Device and Method for Technical Assessment of Tube Blocking in Steam Generator of High Temperature Gas-Cooled Reactor

Abstract

The present invention discloses a device and method for technical assessment of plugging tubes in a steam generator of a high-temperature gas-cooled reactor. The device includes an inlet end header and tube sheet unit, a main steam outlet end header and assessment tube sheet unit, a steel structure, a surrounding environment unit, and an assessment management unit. Among them, the inlet end tube sheet and the main steam outlet end tube sheet are the working surfaces for welded tube plugging. The surrounding environment unit is used to assess the passability of the automated tube plugging equipment and simulate actual working conditions such as temperature. The assessment management unit mainly monitors and manages the assessment process. The present invention can realize the assessment and evaluation of the on-site applicability, joint quality, and stability of the automated welded tube plugging equipment. The assessment items mainly include: the passability of the automated welded tube plugging equipment; the timeliness of completing tasks within a specified time; the accessibility, positioning accuracy, and repeatability of the welding head after the welding device reaches the working surface. The present invention provides a platform for the verification, assessment, and operator training of the automated tube plugging technology for the steam generator of the high-temperature gas-cooled reactor.

Description

Technical Field

[0001] The present invention belongs to the field of nuclear power safety operation and maintenance support, and particularly relates to a device and method for technical assessment of tube plugging in a steam generator of a high-temperature gas-cooled reactor, belonging to the verification and assessment technology of automated welding tube plugging technology. Background Art

[0002] In October 2020, the world's first high-temperature gas-cooled reactor, abbreviated as HTR-PM, the first reactor of the nuclear power demonstration project - the primary circuit cold-state function test of the high-temperature gas-cooled reactor of Shidao Bay Nuclear Power Plant of China Huaneng Group was successfully completed at one time. In November 2020, another piece of good news came from the construction site of the world's first high-temperature gas-cooled reactor nuclear power demonstration project. The cold-state function test of the primary circuit unit of Reactor No. 1 was successfully completed again, and all indicators reached the design requirements, marking the basic completion of the world's first fourth-generation nuclear energy unit with higher safety and independent intellectual property rights in China. However, due to the significant differences in the service conditions and component sizes between the high-temperature gas-cooled reactor and the pressurized water reactor, the original safety maintenance technologies and equipment for the pressurized water reactor are difficult to be directly applied to HTR-PM.

[0003] The steam generator is one of the most critical equipment in the HTR-PM nuclear power unit and is the "lung" of the nuclear power plant. In the steam generator, the heat transfer tubes are an important part of the primary circuit pressure boundary, an important barrier to prevent the leakage of radioactive fission products, and also the weakest link in the primary circuit unit. Their total area accounts for 80% of the pressure boundary of the primary circuit coolant unit. During service, the heat transfer tubes are under the long-term erosion of high temperature, high pressure and high radiation dose media, which will cause mechanical or chemical damage, resulting in the breakage of the heat transfer tubes and the leakage of radioactive coolant, causing serious social adverse reactions and huge economic losses. Therefore, it is necessary to plug the damaged heat transfer tubes at both the feed water end and the main steam outlet to avoid major accidents. Compared with the in-service pressurized water reactor steam generator unit, the service temperature of the heat transfer tubes in the steam generator of HTR-PM is higher, and the temperature of the primary side is increased from 343°C to 750°C. The mechanical tube plugging method applied to the conventional pressurized water reactor may lead to tube plugging failure due to stress relaxation at high temperature, and its applicability is in doubt. Therefore, it is necessary to develop a new tube plugging technology based on welding metallurgy.

[0004] In addition, the higher ambient temperature (about 80°C) and the presence of a radiation environment after reactor shutdown compared to a pressurized water reactor render the manual intervention plugging method inapplicable within a controllable time. Therefore, it is necessary to develop an automated device to enter the site and weld and seal the inlets and outlets of the damaged heat exchange tubes. During the equipment development process, the optimization and improvement of the automated plugging equipment, the assessment of the applicability and stability of the forming equipment, and the training and assessment of the operators all need to be completed through long-term on-site practice. However, since it is difficult to directly complete the above processes in an operating nuclear island, it is necessary to build a device for on-site applicability verification and assessment of the welding plugging technology for the steam generator of a high-temperature gas-cooled reactor that includes the core components affecting the plugging process and establish corresponding assessment methods, and then verify, train, and assess the equipment and personnel. Summary of the Invention

[0005] Aiming at the requirements for assessment devices and methods in the development, assessment, and personnel training of the steam generator plugging technology for the fourth-generation nuclear power technology of high-temperature gas-cooled reactors, the purpose of the present invention is to provide a device and method for assessing the steam generator plugging technology of high-temperature gas-cooled reactors. The device and method can be used for the verification, assessment, and personnel training of the automated plugging technology for the steam generators of high-temperature gas-cooled reactor nuclear power plants, and provide a platform for the development of operation and maintenance auxiliary technologies for high-temperature gas-cooled reactor nuclear power plants.

[0006] The present invention is achieved through the following technical solutions:

[0007] Device for technical assessment of plugging tubes in steam generators of high-temperature gas-cooled reactors. The device includes an inlet-end header and tube sheet unit 1, a main steam outlet-end header and assessment tube sheet unit 2, a steel structure 3, a surrounding environment unit 4, and an assessment management unit 5. The inlet-end header and tube sheet unit 1, the main steam outlet-end header and tube sheet unit 2, and the surrounding environment unit 4 are supported by the steel structure 3. The inlet-end header and tube sheet unit 1 includes an inlet-end header 1-1 and an inlet-end tube sheet 1-2 connected by threads. The main steam outlet-end header and assessment tube sheet unit 2 includes a main steam outlet-end header 2-1 and a main steam outlet-end tube sheet 2-2 connected by threads. The inlet-end tube sheet 1-2 and the main steam outlet-end tube sheet 2-2 are the working surfaces for welded tube plugging. The surrounding environment unit 4 is used to assess the passability of the automatic tube plugging equipment and simulate the actual temperature conditions, including a maintenance work platform 4-2 for the inlet-end header and tube sheet unit, an inlet-end concrete protective shell and maintenance hole 4-3 for simulating entry from the external platform of the high-temperature gas-cooled reactor into the inlet-end header and tube sheet unit, a main steam outlet-end concrete protective shell and maintenance hole 4-6 for simulating entry from the external platform of the high-temperature gas-cooled reactor into the main steam outlet-end header and tube sheet unit, an inlet-end heating device 4-4 for preheating the inlet-end header and tube sheet unit by simulating the real environmental temperature, and a main steam outlet-end heating device 4-7 for preheating the main steam outlet-end header and tube sheet unit. The assessment management unit 5 monitors and manages the assessment process, including a software unit for process control and a positioning and video unit for process monitoring. The software unit and the positioning and video unit cooperate to complete the process management and inspection assessment of the assessment process.

[0008] The material of the main steam outlet-end tube sheet 2-2 is Inconly 800H nickel-based superalloy, and the material of the inlet-end tube sheet 1-2 is 2 1 / 4 Cr1Mo heat-resistant steel, which is the same as the material of the steam generator in the real high-temperature gas-cooled reactor.

[0009] The inlet-end header and tube sheet unit 1 and the main steam outlet-end header and tube sheet unit 2 are in a vertical geometric relationship and are fixed by the lower head 4-1 of the steam generator pressure vessel and the side wall surface 4-5 of the steam generator pressure vessel. The plane of the inlet-end tube sheet 1-2 is parallel to the horizontal plane, and the plane of the main steam outlet-end tube sheet 2-2 is perpendicular to the horizontal plane.

[0010] The inlet-end heating device 4-4 and the main steam outlet-end heating device 4-7 adopt the electric heating method.

[0011] The testing method of the device for assessing the pipe plugging technology of a high-temperature gas-cooled reactor steam generator is implemented according to the following testing steps: first, the assessment management unit 5 is turned on, and the assessment management unit 5 automatically turns on the water inlet heating device 4-4 and the main steam outlet heating device 4-7. After reaching the service temperature, the software unit in the assessment management unit 5 issues an instruction to start the assessment; secondly, after confirming that the object to be assessed, that is, the automated welding pipe plugging equipment, is ready, click to start the assessment process, and the software unit in the assessment management unit starts timing. The automated welding pipe plugging equipment enters the water inlet pipe box and the working surface of the tube sheet unit 1 through the surrounding environment unit 4, and locates the positions to be blocked, which are given numbers and are located at the center of the water inlet tube sheet 1-2, four at the edges of the front, back, left and right tube sheets, and a total of no less than five positions to be blocked, and the automated welding pipe plugging equipment to be assessed implements welding pipe plugging; after the automated welding pipe plugging equipment is positioned, welded, and welded, the high-resolution camera in the positioning and video unit in the assessment management unit 5 is used to monitor the positioning and video after the welding is completed. Video and image recording; after the above process is completed, the automated welding pipe plugging equipment returns to the working surface of the water inlet pipe box and tube sheet unit 1 through the surrounding environment unit 4, and completes the welding pipe plugging applicability assessment of the automated welding pipe plugging equipment to be assessed at the water inlet; after the software unit in the assessment management unit 5 confirms that the welding pipe plugging at the water inlet is completed, the main steam outlet pipe box and tube sheet unit 2 welding pipe plugging process assessment is started; the automated welding pipe plugging equipment enters the working surface of the main steam outlet pipe box and tube sheet unit 2 through the surrounding environment unit 4, and locates the position of the pipe to be plugged corresponding to the water inlet and implements the welding pipe plugging operation. After the automated welding pipe plugging equipment is positioned, welded and welded, the high-resolution camera in the positioning and video unit in the assessment management unit 5 is used to record the video and image, and the welding pipe plugging applicability assessment of the main steam outlet pipe box and tube sheet unit 2 is completed; finally, the water inlet tube sheet 1-2 and the main steam outlet tube sheet 2-2 are cut and sampled, and then the quality of the joints of the automated welding pipe plugging equipment is evaluated.

[0012] The specific process of evaluating the quality of the joint is as follows: the passability of the automated welding pipe plugging equipment is judged based on video information: whether there is a collision with surrounding devices during the entry and exit process, and whether there is an unreasonable pause of more than 10 seconds; the timeliness of completing the task within the specified time, that is, whether the time for the automated welding pipe plugging equipment to reach the working surface, position, and weld exceeds the specified time; the accessibility, positioning accuracy and repeatability of the welding head after the welding device reaches the working surface, that is, based on high-resolution images, it is judged whether the welding head reaches the center of the tube plate and the four front, back, left and right circumferential weld positions to be blocked, whether the lateral difference between the actual position and the target position is greater than the specified value, and whether the difference in three repeated positioning of the same position to be blocked is greater than the specified value.

[0013] The items and test methods for evaluating the joint quality of automated welding pipe plugging equipment include: crack detection - penetrant testing; weld penetration - metallographic testing; mechanical properties - tensile testing.

[0014] The present invention also has the following advantages:

[0015] 1) The software and hardware technologies in the assessment management unit cooperate with each other, not only realizing on-site assessment, but also feedbacking the improvement of the automatic pipe plugging technology through the accumulation of failure numerical data and image and video data.

[0016] 2) The replacement of the tube sheet material can be synchronized with the update of the high-temperature gas-cooled reactor steam generator material, so as to be used for the verification of the pipe plugging technology for updating nuclear power technology.

[0017] 3) The outer facade of the device is made of transparent organic glass, significantly enhancing the visibility of the device, so it is convenient for the training and teaching of relevant personnel. Description of the Drawings

[0018] Figure 1 It is a three-dimensional view of the device for the assessment of the pipe plugging technology of the high-temperature gas-cooled reactor steam generator of the present invention.

[0019] Figure 2 It is a cross-sectional view of the device for the assessment of the pipe plugging technology of the high-temperature gas-cooled reactor steam generator of the present invention.

[0020] Figure 3 It is a structural diagram of the water inlet end tube sheet and tube box unit and the surrounding environment unit of the device of the present invention.

[0021] Figure 4 It is a structural diagram of the main steam outlet end tube sheet and tube box unit and the surrounding environment unit of the device of the present invention. Detailed Description of the Invention

[0022] The following combines specific embodiments and the appended Figure 1 to further elaborate on the present invention in detail. The above is an explanation of the present invention rather than a limitation.

[0023] Such as Figure 1 、 Figure 2 、 Figure 3 and Figure 4As shown in the figure, the device of the present invention for the technical assessment of the plugging of tubes in a high-temperature gas-cooled reactor steam generator includes an inlet-end header and tube sheet unit 1, a main steam outlet-end header and assessment tube sheet unit 2, a steel structure 3, a surrounding environment unit 4, and an assessment management unit 5. The inlet-end header and tube sheet unit 1, the main steam outlet-end header and tube sheet unit 2, and the surrounding environment unit 4 are supported by the steel structure 3. The inlet-end header and tube sheet unit 1 includes an inlet-end header 1-1 and an inlet-end tube sheet 1-2 connected by threads. The main steam outlet-end header and assessment tube sheet unit 2 includes a main steam outlet-end header 2-1 and a main steam outlet-end tube sheet 2-2 connected by threads. Among them, the inlet-end tube sheet 1-2 and the main steam outlet-end tube sheet 2-2 are the working surfaces for welded tube plugging. The surrounding environment unit 4 is used to assess the passability of the automated tube plugging equipment and simulate the actual temperature conditions, including a maintenance work platform 4-2 for the inlet-end header and tube sheet unit, an inlet-end concrete protective shell and maintenance hole 4-3 for simulating the entry from the external platform of the high-temperature gas-cooled reactor into the inlet-end header and tube sheet unit, a main steam outlet-end concrete protective shell and maintenance hole 4-6 for simulating the entry from the external platform of the high-temperature gas-cooled reactor into the main steam outlet-end header and tube sheet unit, an inlet-end heating device 4-4 for preheating the inlet-end header and tube sheet unit by simulating the real environmental temperature, and a main steam outlet-end heating device 4-7 for preheating the main steam outlet-end header and tube sheet unit. The assessment management unit 5 monitors the implementation and manages the process of the assessment, including a software unit for process control and a positioning and video unit for process monitoring. The software unit and the positioning and video unit cooperate to complete the process management and inspection assessment of the assessment process.

[0024] As a preferred embodiment of the present invention, the material of the main steam outlet-end tube sheet 2-2 is Inconly 800H nickel-based superalloy, and the material of the inlet-end tube sheet 1-2 is 2 1 / 4 Cr1Mo heat-resistant steel, which is the same as the material of the real high-temperature gas-cooled reactor steam generator, and the optimized welding parameters can be directly used for the tube plugging operation under real conditions.

[0025] As a preferred embodiment of the present invention, the inlet-end header and tube sheet unit 1 and the main steam outlet-end header and tube sheet unit 2 are in an upper and lower geometric relationship and are fixed by the lower head 4-1 of the steam generator pressure vessel and the side wall surface 4-5 of the steam generator pressure vessel. The plane of the inlet-end tube sheet 1-2 is parallel to the horizontal plane, and the plane of the main steam outlet-end tube sheet 2-2 is perpendicular to the horizontal plane, which is the same as that on-site of the high-temperature gas-cooled reactor. It can realize the assessment of the passability, position accessibility, and welding posture feasibility of the device to be assessed when entering the site.

[0026] As a preferred embodiment of the present invention, the water inlet end heating device 4-4 and the main steam outlet end heating device 4-7 adopt an electric heating method. Since the heating components are respectively located on the outer wall surfaces of the water inlet end header 1-1 and the main steam outlet end header 2-1, compared with heating methods such as infrared light irradiation and hot air, the heating devices are not inside the header and will not cause obstacles to the operation of the equipment to be tested.

[0027] The test method of the device for the plugging tube technology assessment of the high-temperature gas-cooled reactor steam generator of the present invention is implemented according to the following test steps: First, turn on the assessment management unit 5, and the assessment management unit 5 automatically turns on the water inlet end heating device 4-4 and the main steam outlet end heating device 4-7. After reaching the service temperature, the software unit in the assessment management unit 5 issues an instruction that the assessment can start; Second, after confirming that the object to be tested, that is, the automated welding plugging equipment, is ready, click the start assessment process. The software unit in the assessment management unit starts timing. The automated welding plugging equipment enters the working surface of the water inlet end header and the tube sheet unit 1 through the peripheral environment unit 4, and positions the plugging positions with given numbers, including one in the center of the water inlet end tube sheet 1-2 and four at the edges of the front, back, left, and right tube sheets, with a total of no less than five positions, and the automated welding plugging equipment to be tested performs welding plugging; After the positioning, welding, and completion of welding of the automated welding plugging equipment, video and image records are made through the high-resolution camera in the positioning and video unit of the assessment management unit 5; After the above process is completed, the automated welding plugging equipment returns to the working surface of the water inlet end header and the tube sheet unit 1 through the peripheral environment unit 4 to complete the applicability assessment of the automated welding plugging equipment for welding plugging at the water inlet end; After the software unit in the assessment management unit 5 confirms the completion of welding plugging at the water inlet end, it starts the assessment of the welding plugging process of the main steam outlet end header and the tube sheet unit 2; The automated welding plugging equipment enters the working surface of the main steam outlet end header and the tube sheet unit 2 through the peripheral environment unit 4, positions the tube positions to be plugged corresponding to the water inlet end, and performs welding plugging operations. After the positioning, welding, and completion of welding of the automated welding plugging equipment, video and image records are made through the high-resolution camera in the positioning and video unit of the assessment management unit 5 to complete the applicability assessment of the welding plugging of the main steam outlet end header and the tube sheet unit 2; Finally, the water inlet end tube sheet 1-2 and the main steam outlet end tube sheet 2-2 are cut and sampled, and then the quality of the joints of the automated welding plugging equipment is evaluated. The items and test methods for evaluating the quality of the joints of the automated welding plugging equipment are: crack detection - penetrant testing; weld penetration - metallographic testing; mechanical properties - tensile testing.

[0028] As a preferred embodiment of the present invention, the specific process of evaluating the quality of the joint is as follows: the passability of the automated welding pipe plugging equipment is judged based on video information: whether the entry and exit process collides with the surrounding devices, and whether there is an unreasonable pause of more than 10 seconds; the timeliness of completing the task within the specified time, that is, whether the time for the automated welding pipe plugging equipment to reach the working surface, position, and weld exceeds the specified time; the accessibility, positioning accuracy and repeatability of the welding head after the welding device reaches the working surface, that is, based on the high-resolution image, it is judged whether the welding head reaches the center of the tube plate and the four front, back, left and right ring weld positions to be blocked, whether the lateral difference between the actual position and the target position is greater than the specified value, and whether the difference in the three repeated positioning of the same position to be blocked is greater than the specified value. The assessment of the timeliness, accessibility and accuracy of the equipment to be assessed can be efficiently completed.

Claims

1. A device for the technical assessment of plugging tubes in a high-temperature gas-cooled reactor steam generator, characterized in that: The device includes an inlet end header and tube sheet unit (1), a main steam outlet end header and test tube sheet unit (2), a steel structure (3), a surrounding environment unit (4), and a test management unit (5); the inlet end header and tube sheet unit (1), the main steam outlet end header and test tube sheet unit (2), and the surrounding environment unit (4) are supported by the steel structure (3); the inlet end header and tube sheet unit (1) includes an inlet end header (1-1) and an inlet end tube sheet (1-2) connected by threads, and the main steam outlet end header and test tube sheet unit (2) includes a main steam outlet end header (2-1) and a main steam outlet end tube sheet (2-2) connected by threads, wherein the inlet end tube sheet (1-2) and the main steam outlet end tube sheet (2-2) are the working surfaces for welding and plugging tubes; the surrounding environment unit (4) is used to test the passability of the automatic tube plugging equipment and simulate the actual temperature conditions, including a maintenance work platform (4-2) for the inlet end header and tube sheet unit, an inlet end concrete protective shell and maintenance hole (4-3) for simulating entry from the external platform of the high-temperature gas-cooled reactor into the inlet end header and tube sheet unit, a main steam outlet end concrete protective shell and maintenance hole (4-6) for simulating entry from the external platform of the high-temperature gas-cooled reactor into the main steam outlet end header and tube sheet unit, an inlet end heating device (4-4) for preheating the inlet end header and tube sheet unit by simulating the real environmental temperature, and a main steam outlet end heating device (4-7) for preheating the main steam outlet end header and tube sheet unit; the test management unit (5) monitors and manages the test process, including a software unit for process control and a positioning and video unit for process monitoring, and the software unit and the positioning and video unit cooperate to complete the process management and test assessment of the test process.

2. The device for the technical assessment of plugging tubes in a high-temperature gas-cooled reactor steam generator according to claim 1, characterized in that: The material of the main steam outlet tube sheet (2-2) is Inconly 800H nickel-based superalloy, and the material of the water inlet tube sheet (1-2) is 2 1 / 4 Cr1Mo heat-resistant steel, which is the same as the material of the steam generator of the real high-temperature gas-cooled reactor.

3. The device for the technical assessment of plugging tubes in a high-temperature gas-cooled reactor steam generator according to claim 1, characterized in that: The inlet end header and tube sheet unit (1) and the main steam outlet end header and tube sheet unit (2) are in a vertical geometric relationship and are fixed by the lower head (4-1) of the steam generator pressure vessel and the side wall surface (4-5) of the steam generator pressure vessel. The plane of the inlet end tube sheet (1-2) is parallel to the horizontal plane, and the plane of the main steam outlet end tube sheet is perpendicular to the horizontal plane.

4. The device for the technical assessment of plugging tubes in a high-temperature gas-cooled reactor steam generator according to claim 1, characterized in that: The inlet end heating device (4-4) and the main steam outlet end heating device (4-7) adopt the electric heating method.

5. The device for the technical assessment of plugging tubes in a high-temperature gas-cooled reactor steam generator according to claim 1, characterized in that: The outer facade of the device is made of transparent organic glass, which enhances the visibility of the device.

6. A test method for the device for the technical assessment of plugging tubes in a high-temperature gas-cooled reactor steam generator according to any one of claims 1 to 5, characterized in that: The test is implemented according to the following steps: first, the assessment management unit (5) is turned on, and the assessment management unit (5) automatically turns on the water inlet heating device (4-4) and the main steam outlet heating device (4-7). After reaching the service temperature, the software unit in the assessment management unit (5) issues an assessment start instruction; second, after confirming that the object to be assessed, i.e., the automated welding pipe plugging equipment, is ready, click to start the assessment process, and the software unit in the assessment management unit starts timing. The automated welding pipe plugging equipment enters the water inlet pipe box and the tube sheet unit (1) working surface through the surrounding environment unit (4), and locates the given numbered and respectively located at the center of the water inlet tube sheet (1-2), four at the front, back, left and right edges of the tube sheet, a total of not less than five locations to be blocked, and the automated welding pipe plugging equipment to be assessed performs welding pipe plugging; after the automated welding pipe plugging equipment is positioned, welded, and the welding is completed, the video and image are recorded by the high-resolution camera in the positioning and video unit in the assessment management unit (5); after the above process is completed, the automated welding pipe plugging equipment is automatically The automated welding pipe plugging equipment returns to the working surface of the water inlet pipe box and tube sheet unit (1) through the surrounding environment unit (4), and completes the welding pipe plugging applicability assessment of the automated welding pipe plugging equipment at the water inlet; after the software unit in the assessment management unit (5) confirms that the welding pipe plugging at the water inlet is completed, the welding pipe plugging process assessment of the main steam outlet pipe box and tube sheet unit (2) is started; the automated welding pipe plugging equipment enters the working surface of the main steam outlet pipe box and tube sheet unit (2) through the surrounding environment unit (4), locates the position of the pipe to be plugged corresponding to the water inlet, and performs welding pipe plugging operations. After the automated welding pipe plugging equipment is positioned, welded, and welded, the high-resolution camera in the positioning and video unit in the assessment management unit (5) is used to record video and images, and the welding pipe plugging applicability assessment of the main steam outlet pipe box and tube sheet unit (2) is completed; finally, the water inlet tube sheet (1-2) and the main steam outlet tube sheet (2-2) are cut and sampled, and then the quality of the joints of the automated welding pipe plugging equipment is evaluated.

7. The test method according to claim 6, characterized in that: The specific process of evaluating the quality of the joint is as follows: the passability of the automated welding pipe plugging equipment is judged based on video information: whether there is a collision with surrounding devices during the entry and exit process, and whether there is an unreasonable pause of more than 10 seconds; the timeliness of completing the task within the specified time, that is, whether the time for the automated welding pipe plugging equipment to reach the working surface, position, and weld exceeds the specified time; the accessibility, positioning accuracy and repeatability of the welding head after the welding device reaches the working surface, that is, based on high-resolution images, it is judged whether the welding head reaches the center of the tube plate and the four front, back, left and right circumferential weld positions to be blocked, whether the lateral difference between the actual position and the target position is greater than the specified value, and whether the difference in three repeated positioning of the same position to be blocked is greater than the specified value.

8. The test method according to claim 6, characterized in that: The items and test methods for evaluating the joint quality of automated welding pipe plugging equipment include: crack detection - penetrant testing; weld penetration - metallographic testing; mechanical properties - tensile testing.

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