CN114519945A - Device and method for high-temperature gas cooled reactor steam generator pipe plugging technical examination - Google Patents

Device and method for high-temperature gas cooled reactor steam generator pipe plugging technical examination Download PDF

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Publication number
CN114519945A
CN114519945A CN202210299141.2A CN202210299141A CN114519945A CN 114519945 A CN114519945 A CN 114519945A CN 202210299141 A CN202210299141 A CN 202210299141A CN 114519945 A CN114519945 A CN 114519945A
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pipe
unit
water inlet
inlet end
examination
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刘福广
杨二娟
米紫昊
李勇
刘刚
王艳松
韩天鹏
杨兰
雒晓涛
王博
张周博
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Xian Jiaotong University
Xian Thermal Power Research Institute Co Ltd
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Xian Jiaotong University
Xian Thermal Power Research Institute Co Ltd
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Priority to CN202210299141.2A priority Critical patent/CN114519945A/en
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    • G—PHYSICS
    • G09—EDUCATION; CRYPTOGRAPHY; DISPLAY; ADVERTISING; SEALS
    • G09B—EDUCATIONAL OR DEMONSTRATION APPLIANCES; APPLIANCES FOR TEACHING, OR COMMUNICATING WITH, THE BLIND, DEAF OR MUTE; MODELS; PLANETARIA; GLOBES; MAPS; DIAGRAMS
    • G09B9/00—Simulators for teaching or training purposes
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/18—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being a hot gas, e.g. waste gas such as exhaust gas of internal-combustion engines
    • F22B1/1823—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being a hot gas, e.g. waste gas such as exhaust gas of internal-combustion engines for gas-cooled nuclear reactors
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for

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  • Physics & Mathematics (AREA)
  • Theoretical Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • Thermal Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Business, Economics & Management (AREA)
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  • Educational Technology (AREA)
  • General Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a device and a method for technical examination of pipe plugging of a high-temperature gas cooled reactor steam generator, wherein the device comprises a water inlet end pipe box and pipe plate unit, a main steam outlet end pipe box and examination pipe plate unit, a steel structure, a peripheral environment unit and an examination management unit, wherein the water inlet end pipe plate and the main steam outlet end pipe plate are working surfaces for welding the pipe plugging, the peripheral environment unit is used for examining the trafficability of automatic pipe plugging equipment and simulating practical working conditions such as temperature, and the examination management unit is mainly used for implementing monitoring and process management on an examination process. The invention can realize the assessment and evaluation of the field applicability, the joint quality and the stability of automatic welding pipe plugging equipment, and the assessment items mainly comprise: the permeability of automatic welding pipe plugging equipment is improved; timeliness of completing tasks within a specified time; accessibility, positioning accuracy and repeatability of a welding head of the welding device after the welding device reaches a working face; the invention provides a platform for verification, assessment and operator training of the automatic pipe plugging technology of the high-temperature gas cooled reactor steam generator.

Description

Device and method for high-temperature gas cooled reactor steam generator pipe plugging technical examination
Technical Field
The invention belongs to the field of nuclear power safe operation and maintenance, particularly relates to a device and a method for checking a pipe plugging technology of a high-temperature gas cooled reactor steam generator, and belongs to a verification and checking technology of an automatic welding pipe plugging technology.
Background
In 10 months in 2020, a primary loop cold function test of a global first high-temperature gas cooled reactor, called HTR-PM for short, of a nuclear power demonstration project global first reactor-Huaneng group Shijiwan nuclear power station is successful once. And the construction site of the first global high-temperature gas-cooled reactor nuclear power demonstration engineering in 11 months in 2020 is reported in a short time, the cold-state function test of the first loop unit of the reactor No. 1 is completed smoothly again, all indexes meet the design requirements, and the fourth generation nuclear power unit with higher security of the first global and having independent intellectual property rights in China is marked to be basically built. But the obvious difference between the service working condition and the component size of the pressurized water reactor makes the original safety maintenance technology and equipment for the pressurized water reactor difficult to be used for HTR-PM.
The steam generator is one of the most critical devices in the HTR-PM nuclear power unit, and is the lung of the nuclear power. In a steam generator, heat transfer tubes are an important component of the primary circuit pressure boundary, are important barriers for preventing radioactive fission product leakage, and are also the weakest link of the primary circuit unit, and the total area of the heat transfer tubes accounts for 80% of the primary circuit coolant unit pressure boundary. In the service process, the heat transfer pipe can be mechanically or chemically damaged under the washing of high-temperature, high-pressure and high-radiation dose media for a long time, so that the heat transfer pipe is damaged, radioactive coolant leaks, serious bad social reaction and huge economic loss are caused, and therefore the damaged heat transfer pipe needs to be plugged from the water supply end and the two ends of the main steam outlet, and major accidents are avoided. Compared with the steam generator unit of the in-service pressurized water reactor, the service temperature of the heating pipe of the steam generator in the HTR-PM is higher, and the temperature of the primary side is increased from 343 ℃ to 750 ℃. The mechanical pipe plugging method applied to the conventional pressurized water reactor may cause pipe plugging failure due to stress relaxation at high temperature, and the applicability is questionable. Therefore, new techniques for plugging pipes based on weld metallurgy are needed.
In addition, the higher ambient temperature (about 80 ℃) and the presence of a radiant environment after shutdown compared to a pressurized water reactor make the manually-intervened tube plugging method no longer applicable within a controlled time, and therefore an automated device must be developed to enter the field and weld and plug the inlet and outlet of the damaged heat exchange tube. Optimization and improvement of automatic pipe plugging equipment, assessment of the applicability and stability of the forming equipment and training and assessment of operators in the equipment development process need to be completed through long-term field practice. However, the above process is difficult to be directly completed in a nuclear island in service, so a device for verifying and examining the field applicability of the 1:1 high-temperature gas cooled reactor steam generator welding pipe plugging technology, which comprises a core component influencing the pipe plugging process, needs to be built, a corresponding examination method needs to be established, and equipment and personnel are verified, trained and examined.
Disclosure of Invention
The invention aims to provide a device and a method for checking the pipe plugging technology of a steam generator of a high-temperature gas-cooled reactor nuclear power plant aiming at the requirements of the pipe plugging technology development, the check and the personnel training of the steam generator of the fourth-generation nuclear power technology on the checking device and the method.
The invention is realized by the following technical scheme:
the device for the technical examination of the pipe plugging of the high-temperature gas cooled reactor steam generator comprises a water inlet end pipe box and pipe plate unit 1, a main steam outlet end pipe box and examination pipe plate unit 2, a steel structure 3, a peripheral environment unit 4 and an examination management unit 5; the water inlet end pipe box and the pipe plate unit 1, the main steam outlet end pipe box and the pipe plate unit 2 and the surrounding environment unit 4 are supported by a steel structure 3; the water inlet end pipe box and tube plate unit 1 comprises a water inlet end pipe box 1-1 and a water inlet end tube plate 1-2 which are connected through threads, the main steam outlet end pipe box and tube plate unit 2 comprises a main steam outlet end pipe box 2-1 and a main steam outlet end tube plate 2-2 which are connected through threads, and the water inlet end tube plate 1-2 and the main steam outlet end tube plate 2-2 are working surfaces for welding and blocking tubes; the peripheral environment unit 4 is used for checking the trafficability of automatic pipe plugging equipment and simulating temperature actual working conditions and comprises a maintenance working platform 4-2 of a water inlet end pipe box and a pipe plate unit, a water inlet end concrete protective shell and a maintenance hole 4-3 for simulating the water inlet end pipe box and the pipe plate unit entering from an external platform of the high-temperature gas cooled reactor, a main steam outlet end concrete protective shell and a maintenance hole 4-6 for simulating the main steam outlet end pipe box and the pipe plate unit entering from the external platform of the high-temperature gas cooled reactor, a water inlet end heating device 4-4 for simulating real environment temperature to preheat the water inlet end pipe box and the pipe plate unit, and a main steam outlet end heating device 4-7 for preheating the main steam outlet end pipe box and the pipe plate unit; the assessment management unit 5 is used for monitoring and managing the assessment process, and comprises a software unit for flow control and a positioning and video unit for process monitoring, wherein the software unit and the positioning and video unit are matched to complete the process management and detection assessment of the assessment process.
The material of the main steam outlet end tube plate 2-2 is Inconly 800H nickel-based high-temperature alloy, and the material of the water inlet end tube plate 1-2 is 21/4The Cr1Mo heat-resistant steel is consistent with the material of a steam generator of a real high-temperature gas cooled reactor.
The water inlet end tube box and the tube plate unit 1 and the main steam outlet end tube box and the tube plate unit 2 are in a vertical geometric relationship and are fixed through a lower seal head 4-1 of a steam generator pressure vessel and a side wall surface 4-5 of the steam generator pressure vessel, the plane of the water inlet end tube plate 1-2 is parallel to the horizontal plane, and the plane 2-2 of the main steam outlet end tube plate is vertical to the horizontal plane.
The water inlet end heating device 4-4 and the main steam outlet end heating device 4-7 adopt an electric heating mode.
The testing method of the device for the technical examination of the pipe plugging of the high-temperature gas cooled reactor steam generator is implemented according to the following testing steps: firstly, starting an examination management unit 5, automatically opening a water inlet end heating device 4-4 and a main steam outlet end heating device 4-7 by the examination management unit 5, and sending an examination starting instruction by a software unit in the examination management unit 5 after the service temperature is reached; secondly, after confirming that an object to be examined, namely the automatic welding pipe plugging device, is completely prepared, clicking to start an examination process, starting timing by a software unit in an examination management unit, enabling the automatic welding pipe plugging device to enter working faces of a water inlet end pipe box and a pipe plate unit 1 through a peripheral environment unit 4, positioning positions to be blocked which are numbered and are respectively positioned at the center of a water inlet end pipe plate 1-2, four at the front, the back, the left and the right pipe plates, and not less than five positions to be blocked in total, and performing welding pipe plugging by the automatic welding pipe plugging device to be examined; after the automatic welding pipe plugging equipment is positioned, welded and welded, video and image recording is carried out through a high-resolution camera in a positioning and video unit in the examination management unit 5; after the process is finished, the automatic welding pipe plugging equipment returns to the working surface of the water inlet end pipe box and the pipe plate unit 1 through the surrounding environment unit 4, and the suitability of the automatic welding pipe plugging equipment to be examined on the welding pipe plugging of the water inlet end is examined; after the software unit in the examination management unit 5 confirms that the welding of the water inlet end and the pipe plugging are finished, the process of welding and pipe plugging of the main steam outlet end pipe box and the pipe plate unit 2 is started for examination; the automatic welding pipe plugging device enters the working surface of the main steam outlet end pipe box and the pipe plate unit 2 through the surrounding environment unit 4, positions a pipe to be plugged corresponding to the water inlet end and performs welding pipe plugging operation, and after the automatic welding pipe plugging device is positioned, welded and welded, video and image recording is performed through a high-resolution camera in a positioning and video unit in the examination management unit 5, so that the suitability of the welding pipe plugging of the main steam outlet end pipe box and the pipe plate unit 2 is examined; and finally, cutting and sampling the water inlet end tube plate 1-2 and the main steam outlet end tube plate 2-2, and then evaluating the quality of the automatic welding pipe plugging equipment joint.
The specific process for evaluating the quality of the joint is as follows: the passability of the automatic welding pipe plugging equipment is judged based on video information: whether the in-out process collides with peripheral devices or not and whether the pause exceeds 10s due to the existence or nonexistence; the timeliness of completing the task within the specified time, namely whether the time for the automatic welding pipe plugging equipment to reach the working surface, position and weld exceeds the specified time or not; the accessibility, the positioning accuracy and the repeatability of a welding head after the welding device reaches a working face are that whether the welding head reaches one position of the center of the tube plate and the positions of circumferential welds of four positions to be blocked, front, back, left and right, is judged based on a high-resolution image, whether the transverse difference between the actual position and the target position is greater than a specified value or not, and whether the three-time repeated positioning difference of the same position to be blocked is greater than the specified value or not is judged.
The project and the test method for evaluating the joint quality of the automatic welding pipe plugging equipment comprise the following steps: crack detection-penetrant inspection; weld penetration-metallographic detection; mechanical properties-tensile test.
The invention also has the following advantages:
1) software in the examination management unit is matched with hardware technology, so that not only is on-site examination realized, but also the feedback automatic pipe plugging technology can be improved through accumulation of failure numerical data and image video data.
2) The method can realize the synchronization with the updating of the high-temperature gas cooled reactor steam generator material by replacing the tube plate material so as to be used for verifying the tube plugging technology of the updating nuclear power technology.
3) The outer facade of the device is transparent organic glass, so that the visibility of the device is obviously enhanced, and the device is convenient for training and teaching of related personnel.
Drawings
Fig. 1 is a perspective view of the device for technical examination of pipe plugging of a steam generator of a high temperature gas cooled reactor according to the present invention.
Fig. 2 is a cross-sectional view of the device for technical examination of pipe plugging of the steam generator of the high temperature gas cooled reactor.
FIG. 3 is a schematic diagram of the water inlet tube plate, tube box unit and surrounding environment unit of the apparatus of the present invention.
FIG. 4 is a block diagram of the primary steam outlet end tube sheet and tube box unit and the surrounding environment unit of the apparatus of the present invention.
Detailed Description
The present invention will now be described in further detail with reference to the following detailed description and accompanying drawings of which, by way of illustration and not limitation, the invention is described.
As shown in fig. 1, fig. 2, fig. 3 and fig. 4, the device for technical examination of tube plugging of a high temperature gas cooled reactor steam generator of the present invention comprises a water inlet end tube box and tube plate unit 1, a main steam outlet end tube box and examination tube plate unit 2, a steel structure 3, a peripheral environment unit 4 and an examination management unit 5; the water inlet end pipe box and the pipe plate unit 1, the main steam outlet end pipe box and the pipe plate unit 2 and the surrounding environment unit 4 are supported by a steel structure 3; the water inlet end pipe box and tube plate unit 1 comprises a water inlet end pipe box 1-1 and a water inlet end tube plate 1-2 which are connected through threads, the main steam outlet end pipe box and tube plate unit 2 comprises a main steam outlet end pipe box 2-1 and a main steam outlet end tube plate 2-2 which are connected through threads, and the water inlet end tube plate 1-2 and the main steam outlet end tube plate 2-2 are working surfaces for welding and blocking tubes; the peripheral environment unit 4 is used for checking the trafficability of automatic pipe plugging equipment and simulating temperature actual working conditions and comprises a maintenance working platform 4-2 of a water inlet end pipe box and a pipe plate unit, a water inlet end concrete protective shell and a maintenance hole 4-3 for simulating the water inlet end pipe box and the pipe plate unit entering from an external platform of the high-temperature gas cooled reactor, a main steam outlet end concrete protective shell and a maintenance hole 4-6 for simulating the main steam outlet end pipe box and the pipe plate unit entering from the external platform of the high-temperature gas cooled reactor, a water inlet end heating device 4-4 for simulating real environment temperature to preheat the water inlet end pipe box and the pipe plate unit, and a main steam outlet end heating device 4-7 for preheating the main steam outlet end pipe box and the pipe plate unit; the assessment management unit 5 is used for monitoring and managing the assessment process, and comprises a software unit for flow control and a positioning and video unit for process monitoring, wherein the software unit and the positioning and video unit are matched to complete the process management and detection assessment of the assessment process.
In a preferred embodiment of the present invention, the material of the main steam outlet end plate 2-2 is Inconly 800H nickel-based superalloy, and the material of the water inlet end plate 1-2 is 21/4The Cr1Mo heat-resistant steel is consistent with the material of a real high-temperature gas cooled reactor steam generator, and can directly use optimized welding parameters for pipe plugging operation under real working conditions.
As a preferred embodiment of the invention, the water inlet end tube box and the tube plate unit 1 and the main steam outlet end tube box and the tube plate unit 2 are in a vertical geometric relationship and are fixed through a lower end socket 4-1 of a pressure vessel of a steam generator and a side wall surface 4-5 of the pressure vessel of the steam generator, the plane of the water inlet end tube plate 1-2 is parallel to a horizontal plane, the plane 2-2 of the tube plate of the main steam outlet end is vertical to the horizontal plane and is consistent with the site of a high-temperature gas cooled reactor, and the passing ability, the position accessibility and the welding posture feasibility of the device to be examined entering the site can be examined.
As a preferred embodiment of the invention, the water inlet end heating device 4-4 and the main steam outlet end heating device 4-7 adopt an electric heating mode, and as the heating parts are respectively positioned on the outer wall surfaces of the water inlet end pipe box 1-1 and the main steam outlet end pipe box 2-1, compared with the heating modes such as infrared illumination, hot air and the like, the heating devices are not arranged in the pipe boxes, and cannot cause obstacles to the operation of equipment to be checked.
The invention discloses a testing method of a device for the technical evaluation of pipe plugging of a high-temperature gas cooled reactor steam generator, which is implemented according to the following testing steps: firstly, starting an examination management unit 5, automatically opening a water inlet end heating device 4-4 and a main steam outlet end heating device 4-7 by the examination management unit 5, and sending an examination starting instruction by a software unit in the examination management unit 5 after the service temperature is reached; secondly, after confirming that an object to be examined, namely the automatic welding pipe plugging device, is completely prepared, clicking to start an examination process, starting timing by a software unit in an examination management unit, enabling the automatic welding pipe plugging device to enter working faces of a water inlet end pipe box and a pipe plate unit 1 through a peripheral environment unit 4, positioning positions to be blocked which are numbered and are respectively positioned at the center of a water inlet end pipe plate 1-2, four at the front, the back, the left and the right pipe plates, and not less than five positions to be blocked in total, and performing welding pipe plugging by the automatic welding pipe plugging device to be examined; after the automatic welding pipe plugging equipment is positioned, welded and welded, video and image recording is carried out through a high-resolution camera in a positioning and video unit in the examination management unit 5; after the process is finished, the automatic welding pipe plugging equipment returns to the working surface of the water inlet end pipe box and the pipe plate unit 1 through the surrounding environment unit 4, and the suitability of the automatic welding pipe plugging equipment to be examined on the welding pipe plugging of the water inlet end is examined; after the software unit in the examination management unit 5 confirms that the welding of the water inlet end and the pipe plugging are finished, the process of welding and pipe plugging of the main steam outlet end pipe box and the pipe plate unit 2 is started for examination; the automatic welding pipe plugging device enters the working surface of the main steam outlet pipe box and the pipe plate unit 2 through the surrounding environment unit 4, positions a pipe to be plugged corresponding to the water inlet end and performs welding pipe plugging operation, and after the automatic welding pipe plugging device is positioned, welded and welded, videos and image records are performed through a high-resolution camera in a positioning and video unit in the examination management unit 5, so that the suitability examination of the welding pipe plugging of the main steam outlet pipe box and the pipe plate unit 2 is completed; and finally, cutting and sampling the water inlet end tube plate 1-2 and the main steam outlet end tube plate 2-2, and then evaluating the quality of the joint of the automatic welding pipe plugging equipment. The project and the test method for evaluating the joint quality of the automatic welding pipe plugging equipment comprise the following steps: crack detection-penetrant inspection; weld penetration-metallographic detection; mechanical properties-tensile test.
As a preferred embodiment of the present invention, a specific procedure for evaluating the quality of the joint is as follows: the passability of the automatic welding pipe plugging equipment is judged based on video information: whether the in-out process collides with peripheral devices or not and whether the pause exceeds 10s due to the existence or nonexistence; the timeliness of completing the task within the specified time, namely whether the time for the automatic welding pipe plugging equipment to reach the working surface, position and weld exceeds the specified time or not; the accessibility, the positioning accuracy and the repeatability of a welding head after the welding device reaches a working face are judged whether the welding head reaches one position of the center of the tube plate and the positions of circumferential welds of four positions to be blocked, namely the front position, the rear position, the left position and the right position, are all reached based on a high-resolution image, whether the transverse difference between the actual position and the target position is greater than a specified value or not, and whether the three-time repeated positioning difference of the same position to be blocked is greater than a specified value or not can efficiently finish the examination of the timeliness, the accessibility and the accuracy of equipment to be examined.

Claims (8)

1. A device for high temperature gas cooled reactor steam generator pipe blockage technical examination, its characterized in that: the device comprises a water inlet end pipe box and pipe plate unit (1), a main steam outlet end pipe box and examination pipe plate unit (2), a steel structure (3), a surrounding environment unit (4) and an examination management unit (5); the water inlet end pipe box and the pipe plate unit (1), the main steam outlet end pipe box and the pipe plate unit (2) and the surrounding environment unit (4) are supported by a steel structure (3); the water inlet end tube box and tube plate unit (1) comprises a water inlet end tube box (1-1) and a water inlet end tube plate (1-2) which are connected through threads, the main steam outlet end tube box and examination tube plate unit (2) comprises a main steam outlet end tube box (2-1) and a main steam outlet end tube plate (2-2) which are connected through threads, and the water inlet end tube plate (1-2) and the main steam outlet end tube plate (2-2) are working surfaces for welding and blocking tubes; the peripheral environment unit (4) is used for checking the trafficability of automatic pipe plugging equipment and simulating temperature actual working conditions and comprises a maintenance working platform (4-2) of a water inlet end pipe box and a pipe plate unit, a water inlet end concrete protective shell and a maintenance hole (4-3) for simulating the water inlet end pipe box and the pipe plate unit entering from an external platform of the high-temperature gas cooled reactor, a main steam outlet end concrete protective shell and a maintenance hole (4-6) for simulating the main steam outlet end pipe box and the pipe plate unit entering from the external platform of the high-temperature gas cooled reactor, a water inlet end heating device (4-4) for simulating real environment temperature to preheat the water inlet end pipe box and the pipe plate unit, and a main steam outlet end heating device (4-7) for preheating the main steam outlet end pipe box and the pipe plate unit; the assessment management unit (5) is used for monitoring and managing the assessment process, and comprises a software unit for flow control and a positioning and video unit for process monitoring, and the software unit and the positioning and video unit are matched to complete the process management and detection assessment of the assessment process.
2. The device for the technical examination of the pipe plugging of the steam generator of the high temperature gas cooled reactor according to claim 1, wherein: the material of the main steam outlet end tube plate (2-2) is Inconly 800H nickel-based high-temperature alloy, and the material of the water inlet end tube plate (1-2) is 21/4The Cr1Mo heat-resistant steel is consistent with the material of a steam generator of a real high-temperature gas cooled reactor.
3. The device for the technical examination of the pipe plugging of the steam generator of the high temperature gas cooled reactor according to claim 1, wherein: the water inlet end tube box and the tube plate unit (1) and the main steam outlet end tube box and the tube plate unit (2) are in a vertical geometric relationship and are fixed through a lower seal head (4-1) of a pressure vessel of a steam generator and a side wall surface (4-5) of the pressure vessel of the steam generator, the plane of the water inlet end tube plate (1-2) is parallel to the horizontal plane, and the plane (2-2) of the main steam outlet end tube plate is vertical to the horizontal plane.
4. The device for the technical examination of the pipe plugging of the steam generator of the high temperature gas cooled reactor according to claim 1, wherein: the water inlet end heating device (4-4) and the main steam outlet end heating device (4-7) adopt an electric heating mode.
5. The device for the technical examination of the pipe plugging of the steam generator of the high temperature gas cooled reactor according to claim 1, wherein: the outer facade of the device is transparent organic glass, so that the visibility of the device is enhanced.
6. The method for testing the device for the technical examination of the pipe blockage of the steam generator of the high temperature gas cooled reactor according to any one of claims 1 to 5, wherein the method comprises the following steps: the following test procedures were followed: firstly, starting an examination management unit (5), automatically opening a water inlet end heating device (4-4) and a main steam outlet end heating device (4-7) by the examination management unit (5), and sending an examination starting instruction by a software unit in the examination management unit (5) after the examination management unit (5) reaches the service temperature; secondly, after confirming that an object to be examined, namely the automatic welding pipe plugging device, is prepared completely, clicking to start an examination process, starting timing by a software unit in an examination management unit, enabling the automatic welding pipe plugging device to enter working faces of a water inlet end pipe box and a pipe plate unit (1) through a peripheral environment unit (4), positioning positions to be blocked which are given numbers and are respectively positioned at the center of a water inlet end pipe plate (1-2), four edges of a front pipe plate, a rear pipe plate, a left pipe plate and a right pipe plate, and not less than five positions to be blocked in total, and welding pipe plugging by the automatic welding pipe plugging device to be examined; after the automatic welding pipe plugging equipment is positioned, welded and welded, video and image recording is carried out through a high-resolution camera in a positioning and video unit in the examination management unit (5); after the process is finished, the automatic welding pipe plugging equipment returns to the working surfaces of the water inlet end pipe box and the pipe plate unit (1) through the surrounding environment unit (4), and the suitability of the automatic welding pipe plugging equipment to be examined at the water inlet end is examined; after the software unit in the examination management unit (5) confirms that the welding of the water inlet end and the pipe plugging are finished, the process of welding and pipe plugging of the main steam outlet end pipe box and the pipe plate unit (2) is started for examination; the automatic welding pipe plugging device enters the working surface of the main steam outlet end pipe box and the pipe plate unit (2) through the surrounding environment unit (4), positions a pipe to be plugged corresponding to the water inlet end and performs welding pipe plugging operation, and after the automatic welding pipe plugging device is positioned, welded and welded, video and image recording is performed through a high-resolution camera in a positioning and video unit in the examination management unit (5) to complete the suitability examination of the welding pipe plugging of the main steam outlet end pipe box and the pipe plate unit (2); and finally, cutting and sampling the water inlet end tube plate (1-2) and the main steam outlet end tube plate (2-2), and then evaluating the quality of the joint of the automatic welding pipe plugging equipment.
7. The test method of claim 6, wherein: the specific process for evaluating the quality of the joint is as follows: the passability of the automatic welding pipe plugging equipment is judged based on video information: whether the in-out process collides with peripheral devices or not and whether the pause exceeds 10s due to the existence or nonexistence; the timeliness of completing the task within the specified time, namely whether the time for the automatic welding pipe plugging equipment to reach the working surface, position and weld exceeds the specified time or not; the accessibility, the positioning accuracy and the repeatability of a welding head after the welding device reaches a working face are that whether the welding head reaches one position of the center of the tube plate and the positions of circumferential welds of four positions to be blocked, front, back, left and right, is judged based on a high-resolution image, whether the transverse difference between the actual position and the target position is greater than a specified value or not, and whether the three-time repeated positioning difference of the same position to be blocked is greater than the specified value or not is judged.
8. The test method of claim 6, wherein: the project and the test method for evaluating the joint quality of the automatic welding pipe plugging equipment comprise the following steps: crack detection-penetrant inspection; weld penetration-metallographic detection; mechanical properties-tensile test.
CN202210299141.2A 2022-03-25 2022-03-25 Device and method for high-temperature gas cooled reactor steam generator pipe plugging technical examination Pending CN114519945A (en)

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Application Number Priority Date Filing Date Title
CN202210299141.2A CN114519945A (en) 2022-03-25 2022-03-25 Device and method for high-temperature gas cooled reactor steam generator pipe plugging technical examination

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Application Number Priority Date Filing Date Title
CN202210299141.2A CN114519945A (en) 2022-03-25 2022-03-25 Device and method for high-temperature gas cooled reactor steam generator pipe plugging technical examination

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CN114519945A true CN114519945A (en) 2022-05-20

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