caused by the gas pressure of the valve cavity; and
the valve cover 30 is hermetically arranged on the valve seat 10, and forms a closed valve cavity space 50 together with the valve seat 10, the valve clack 20 and the air bag 40 of the check valve, the air bag 40 is connected with an air bag pressurizing and monitoring device through an air bag pressurizing pipeline 70 penetrating through the valve cover 30, and the valve cavity space 50 is connected with the valve pressurizing and monitoring device through a valve body pressurizing pipeline 60 penetrating through the valve cover 30.
Referring also to fig. 2, the bladder 40 is provided with an axial balancing device 400 for preventing the bladder 40 from entering the conduit, so as to balance the axial force caused by the gas pressure in the valve chamber. The axial balancing device 400 is a stainless steel spider 404 comprising two mutually perpendicular struts, the size of the spider 404 of the axial balancing device 400 being 8-12mm larger than the pipe diameter, preventing axial pressure from the high pressure gas in the valve chamber during the test from pressing the bladder 40 into the system pipe.
The axial balancing device 400 is located inside the bladder 40 and does not directly contact the valve body, preventing the axial balancing device 400 from scratching the pipe during testing. A circle of stainless steel protecting net 402 is arranged on the inner side of the air bag 40, the diameter of the stainless steel protecting net is smaller than the diameter of the pipeline by 60mm, the air bag 40 can be conveniently and rapidly installed under the non-pressurized condition, and the air bag sealing device is also suitable for sealing check valves on different pipe diameters and verifying the sealing performance test. During the test, the tightness of the tested check valve is measured by a pressure gauge on the valve cover 30. According to the utility model discloses an embodiment adopts quick-operation joint to be connected between gasbag 40 and the valve gap 30, has the convenience of being connected, and the leakproofness is good, possesses real-time supervision self leakproofness, balanced axial ability and the light characteristics of installation.
The maximum pressure of the valve body during the test is 4.2bar.g, so the thickness of the special valve cover 30 for the test is smaller than that of the original valve cover. In order to match the test valve cover 30 with the original valve body and the bolt 300, the illustrated embodiment is always provided with 6 sleeves 302 with a height of 3-5cm and a wall thickness of 1cm, so as to avoid the mismatching of the thread length of the bolt due to the thickness of the test valve cover.
The use method of the sealing test device for the containment check valve of the nuclear power station of the present invention is described in detail below with reference to fig. 1 and 2, and includes the following steps:
1) the valve cover 30 is opened, the air bag 40 is placed in the pipeline corresponding to the valve clack 20 and is connected with an SAT air source, and the pressure is increased to 1.5bar.g from a valve V2 (if the pressure of the air bag 40 is less than 1.5bar.g, the pressure is supplemented to the air bag);
2) after stabilizing for 5min, if the pressure drop in the air bag 40 is less than 0.05bar, installing the sleeve 302, the bolt 300 and the valve cover 30;
3) pressurizing the valve cavity space 50 to the design pressure of 4.2bar.g from the pressurizing device V1, and recording the time t 1;
4) after the time requirement is met, recording the time t2 and the reading P of the current pressure gauge1When t1-t2 is more than 15min, according to the formula
Where V is the valve body volume, Δ P is 4.2-P1, t is t1-t2, and P is 1.013. And when the Q is smaller than 400-pipe diameter, determining that the valve tightness test is qualified, otherwise, removing the valve core for grinding, and verifying again after re-grinding.
It is right above combining the utility model discloses a detailed description can be seen from, for prior art, the utility model discloses nuclear power station containment check valve leakproofness test device has following advantage:
1) the valve cover 30, the air bag 40, the air bag pressurizing and monitoring device, the valve pressurizing and monitoring device and the axial balancing device 400 are adopted to realize the plugging of the non-specific test window check valve and the online detection of the tightness of the check valve, and the problems of high risk and inflexible test window of the traditional scheme operation are solved; when the air bag 40 is not pressurized, the air bag is placed into a pipeline of the valve to be measured, and then the air bag is pressurized, so that the pipeline plugging with different valve diameters can be realized.
2) The check valve tightness detection does not depend on cold test and hot test windows any more, so that the problem that the key path of a project is influenced due to unqualified valve tightness is avoided;
3) the axial balancing device 400 is disposed in the air bag 40 to prevent scratching of the main circuit pipe and generation of foreign materials. The axial balancing device 400 prevents the risk of the high pressure gas in the valve chamber pressing the bladder 40 into the pipe and causing foreign objects during check valve testing.
4) The inboard stainless steel protecting wire 402 that is provided with of gasbag 40, its diameter is less than valve pipeline diameter 60mm, and the gasbag of being convenient for carries out quick installation under the non-charging condition, also is applicable to the check valve shutoff and the experimental verification of leakproofness on the different pipe diameters simultaneously.
According to the above principle, the present invention can also make appropriate changes and modifications to the above embodiments. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and changes to the present invention should fall within the protection scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (9)
1. The utility model provides a nuclear power station containment check valve leakproofness test device which characterized in that includes:
the air bag is arranged in the pipeline opposite to the valve clack, is placed in the pipeline when not pressurized, and seals and blocks the pipeline after being pressurized;
the axial balancing device is arranged in the air bag and used for balancing the axial force caused by the gas pressure of the valve cavity; and
the valve cover is hermetically arranged on the valve seat, the valve clack and the air bag of the valve cover and the check valve jointly enclose a closed valve cavity space, the air bag is connected with the air bag pressurizing and monitoring device through an air bag pressurizing pipeline penetrating through the valve cover, and the valve cavity space is connected with the valve pressurizing and monitoring device through a valve body pressurizing pipeline penetrating through the valve cover.
2. The nuclear power plant containment check valve tightness test device according to claim 1, wherein the axial balancing device is a cross bracket.
3. The nuclear power station containment check valve tightness test device according to claim 2, wherein the size of the cross bracket is 8-12mm larger than the diameter of the pipeline.
4. The nuclear power station containment check valve tightness test device according to claim 1, wherein a circle of stainless steel protecting net is installed inside the air bag.
5. The nuclear power station containment check valve tightness test device according to claim 1, wherein the air bag is made of vulcanized rubber.
6. The device for testing the sealing performance of the containment check valve of the nuclear power plant as claimed in claim 1, wherein the valve cover is detachably and hermetically mounted on the valve seat through bolts.
7. The device for testing the sealing performance of the containment check valve of the nuclear power station as claimed in claim 6, wherein a sleeve is arranged between the valve cover and the bolt, and the length of the sleeve is 3-5 cm.
8. The nuclear power plant containment check valve tightness test device according to any one of claims 1 to 7, wherein the air bag is connected with an SAT air source.
9. The device for testing the sealing performance of the containment check valve in the nuclear power plant according to any one of claims 1 to 7, wherein the pressure of the air bag is not less than 1.5bar.g during sealing detection.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202120010440.0U CN215065114U (en) | 2021-01-05 | 2021-01-05 | Nuclear power station containment check valve sealing test device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202120010440.0U CN215065114U (en) | 2021-01-05 | 2021-01-05 | Nuclear power station containment check valve sealing test device |
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| Publication Number | Publication Date |
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| CN215065114U true CN215065114U (en) | 2021-12-07 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN202120010440.0U Active CN215065114U (en) | 2021-01-05 | 2021-01-05 | Nuclear power station containment check valve sealing test device |
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| CN (1) | CN215065114U (en) |
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2021
- 2021-01-05 CN CN202120010440.0U patent/CN215065114U/en active Active
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