Verification test device and method for nuclear power containment sealing test

Abstract

The invention provides a verification test device and method for a nuclear power containment sealing test, the verification test device comprises an instrument, a computer, a mechanical pipeline, an electrical circuit, a plurality of signal conversion boxes and a relay router, one end of the instrument is connected with a containment penetration piece interface through the mechanical pipeline; the computer is an operation end, is provided with operation software, is connected with the instrument through the electrical circuit, and is used for transmitting a control signal; the signal conversion box and the relay router are connected between the instrument and the computer at intervals through the electrical circuit, and the other end of the instrument is connected to a negative pressure shed. The accuracy, the test efficiency and the safety of the verification test are greatly improved. In the test execution period, personnel do not need to carry out on-site guarding, measuring and recording, the personnel radiation risk caused by on-site guarding, measuring and recording is avoided, and labor consumption is reduced.

Description

Technical Field

[0001] The invention relates to the field of nuclear power safety testing, and in particular to a verification test device and method for nuclear power containment sealing testing. Background Art

[0002] In the existing technology, the containment of a nuclear power plant is the last barrier of a nuclear reactor. During commissioning and overhaul, the sealing performance of the containment needs to be tested, and the online operation status of the system under the design basis accident state needs to be simulated to evaluate whether the containment can maintain its sealing under the accident state.

[0003] However, verification testing is a key link in ensuring the accuracy and effectiveness of simulation calculations. The overall sealing test of the containment takes up 80-100 hours of main line time during the overhaul and is the largest single test in the overhaul.

[0004] The verification test is a test to verify the effectiveness of the entire test system and test process after the containment sealing test calculation is completed. The technical principle is to artificially superimpose a known and controllable leakage volume on the containment pressure boundary, and compare the calculated superimposed containment composite leakage rate with the expected leakage rate range limit to verify the effectiveness of the overall leakage rate test calculation results.

[0005] The current verification test device has a complex structure and cumbersome operation, which makes it inconvenient for test personnel to conduct sealing performance testing, and the accuracy needs to be further improved.

[0006] In view of this, the inventors of the present application have designed a verification test device and method for nuclear power containment sealing test, in order to overcome the above-mentioned technical problems. Summary of the invention

[0007] The technical problem to be solved by the present invention is to overcome the defects of the verification test device in the prior art, such as complex structure, cumbersome operation, and the need to further improve the accuracy, and to provide a verification test device and method for nuclear power containment sealing test.

[0008] The present invention solves the above technical problems through the following technical solutions:

[0009] The present invention provides a verification test device for nuclear power containment sealing test, which is characterized in that the verification test device includes an instrument, a computer, a mechanical pipeline, an electrical circuit, a plurality of signal conversion boxes and a relay router, one end of the instrument is connected to the containment penetration interface through the mechanical pipeline; the computer is an operating end, which is installed with operating software, and is connected to the instrument through the electrical circuit for transmitting control signals;

[0010] The signal conversion box and the relay router are connected between the meter and the computer at intervals through the electrical line, and the other end of the meter is connected to the negative pressure shed.

[0011] According to one embodiment of the present invention, the instrument is a mass flow controller.

[0012] According to an embodiment of the present invention, a first manual ball valve is provided between the instrument and the negative pressure shelf for controlling the pipeline outlet.

[0013] According to one embodiment of the present invention, a second manual ball valve is provided between the instrument and the containment penetration interface for controlling the pipeline inlet.

[0014] According to one embodiment of the present invention, the signal conversion box includes a primary signal conversion box and a secondary signal conversion box, the primary signal conversion box is close to the mass flow controller, and the secondary signal conversion box is close to the computer.

[0015] According to one embodiment of the present invention, the data signal interface of the mass flow controller is an R232 serial port, the primary signal conversion box converts the R232 signal into an Ethernet signal, and the secondary signal conversion box converts the Ethernet signal into an R232 signal, which is connected to the computer via a USB interface.

[0016] According to an embodiment of the present invention, the mass flow controller and the primary signal conversion box are powered by an integrated system, integrating the power supply with the primary signal conversion box.

[0017] According to an embodiment of the present invention, a bypass spare channel is provided on one side of the instrument, and a third manual ball valve is provided in the spare channel for controlling the spare channel.

[0018] According to one embodiment of the present invention, the mechanical pipeline is connected to the containment penetration interface using an NPT threaded joint.

[0019] The present invention also provides a verification test method for a nuclear power containment sealing test, which is characterized in that the verification test method adopts the verification test device for a nuclear power containment sealing test as described above, and the verification test method comprises:

[0020] S1, hardware self-check;

[0021] S2, the instrument performs feedback. If the feedback value is normal, the process proceeds to step S3; if the feedback value is abnormal, the system prompts that the hardware is abnormal, and returns to step S1;

[0022] S3, setting parameters of the instrument;

[0023] S4, entering the adjustment mode, the instrument performs self-check, if the result is normal, then proceed to step S5; if the result is abnormal, then prompt hardware abnormality, and return to step S1;

[0024] S5, enter the test mode, set the cycle and threshold, and then collect and display data;

[0025] S6. The verification test method ends.

[0026] The positive and progressive effects of the present invention are:

[0027] The verification test device and method for nuclear power containment sealing test of the present invention have the following advantages:

[0028] 1. The accuracy, efficiency and safety of verification tests have been greatly improved;

[0029] Second, the verification test device adopts the form of remotely operating the flow control unit in the data acquisition center to realize remote control of the verification test superimposed flow, system start and stop, test mode selection and other functions, and the test state can be achieved without the need for personnel to operate the test equipment on site;

[0030] 3. Flow measurement adopts automatic reading mode of electronic flow meter. The accuracy of flow meter can reach 1%, and the reading is intuitive. The instrument has built-in pressure sensor and temperature sensor, which can automatically convert working condition and standard condition according to environmental status, without measuring local temperature and pressure.

[0031] 4. The flow control method during the test is automatic feedback control, with high flow regulation accuracy and high flow stability;

[0032] 5. During the test, there is no need for personnel to perform on-site supervision, measurement, and recording, which avoids the risk of radiation to personnel and reduces manpower consumption. BRIEF DESCRIPTION OF THE DRAWINGS

[0033] The above and other features, properties and advantages of the present invention will become more apparent through the following description in conjunction with the accompanying drawings and embodiments, in which the same reference numerals always represent the same features, wherein:

[0034] Figure 1 The present invention is a schematic structural diagram of a verification test device for testing the sealing properties of a nuclear power containment vessel.

[0035] Figure 2 The software operation diagram of the verification test method for nuclear power containment sealing test of the present invention is shown.

[0036] [Reference Signs]

[0037] Computer 10

[0038] Mechanical pipeline 20

[0039] Electrical wiring 30

[0040] Relay router 40

[0041] Mass Flow Controller 50

[0042] Containment penetration interface 60

[0043] Negative pressure shed 70

[0044] The first manual ball valve 100

[0045] Second manual ball valve 200

[0046] First level signal conversion box 300

[0047] Secondary signal conversion box 400

[0048] Spare channel 500

[0049] The third manual ball valve 600 DETAILED DESCRIPTION

[0050] In order to make the above-mentioned objects, features and advantages of the present invention more obvious and easy to understand, the specific embodiments of the present invention are described in detail below with reference to the accompanying drawings.

[0051] Embodiments of the present invention will now be described in detail with reference to the accompanying drawings. Reference will now be made in detail to preferred embodiments of the present invention, examples of which are shown in the accompanying drawings. Wherever possible, the same reference numerals will be used throughout the drawings to represent the same or similar parts.

[0052] Furthermore, although the terms used in the present invention are selected from well-known and commonly used terms, some terms mentioned in the present invention specification may be selected by the applicant at his or her discretion, and their detailed meanings are explained in the relevant parts of the description of this document.

[0053] Furthermore, it is required that the present invention be understood not only by the actual terms used but also by the meanings connoted by each term.

[0054] Figure 1 The present invention is a schematic structural diagram of a verification test device for testing the sealing properties of a nuclear power containment vessel.

[0055] like Figure 1As shown, the present invention provides a verification test device for nuclear power containment sealing test, which adopts the form of remotely operating the local flow control unit in the data acquisition center to realize the remote control of the verification test superimposed flow. The flow measurement during the test is electronic measurement, the control method is automatic feedback control, and the data is remotely transmitted to the command center in real time.

[0056] The verification test device includes an instrument, a computer 10, a mechanical pipeline 20, an electrical line 30, a plurality of signal conversion boxes and a relay router 40. One end of the instrument (e.g., preferably a mass flow controller 50) is connected to the containment penetration interface 60 through the mechanical pipeline 20. The computer 10 (e.g., a computer) is an operating end, which is installed with operating software and is connected to the instrument through the electrical line 30 for transmitting control signals. The signal conversion box and the relay router 40 are connected between the instrument and the computer 10 at intervals through the electrical line 30, and the other end of the instrument is connected to the negative pressure shed 70.

[0057] Preferably, the instrument described here can use a mass flow controller 50. The instrument uses a mass flow controller 50 as a flow measurement and control unit, and is connected to the local containment penetration interface 60 through a mechanical pipeline 20 to achieve flow superposition to form a passage. The computer (i.e., computer 10) is used as an operating terminal, and the operating software is installed, and is connected to the mass flow controller 50 through an electrical line 30 to achieve transmission of control signals. The operating software has the functions of system start and stop, test setting, and operation mode setting.

[0058] Further preferably, a first manual ball valve 100 is provided between the instrument (i.e., the mass flow controller 50) and the negative pressure shelf 70 to control the pipeline outlet. A second manual ball valve 200 is provided between the instrument (i.e., the mass flow controller 50) and the containment penetration interface 60 to control the pipeline inlet.

[0059] Here, the signal conversion box preferably includes a primary signal conversion box 300 and a secondary signal conversion box 400, the primary signal conversion box 300 is close to the mass flow controller, and the secondary signal conversion box 400 is close to the computer.

[0060] The data signal interface of the mass flow controller 50 is preferably an R232 serial port. The primary signal conversion box 300 converts the R232 signal into an Ethernet signal, and the secondary signal conversion box 400 converts the Ethernet signal into an R232 signal, which is connected to the computer 10 via a USB interface.

[0061] The mass flow controller 50 and the primary signal conversion box 300 are powered by an integrated system, and the power supply is integrated with the primary signal conversion box 300. A bypass spare channel 500 is provided on one side of the instrument, and a third manual ball valve 600 is provided in the spare channel 500 for controlling the spare channel 500.

[0062] Here, the mechanical pipeline 20 is connected to the containment penetration interface 60 using an NPT threaded joint, and a two-way design is adopted. One of the ways is a flow control pipeline, and the other is a bypass, and the two ways are connected by a tee. The core component of the flow control pipeline is a mass flow controller 50. A first manual ball valve (V2) 100 is set upstream of the mass flow controller 50, which can quickly cut off the pipeline airflow in an emergency situation, and a section of extended pipeline is connected downstream of the controller. During the overhaul of the nuclear power unit, the pipeline outlet can be connected to the negative pressure shed in the radiation control area. If the exhaust gas is radioactive, radioactive gas control can be achieved. A third manual ball valve (V3) 600 is set on the backup channel 500 of the bypass, and the downstream of the ball valve is connected to an extension pipe, which can also be connected to the negative pressure shed 70. It has three main functions: first, exhaust sampling is performed in the initial stage of the verification test to test the radioactivity of the gas; second, before opening the control pipeline, the pipeline is purged by exhaust to prevent impurities from clogging the instrument; third, when the instrument fails, the bypass is used to connect the backup instrument to ensure that the verification test can be performed normally. The various parts of the mechanical pipeline are connected with PU pipes, and the connecting parts are in the form of ferrules to ensure the sealing of the pipeline.

[0063] The electrical line 30 connects the mass flow controller 50 to the operating computer (i.e., computer 10). The controller is located in the on-site penetration room, and the computer is placed in the collection center. The distance is generally between 50 meters and 150 meters. In order to ensure the stability of signal transmission, a network cable is required for signal transmission. The data signal interface of the controller is an R232 serial port. A primary signal conversion box 300 is required to be set next to the controller to convert the R232 signal into an Ethernet signal. A secondary signal conversion box 400 is set next to the computer (i.e., computer 10) to convert the Ethernet signal into an R232 signal, which is connected to the computer (i.e., computer 10) through a USB interface.

[0064] The transmission distance of the network cable is generally no more than 80 meters, so the network cable uses two sections, and a router is used in the middle as a signal relay to ensure the stability of signal transmission. In the electrical circuit, the mass flow controller, two signal conversion boxes, routers, computers and other equipment need to be powered. Among them, the computer, the secondary signal conversion box, and the router use the on-site power distribution cabinet for separate power supply. The mass flow controller and the primary signal conversion box use an integrated power supply, integrating the power supply with the primary conversion box. The power supply supplies power to the primary conversion box, and the primary conversion box supplies power to the mass flow controller through the signal line.

[0065] According to the above structural description, the verification test device is as follows Figure 1 Install and connect, power the primary conversion box, router, secondary conversion box, and computer, connect the mechanical pipeline outlet to the negative pressure shed, the initial state of valve V1 is closed, the initial state of valve V2 is open, and the initial state of the mass flow controller is closed (i.e., the control flow is 0).

[0066] After the installation is complete, perform a system test, start the operating software, and obtain the controller flow value. Since the initial state is closed, the initial flow value should be 0. If it is not 0 or the data cannot be obtained, it is necessary to check the instruments, electrical circuits and equipment.

[0067] After the leakage rate calculation of the containment overall sealing test is completed, the pipeline is purged first. The specific purging steps are: close valve V2, open the isolation valve of the penetration piece connected to the device, slowly open V2, use the containment exhaust to purge the leakage channel until there is no impurity, close valve V2, and open valve V1 (the second manual ball valve 200).

[0068] After the purge is completed, the calculated superimposed flow L0 value is input into the operating software as the control flow, the correct gas type and flow unit are selected, the adjustment mode is started, and the mass flow controller starts to adjust the flow to L0. After the flow is stable, the test cycle is set according to the test requirements, the test mode is started, and automatic data recording begins. After the test is completed, the system operation is stopped.

[0069] The present invention also provides a verification test method for a nuclear power containment sealing test, which uses the verification test device for a nuclear power containment sealing test as described above, and the verification test method comprises:

[0070] Step S1, hardware self-check;

[0071] Step S2: the instrument performs feedback. If the feedback value is normal, the process proceeds to step S3; if the feedback value is abnormal, the process prompts that the hardware is abnormal, and the process returns to step S1;

[0072] Step S3, setting parameters for the instrument;

[0073] Step S4, entering the adjustment mode, the instrument performs self-checking, if the result is normal, then proceeding to step S5; if the result is abnormal, then prompting hardware abnormality, and returning to step S1;

[0074] Step S5, enter the test mode, set the cycle and threshold, and then collect and display data;

[0075] Step S6: the verification test method ends.

[0076] The operating software used in the verification test device for nuclear power containment sealing test includes an instrument setting module, a data output module and a mode setting module. Among them, the instrument setting module is a basic instrument function, which can be programmed according to the instruction set, send instructions, and realize various functions of the instrument setting. For example, various functions such as start and stop (self-test), key lock, password modification, flow value setting, flow unit setting, gas type setting, range setting, minimum change span setting, valve state setting and zeroing.

[0077] The data output module is implemented by regularly reading instrument data, displaying it in real time in the software interface, drawing real-time data curves, and outputting raw data in a fixed format in the background. Its functions include reading air flow temperature, pressure, periodically reading flow values, outputting tables, and displaying data curves in real time.

[0078] The mode setting module is the main operation module during the test, such as adjustment mode and test mode.

[0079] After the mass flow controller sets the outlet flow and starts, the control valve automatically adjusts until the set flow value is reached. During this period, the flow value will fluctuate up and down, so the adjustment mode needs to be set to determine that the flow value has stabilized. The judgment of flow stability requires the input of the collection cycle and judgment conditions (stable deviation value). A flow value is collected in each cycle. If the deviation of several consecutive groups of flow values ​​does not exceed a certain value, the flow can be judged to be stable and the test mode can be stopped. After the test is completed, the test mode can be started. The test mode must have a cycle setting function, and the minimum cycle value must be set to 1min.

[0080] The verification test device for nuclear power containment sealing test of the present invention is innovatively designed based on the third-generation nuclear power containment sealing test technology and the characteristics of the verification test method. Through the intelligent operation method of the device, it reduces the manual adjustment of the superimposed leakage volume and the on-site reading and recording of data, reduces the various risks such as the irradiation risk in the process, and improves the accuracy of the containment sealing test verification stage and the accuracy of performance judgment.

[0081] In summary, the verification test device and method for nuclear power containment sealing test of the present invention have the following advantages:

[0082] 1. The accuracy, efficiency and safety of verification tests have been greatly improved;

[0083] Second, the verification test device adopts the form of remotely operating the flow control unit in the data acquisition center to realize remote control of the verification test superimposed flow, system start and stop, test mode selection and other functions, and the test state can be achieved without the need for personnel to operate the test equipment on site;

[0084] 3. Flow measurement adopts automatic reading mode of electronic flow meter. The accuracy of flow meter can reach 1%, and the reading is intuitive. The instrument has built-in pressure sensor and temperature sensor, which can automatically convert working condition and standard condition according to environmental status, without measuring local temperature and pressure.

[0085] 4. The flow control method during the test is automatic feedback control, with high flow regulation accuracy and high flow stability;

[0086] 5. During the test, there is no need for personnel to perform on-site supervision, measurement, and recording, which avoids the risk of radiation to personnel and reduces manpower consumption.

[0087] For those skilled in the art, the above invention disclosure is only used as an example and does not constitute a limitation of the present application. Although not explicitly stated herein, those skilled in the art may make various modifications, improvements and amendments to the present application. Such modifications, improvements and amendments are suggested in the present application, so such modifications, improvements and amendments still belong to the spirit and scope of the exemplary implementation of the present application.

[0088] At the same time, the present application uses specific words to describe the embodiments of the present application. For example, "one embodiment", "an embodiment", and / or "some embodiments" refer to a certain feature, structure or characteristic related to at least one embodiment of the present application. Therefore, it should be emphasized and noted that "one embodiment" or "an embodiment" or "an alternative embodiment" mentioned twice or more in different positions in this specification does not necessarily refer to the same embodiment. In addition, some features, structures or characteristics in one or more embodiments of the present application can be appropriately combined.

[0089] Although the specific embodiments of the present invention are described above, it should be understood by those skilled in the art that these are only examples, and the protection scope of the present invention is defined by the appended claims. Those skilled in the art may make various changes or modifications to these embodiments without departing from the principles and essence of the present invention, but these changes and modifications all fall within the protection scope of the present invention.

Claims

1. A verification test device for nuclear power containment sealing test, characterized in that: The verification test device includes an instrument, a computer, a mechanical pipeline, an electrical circuit, a plurality of signal conversion boxes and a relay router. One end of the instrument is connected to the containment penetration interface through the mechanical pipeline; the computer is an operating end, which is installed with operating software and is connected to the instrument through the electrical circuit for transmitting control signals; The signal conversion box and the relay router are connected between the meter and the computer at intervals through the electrical line, and the other end of the meter is connected to the negative pressure shed.

2. The verification test device for nuclear power containment sealing test according to claim 1, characterized in that: The instrument is a mass flow controller.

3. The verification test device for nuclear power containment sealing test according to claim 1, characterized in that: A first manual ball valve is arranged between the instrument and the negative pressure shelf to control the pipeline outlet.

4. The verification test device for nuclear power containment sealing test according to claim 1, characterized in that: A second manual ball valve is provided between the instrument and the containment penetration interface for controlling the pipeline inlet.

5. The verification test device for nuclear power containment sealing test according to claim 2, characterized in that: The signal conversion box includes a primary signal conversion box and a secondary signal conversion box, wherein the primary signal conversion box is close to the mass flow controller, and the secondary signal conversion box is close to the computer.

6. The verification test device for nuclear power containment sealing test according to claim 5, characterized in that: The data signal interface of the mass flow controller is an R232 serial port. The primary signal conversion box converts the R232 signal into an Ethernet signal. The secondary signal conversion box converts the Ethernet signal into an R232 signal, which is connected to the computer via a USB interface.

7. The verification test device for nuclear power containment sealing test according to claim 6, characterized in that: The mass flow controller and the primary signal conversion box are powered by an integrated system, integrating the power supply with the primary signal conversion box.

8. The verification test device for nuclear power containment sealing test according to claim 1, characterized in that: A bypass spare channel is arranged on one side of the instrument, and a third manual ball valve is arranged in the spare channel for controlling the spare channel.

9. The verification test device for nuclear power containment sealing test according to claim 1, characterized in that: The mechanical pipeline is connected to the containment penetration interface using an NPT threaded joint.

10. A verification test method for nuclear power containment sealing test, characterized in that: The verification test method adopts the verification test device for nuclear power containment sealing test according to any one of claims 1 to 9, and the verification test method comprises: S1, hardware self-check; S2, the instrument performs feedback. If the feedback value is normal, the process proceeds to step S3; if the feedback value is abnormal, the system prompts that the hardware is abnormal, and returns to step S1; S3, setting parameters of the instrument; S4, entering the adjustment mode, the instrument performs self-checking, if the result is normal, then proceed to step S5; if the result is abnormal, then prompt hardware abnormality, and return to step S1; S5, enter the test mode, set the cycle and threshold, and then collect and display data; S6. The verification test method ends.

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