CN211427856U - Nuclear power station containment mechanical penetration piece isolation valve leakage rate test device - Google Patents
Nuclear power station containment mechanical penetration piece isolation valve leakage rate test device Download PDFInfo
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- CN211427856U CN211427856U CN201921448653.0U CN201921448653U CN211427856U CN 211427856 U CN211427856 U CN 211427856U CN 201921448653 U CN201921448653 U CN 201921448653U CN 211427856 U CN211427856 U CN 211427856U
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- pipeline
- inlet
- outlet
- test
- electronic flowmeter
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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 utility model discloses a nuclear power station containment mechanical penetration spare isolating valve leakage rate test device belongs to nuclear power equipment technical field, including import test pipeline, export test pipeline, electronic flowmeter and control system, import test pipeline exit end connects gradually electronic flowmeter, export test pipeline entrance point, and control system connects in electronic flowmeter for control measurement process and carry out real-time acquisition and processing to electronic flowmeter's measured data. The inlet test pipeline and the port test pipeline respectively comprise a joint, a pipeline and a stop valve arranged on the pipeline; the control system comprises an embedded computer system, a touch control type human-computer interaction interface and an image device. The measuring device does not depend on experience and capability of an operator during measurement operation, can prevent misoperation of the operator, and simultaneously realizes automatic real-time acquisition and processing of data.
Description
Technical Field
The utility model belongs to the technical field of the nuclear power equipment technique and specifically relates to a nuclear power station containment mechanical penetration piece isolating valve leakage rate test device.
Background
The leakage rate inspection of the mechanical penetrating member isolation valve of the containment vessel of the nuclear power station is an effective way for judging whether the integral sealing performance of the containment vessel meets related requirements. At present, two methods, namely a pressure drop method and a direct flow measurement method, are mainly used for the sealing performance test of the penetration piece of the nuclear power station in China, and a series of special flow measurement devices are developed. These test devices suffer from the following disadvantages:
1. the use and flow control of the flow measuring device seriously depend on the experience and the capability of operators, and the validity and the reliability of measured data are not guaranteed;
2. in the test process, the information identification of the tested object only depends on manual identification of an operator, no traceable control means exists, and huge potential safety hazards exist;
3. the measured data has no on-site processing capability and needs to be subjected to background secondary processing, so that the detection time limit is prolonged, and the working efficiency is low.
Disclosure of Invention
The utility model aims at providing a nuclear power station containment machinery through-piece isolating valve leakage rate test device reaches the intelligent measuring purpose that does not use operating personnel's experience and ability to rely on, can take precautions against operating personnel maloperation when measurement test to realize the automatic real-time acquisition and the processing function of data simultaneously.
The utility model discloses a concrete technical scheme as follows:
a leakage rate test device for a mechanical penetration piece isolation valve of a containment vessel of a nuclear power station comprises an inlet test pipeline, an outlet test pipeline, an electronic flowmeter and a control system;
the outlet end of the inlet test pipeline is sequentially connected with the electronic flowmeter and the inlet end of the outlet test pipeline; the control system is connected with the electronic flowmeter and used for controlling the measuring process and acquiring and processing the measuring data of the electronic flowmeter in real time.
Further, the inlet test pipeline comprises an inlet joint, an inlet pipeline and an inlet stop valve arranged on the inlet pipeline, wherein the inlet joint and the inlet pipeline are sequentially connected; the inlet joint is used for accessing measured fluid during a measurement test.
Further, the outlet test pipeline comprises an outlet pipeline, an outlet joint and an outlet stop valve arranged on the outlet pipeline, wherein the outlet pipeline and the outlet joint are sequentially connected; the outlet connector is used for connecting the measured fluid into the tested through-piece isolation valve during the measurement test.
As a preferred embodiment of the present invention, the control system includes an embedded computer system and a touch-control human-computer interaction interface, and the embedded computer system can realize the acquisition, processing and flow control of measurement data; the operation and the use of the embedded computer system can be realized through the touch control type human-computer interaction interface.
Furthermore, the control system also comprises an image device which is connected with the embedded computer system and used for collecting the image information of the detected penetrating piece isolation valve and transmitting the collected image information to the embedded computer system.
Further, the imaging device is a camera.
Furthermore, the imaging device is a bar code scanning device.
Furthermore, the leakage rate measurement test device for the mechanical penetration isolation valve of the containment of the nuclear power station also comprises a box body, wherein the part of the inlet test pipeline except the inlet joint, the part of the outlet test pipeline except the outlet joint, the electronic flowmeter and the embedded computer system are integrated in the box body, and the inlet joint, the outlet joint, the opening and closing switches of the inlet stop valve and the outlet stop valve, the touch human-computer interaction interface and the imaging device are all arranged outside the box body; the box body is arranged to facilitate free movement of the device in the using process.
Compared with the prior art, the beneficial effect of this practicality embodies:
1. the measuring device comprises an inlet test pipeline, an outlet test pipeline, an electronic flowmeter and a control system, wherein the outlet end of the inlet test pipeline is sequentially connected with the inlet ends of the electronic flowmeter and the outlet test pipeline, the control system is connected with the electronic flowmeter and used for controlling the measuring process and collecting and processing the measured data of the electronic flowmeter in real time, intelligent data collection and processing can be realized, the data collection speed and accuracy are improved, and the condition that manual data entry is prone to errors is avoided; and the data can be processed on site in real time, so that the measurement result can be obtained quickly, and the working efficiency of the measurement test is improved.
2. The utility model discloses a measuring device, whole measurement test is guided by control system, has reduced the experience to operating personnel and the degree of dependence of ability, has avoided taking place the phenomenon of maloperation because of operating personnel is unfamiliar with to the measurement test procedure, more does benefit to and uses widely.
3. The measuring device collects the image information of the detected penetrating piece isolation valve through the image device and transmits the image information to the embedded computer system, and then the identity information of the detected penetrating piece isolation valve is checked and confirmed, so that the detected object is ensured to be consistent with the requirements of a preset control program, and the misoperation risk is further avoided.
Drawings
In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present application, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Fig. 1 is a system schematic diagram of the measurement testing apparatus of the present invention.
Fig. 2 is a flowchart of a control procedure of the control system of the present invention.
Fig. 3 is the schematic view of the external plane structure of the box body of the present invention.
Fig. 4 is the schematic view of the internal plane structure of the box body of the present invention.
In the figure:
1. an inlet test pipeline 11, an inlet joint 12, an inlet pipeline 13 and an inlet stop valve;
2. an outlet test pipeline 21, an outlet joint 22, an outlet pipeline 23 and an outlet stop valve;
3. an electronic flow meter;
4. a control system 41, an embedded computer system 42, a touch control type human-computer interaction interface 43 and an image device;
and 5, a box body.
Detailed Description
The utility model discloses the technical problem that will solve is: the existing flow measuring device used for the sealing performance test of the nuclear power station penetration piece generally depends on experience and capability of operators seriously when in use, the misoperation risk is large, the measured data accuracy is unreliable, the data cannot be processed in real time, and the like. The utility model discloses the technical thinking that just this technical problem provided is: the device is characterized in that a digital informationized penetration piece isolation valve leakage rate measurement test device is adopted, specifically, a flow measurement and data processing integrated device based on computer acquisition and processing is adopted, an embedded computer system control program is adopted, a nuclear power station related test program is used as guidance to automatically guide an operator to complete related measurement work, and the device is suitable for a nuclear power station penetration piece leakage rate measurement test which performs measurement tests by a flow method.
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 only some embodiments of the present invention, not all embodiments. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative work belong to the protection scope of the present invention.
As shown in fig. 1-4, a nuclear power station containment mechanical penetration isolation valve leakage rate test device comprises an inlet test pipeline 1, an outlet test pipeline 2, an electronic flowmeter 3 and a control system 4; the outlet end of the inlet test pipeline 1 is sequentially connected with the inlet ends of the electronic flowmeter 3 and the outlet test pipeline 2; the control system 4 is connected to the electronic flowmeter 3 and used for controlling the measuring process and acquiring and processing the measuring data of the electronic flowmeter 3 in real time.
The inlet test pipeline 1 comprises an inlet joint 11, an inlet pipeline 12 and an inlet stop valve 13 arranged on the inlet pipeline 12 which are connected in sequence; the inlet joint 11 is used for accessing measured fluid during a measurement test; the outlet test pipeline 2 comprises an outlet pipeline 22, an outlet joint 21 and an outlet stop valve 23 arranged on the outlet pipeline 22 which are connected in sequence; the outlet connector 21 is used for connecting the measured fluid into the measured penetrating piece isolation valve during the measurement test.
The control system 4 comprises an embedded computer system 41 and a touch control type human-computer interaction interface 42, preferably, test software can be assembled in the embedded computer system 41, the test software is compiled according to relevant test procedure requirements of the nuclear power station, and acquisition, processing and flow control of measurement data can be realized; the touch control type man-machine interaction interface 42 can be used for operating the test software, and a test process is started through the interaction interface.
As a further preferred embodiment, the control system 4 further includes an image device 43 connected to the embedded computer system 41, and configured to collect image information of the tested penetration piece isolation valve and transmit the collected image information to the embedded computer system 41, so that the embedded computer system 41 can check and confirm the identity information of the tested penetration piece isolation valve according to the image information, and avoid misoperation.
In this embodiment, the image device 43 is a camera; in other embodiments, the imaging device 43 may also be a barcode scanning device.
As shown in fig. 3-4, the measuring apparatus further includes a box 5, a portion of the inlet test pipeline 1 except the inlet joint 11, a portion of the outlet test pipeline 2 except the outlet joint 21, an electronic flow meter 3 and an embedded computer system 41 are all integrated inside the box 5, and the opening and closing switches of the inlet joint 11, the outlet joint 21, the inlet stop valve 13 and the outlet stop valve 23, the touch human-computer interface 42 and the imaging device 43 are all disposed outside the box 5; the provision of the housing 5 facilitates free movement of the device during use.
When the device is used, firstly, a power supply of the device is turned on, the control system 4 is started, the device enters a measurement test guiding state through the operation of the touch control type man-machine interaction interface 42, an operator inputs parameter information of the isolation valve of the tested penetration piece, a camera is used for shooting related image information of the isolation valve of the tested penetration piece and transmitting the related image information to the control system 4 for identity information check, when all data are confirmed to meet requirements, the inlet stop valve 13 and the outlet stop valve 23 are opened, the fluid to be measured is connected into the measurement device from the inlet joint 11 of the inlet test pipeline 1, a fluid medium flows through the electronic flowmeter 3 through the inlet stop valve 13 and the inlet pipeline 12, then flows through the outlet pipeline 22 and the outlet stop valve 23 and is connected into the tested penetration piece isolation valve through the outlet joint 21; in the process, the electronic flowmeter 3 measures the flow of the fluid flowing through the inside of the electronic flowmeter and then transmits the relevant information to the control system 4 in an electric signal mode, and the control system 4 analyzes and processes the acquired data to obtain measurement result data, so that the measurement of the leakage flow is completed.
It should be noted that the power supply system of the present apparatus is used for supplying power to the inlet test pipeline, the outlet test pipeline, the electronic flow meter and the control system, and the connection relationship between the power supply system and the present apparatus is also a conventional connection relationship, which is well known to those skilled in the art, and therefore, the detailed description in this embodiment is not provided.
In the above description of the present invention, it should be understood that the terms "upper", "lower", "inner", "outer", etc. indicate the orientation or positional relationship based on the orientation or positional relationship shown in the drawings, or the orientation or positional relationship that the product of the present invention is usually placed when in use, or the orientation or positional relationship that a person skilled in the art conventionally understands, only for the convenience of describing the present invention and simplifying the description, but not for indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus should not be construed as limiting the present invention.
The foregoing is considered as illustrative only of certain exemplary embodiments of this invention, and is therefore to be understood that the drawings and descriptions will be regarded as illustrative in nature and not as restrictive. It should also be noted that, for those skilled in the art, a plurality of improvements and additions can be made in various ways without departing from the principles of the present invention, and these improvements and additions should also be considered as the protection scope of the present invention.
Claims (7)
1. The utility model provides a nuclear power station containment machinery penetrating piece isolating valve leakage rate test device which characterized in that: the device comprises an inlet test pipeline, an outlet test pipeline, an electronic flowmeter and a control system; the outlet end of the inlet test pipeline is sequentially connected with the electronic flowmeter and the inlet end of the outlet test pipeline; the control system is connected with the electronic flowmeter and used for controlling the measuring process and acquiring and processing the measuring data of the electronic flowmeter in real time.
2. The test device of claim 1, wherein: the inlet test pipeline comprises an inlet joint, an inlet pipeline and an inlet stop valve, wherein the inlet joint, the inlet pipeline and the inlet stop valve are sequentially connected.
3. The test device of claim 1, wherein: the outlet test pipeline comprises an outlet pipeline, an outlet connector and an outlet stop valve arranged on the outlet pipeline, wherein the outlet pipeline and the outlet connector are sequentially connected.
4. The test device of claim 1, wherein: the control system also includes an imaging device for collecting and transmitting image information of the detected through-member isolation valve.
5. The testing device of claim 4, wherein: the imaging device is a camera.
6. The testing device of claim 4, wherein: the imaging device is a bar code scanning device.
7. The testing device of claim 4, wherein: the intelligent testing device is characterized by further comprising a box body, wherein the part of the inlet testing pipeline except the inlet connector, the part of the outlet testing pipeline except the outlet connector and the electronic flowmeter are integrated inside the box body, and the opening and closing switches and the imaging device of the inlet connector, the outlet connector, the inlet stop valve and the outlet stop valve are all arranged outside the box body.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201921448653.0U CN211427856U (en) | 2019-09-02 | 2019-09-02 | Nuclear power station containment mechanical penetration piece isolation valve leakage rate test device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201921448653.0U CN211427856U (en) | 2019-09-02 | 2019-09-02 | Nuclear power station containment mechanical penetration piece isolation valve leakage rate test device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN211427856U true CN211427856U (en) | 2020-09-04 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201921448653.0U Expired - Fee Related CN211427856U (en) | 2019-09-02 | 2019-09-02 | Nuclear power station containment mechanical penetration piece isolation valve leakage rate test device |
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| CN (1) | CN211427856U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114235307A (en) * | 2021-12-06 | 2022-03-25 | 中广核工程有限公司 | System and method for testing tightness of isolation valve of mechanical penetration piece of containment vessel of nuclear power station |
-
2019
- 2019-09-02 CN CN201921448653.0U patent/CN211427856U/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114235307A (en) * | 2021-12-06 | 2022-03-25 | 中广核工程有限公司 | System and method for testing tightness of isolation valve of mechanical penetration piece of containment vessel of nuclear power station |
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| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20200904 Termination date: 20210902 |