CN209822291U - Detection tool for surfacing layer of lower end socket of reactor pressure vessel - Google Patents
Detection tool for surfacing layer of lower end socket of reactor pressure vessel Download PDFInfo
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- CN209822291U CN209822291U CN201822151666.3U CN201822151666U CN209822291U CN 209822291 U CN209822291 U CN 209822291U CN 201822151666 U CN201822151666 U CN 201822151666U CN 209822291 U CN209822291 U CN 209822291U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model discloses mainly used nuclear power station overhauls the field, concretely relates to reactor pressure vessel low head surfacing layer detects instrument and method. The worn areas of the reactor pressure vessel are prone to hazardous defects due to stress concentration, which reduces the useful life of the vessel and requires defect detection of these worn areas. The utility model discloses a: a linear telescopic device and a tail end monitoring device. The linear telescopic device is connected with the tail end monitoring device, and the tail end monitoring device is integrally positioned below the linear telescopic device. The utility model discloses can effectually realize reactor pressure vessel wear area defect detection, improve work efficiency, reduce the running cost.
Description
Technical Field
The utility model discloses mainly used nuclear power station overhauls the field, concretely relates to reactor pressure vessel low head surfacing layer detects instrument.
Background
The reactor pressure vessel is a key component of a nuclear reactor and belongs to a nuclear primary component. In the operation process of a nuclear power station, a reactor pressure vessel is mainly loaded with a reactor core and a high-temperature and high-pressure coolant, and the structural integrity of the reactor pressure vessel is required to be guaranteed under various working conditions. Before the reactor pressure vessel is in service, the reactor pressure vessel is installed and debugged or in the process of in service operation, due to the influence of improper operation or high-temperature, high-pressure and high-disturbance water flow impact, other internal components fail to cause impact abrasion on the inner wall of the vessel, so that concave regions with different sizes are formed. The inner wall of the container is extruded and abraded due to the falling of inner objects in a certain domestic power station.
The inner surface of the reactor pressure vessel is provided with a stainless steel surfacing layer of 4-12 mm, so that the influence of high irradiation of the reactor core on the vessel cylinder is reduced, and the service life of the vessel is prolonged. Due to the extrusion wear of the surface, deeper pits are formed, resulting in a reduced thickness or disappearance of the weld overlay. Under the operating conditions of high temperature, high pressure and high radiation, the worn areas are easy to generate hazardous defects due to stress concentration, so that the service life of the container is shortened. It is therefore particularly necessary to detect defects in these wear zones.
The equipment adopted for detecting the defects of the wear zone of the lower end socket of the reactor pressure vessel is as follows: on the basis of the existing six-joint robot, a special movement track for lower head inspection is designed and compiled, and a special tool for lower head inspection is designed.
The method for detecting the defects of the wear area of the lower end socket of the reactor pressure vessel comprises the following steps: the full-depth coverage of the defects of the wear area is realized within the depth range of 0-30mm of the inner wall of the reactor pressure vessel. The ultrasonic and eddy current detection technology can realize the defect detection and quantification in the depth range of 0-30mm, and the underwater three-dimensional laser scanning can realize the measurement and quantification of the related dimension of the surface opening defect.
Disclosure of Invention
Firstly, the purpose is as follows:
the utility model aims at providing a can carry out detection instrument and detection method that detects to nuclear power station reactor pressure vessel lower head inner wall wearing and tearing district defect.
The technical scheme is as follows:
a reactor pressure vessel low head surfacing layer detects instrument includes: a linear telescopic device and a tail end monitoring device. The terminal monitoring device includes: the camera, the switching base, the connecting plate and the switching plate; the whole adapter base is U-shaped, and the bottom and two side surfaces of the adapter base are hollow straight plates; the camera is embedded in the switching base and is connected with the bottom of the connecting base through a screw; the connecting plate is in an inverted U shape, the bottom and two side surfaces of the connecting plate are straight plates, the left side surface and the right side surface of the connecting plate are respectively connected with the side surfaces of the switching base through bolts, and the bottom surface of the connecting plate is connected with the switching plate; the connecting plate and the adapter base are arranged up and down mutually, and the camera is limited in the adapter base; the linear expansion device comprises: the shaft end fixing block and the shaft fixing block are cuboids, are consistent in size and shape, and are provided with three through holes from left to right; both ends of the shaft end fixing block and the shaft fixing block are fixedly connected with the bottom surface of the switching base through bolts, the linear telescopic device is connected with the terminal monitoring device, and the terminal monitoring device is integrally located below the linear telescopic device.
The linear expansion device further comprises: the device comprises a stretching cylinder, a sliding shaft, a transfer block and a shaft sleeve; the sliding shafts are cylindrical straight rods, are two in number, are arranged in parallel and penetrate through holes at the two ends of the shaft end fixing block and the shaft fixing block; the shaft end fixing block and the middle through hole of the shaft fixing block are both threaded through holes, and the stretching cylinder penetrates through the middle threaded through hole and is parallel to the sliding rod; the shaft end fixing block is fixedly installed at the rightmost end of the linear expansion device, and the switching block is fixedly installed at the leftmost end of the linear expansion device.
The number of the shaft sleeves is three, and the linear bearings correspond to the shaft sleeves one by one and are all loaded in the shaft sleeves; two of the shaft sleeves are arranged in parallel, and the sliding shaft passes through the two shaft sleeves; the other shaft sleeve is welded with the adapter block, and a linear shaft penetrates through the other shaft sleeve.
The switching block is in a convex shape as a whole, threaded through holes are formed in two ends of the lower half part of the switching block, and the sliding shaft penetrates through the through holes and is fixedly connected with the switching block through bolts; the shaft sleeve penetrates through the middle part of the transfer block; the bearing baffle is closely installed in the left side of switching piece, and the axle sleeve is laminated with the bearing baffle mutually.
The two parallel shaft sleeves are connected with the constant force spring fixing seat through bolts to form the axial baffle of the linear bearing.
The constant force spring fixing seat is connected with the air cylinder fixing seat through a bolt; the cylinder fixing seat is connected with the stretching cylinder through the cylinder with threads.
The linear shaft penetrates through the bearing baffle plate and is movably connected with the lower end enclosure inspection tray; and an inspection probe is carried on the lower end enclosure inspection tray.
Thirdly, the effect is as follows:
3.1 end monitoring techniques
When the lower seal head of the reactor pressure vessel is inspected, a monitoring video signal transmitted back by the terminal ZUMA camera is processed by the video control system, the underwater state of the lower seal head of the reactor pressure vessel can be displayed on the monitor in real time, and the collision risk during the detection of the lower seal head is greatly reduced. The ZUMA camera is connected with the switching base through a screw, and the switching base is connected with the connecting plate through a screw. The bolt is screwed up and then not only is good connection realized, but also the overall strength of the detection tool for the surfacing layer of the lower end enclosure of the reactor pressure vessel is enhanced, and the reciprocating coincidence of ultrasonic waves and eddy current signals during detection is ensured.
3.2 Linear expansion and contraction technique
When the stretching cylinder stretches, the shaft sleeve and the linear shaft fixed on the shaft sleeve are driven to move, so that the lower end socket inspection tray is controlled to be attached to or detached from the lower end socket inspection tray. When the arm is folded to the arm action, but sharp telescopic machanism furthest reduces terminal distance, greatly reduces arm collision risk and rolls over the arm degree of difficulty. Meanwhile, in the scanning process, the telescopic mechanism has a buffering effect, and the probe is well attached to a scanned object in the scanning process.
3.3 other technical effects
The most length of the straight-line shaft cantilever is changed into two-point support in a mode of scanning the compression amount, only a few allowance exists in a cantilever mode, the design enhances the rigidity of the telescopic part on the basis of not influencing the straight-line expansion, and the reciprocating coincidence of ultrasonic waves and eddy current signals during detection is ensured.
All joints of the mechanical arm are arranged on the penetrating piece, the reactor pressure vessel lower head detection tool is arranged in a narrow and flat shape, the maximum width of the whole detection tool at the position below the penetrating piece is the maximum width of the probe tray, and the widths of other positions are smaller than the width of the position, so that the detection collision risk is reduced, the operation difficulty of an operator is greatly reduced, the scanning area range is kept as large as possible, and the inaccessible range of the detection position is ensured to be minimum.
3.4 detection method
By adopting a narrow-pulse broadband probe with the frequency of 3-5 MHz, the resolution and the signal-to-noise ratio of ultrasonic signals are greatly improved; the water immersion probe is adopted, so that not only can the defects of a wear area be detected, but also the coupling condition and the profile measurement of the wear area can be judged through water/steel interface waves; the elastic point type eddy current probe is adopted, so that the probe can be ensured to be always attached to the surface in the scanning of a wear area to the greatest extent; the designed reference test block can effectively set the detection sensitivity; the probe clamping device can be used for simultaneously mounting ultrasonic probes with different specifications and different directions and a vortex elastic point type probe, so that multidirectional inspection of a wear area is realized;
drawings
FIG. 1 left side view of the inspection tool
FIG. 2 front view of a detection tool
FIG. 3 eddy current probe structure
FIG. 4 quantitative defect height diagram
In the figure: 1. the camera comprises a camera, 2. a switching base, 3. a connecting plate, 4. a switching plate, 5. a shaft end fixing block, 6. a shaft fixing block, 7. a sliding shaft, 8. a cylinder fixing seat, 9. a constant force spring fixing seat, 10. a linear bearing, 11. a shaft sleeve, 12. a linear shaft, 13. a lower end socket inspection tray, 14. a bearing baffle, 15. a switching block and 16. a stretching cylinder.
Detailed Description
The following detailed description of the patent refers to the accompanying drawings and specific embodiments:
the method mainly comprises the following technologies:
1. end monitoring techniques
As shown in fig. 1, the tip monitor device includes: connecting block, camera 1, switching base 2. The distance between two rows of penetrating pieces in the surfacing layer area of the lower end enclosure of the reactor pressure vessel is 200.3mm, the vertical heights are not completely consistent, the penetrating pieces are influenced by J-shaped welding seams, and the detection range is small. The detection environment is complex and the light is weak. Other positions of pressure vessel rely on the control of center box both sides of robot or stock camera control to monitor when detecting, and these two kinds of monitoring methods are all far away and are difficult to guarantee long-time real time monitoring, and very big collision risk when can causing the low head to detect like this. In view of the above situation, a monitoring camera is installed at the tail end of the reactor pressure vessel lower head detection tool, and the distance between the central line of the scanning tool determined by virtual simulation scanning and the central line of the No. 6 joint of the mechanical arm is combined, so that a mature ZUMA camera 1 is adopted, not only can the good implementation monitoring of the part be realized, but also the cost can be greatly saved.
ZUMA camera 1 passes through the screw and links to each other with switching base 2, and switching base 2 passes through the screw and links to each other with connecting plate 3. Adapter base 2 and connecting plate 3 all design into C type structure, and adapter base 2 and camera length dimension and 3 width dimensions of connecting plate form the cooperation relation, not only can realize good connection after the bolt is screwed up, can also strengthen reactor pressure vessel lower head surfacing layer detection tool's bulk strength.
2. Linear expansion technology
As shown in fig. 2, the linear telescopic mechanism includes a shaft end fixing block 5, a shaft fixing block 6, a stretching cylinder 16, a sliding shaft 7, an adapter block 15, and a shaft sleeve 11.
The shaft end fixing block 5, the shaft fixing block 6, the switching block 15 and the sliding shaft 7 form a basic framework of the whole linear telescopic motion. The linear bearing is loaded in the shaft sleeve 11, and the constant force spring fixing seat 9 is connected with the shaft sleeve 11 through a bolt to form an axial baffle of the linear bearing. The cylinder fixing seat 8 is connected with the constant force spring fixing seat 9 through a bolt, and the cylinder fixing seat 8 is connected with the stretching cylinder 16 through a cylinder with threads.
3. Expansion piece rigidity enhancement technology
On the basis of linear extension, the linear shaft 12 is long in cantilever, in order to solve the problem of poor rigidity of the cantilever shaft, the adapter block 15 is designed into a special-shaped piece, the adapter block is matched with the sliding shaft 7, and meanwhile, the sliding bearing of the linear shaft 12 is installed on the adapter block, so that most of the length of the cantilever of the linear shaft 12 is changed into two-point support in a mode of scanning the compression amount, only a few allowance exists in a cantilever mode, and the design enhances the rigidity of the telescopic piece on the basis of not influencing the linear extension.
4. Obstacle avoidance design technology
The distance between two rows of penetrating pieces in the lower head area of the 300Mev nuclear reactor pressure vessel is 200.3mm, the heights of the penetrating pieces are not completely consistent, and the maximum height of the penetrating pieces in the vertical direction is about 450 mm. Due to the limitation of the penetration piece and the scanning range, all joints of the mechanical arm are arranged on the penetration piece, the reactor pressure vessel lower end socket detection tool is arranged in a narrow and flat shape, the maximum width of the whole detection tool below the penetration piece is the maximum width of the probe tray, and the widths of other positions are smaller than the width of the probe tray, so that the detection collision risk is reduced, and the scanning area range is kept as large as possible.
2.2 technical scheme of detection method
Aiming at the crack defects, in order to improve the detectable rate of the defects, the full-depth coverage is realized by adopting ultrasonic inspection and eddy current inspection technologies;
in order to improve the detection efficiency, ultrasonic and eddy current inspection is completed at one time, a special probe clamping device is designed, a plurality of ultrasonic probes and eddy current probes can be installed at the same time, and defect inspection is implemented at one time;
in order to reduce the influence of surface concave-convex on ultrasonic coupling and sound beam propagation, a high-frequency (3-5 MHz) narrow-pulse broadband water immersion ultrasonic probe is adopted;
by setting the incident angle of the ultrasonic sound beam of the underwater probe, longitudinal waves of 45 degrees or 70 degrees are generated in the steel, so that the defects are detected and the height is measured;
the eddy current detection adopts an elastic point type probe, so that the probe can automatically attach to the surface along the outline of a wear area, and the lift-off effect is reduced to the maximum extent;
designing ultrasonic reference test blocks of the transverse through holes with different depths, which can cover the inspection depth, according to the inspection specification, and setting the water immersion ultrasonic detection sensitivity;
designing eddy current reference test blocks of grooves with different depths on the surface according to detection specifications for setting eddy current detection sensitivity;
the method is characterized in that the profile of a surface opening wear area is directly scanned by adopting an underwater three-dimensional laser scanning technology to form profile data, and the size of the wear area is accurately measured under the cooperation of corresponding software.
Claims (7)
1. A reactor pressure vessel low head surfacing layer detects instrument includes: linear telescoping device, its characterized in that: the terminal monitoring device includes: the camera comprises a camera (1), a switching base (2), a connecting plate (3) and a switching plate (4); the whole adapter base (2) is U-shaped, and the bottom and two side surfaces are hollow straight plates; the camera (1) is embedded in the switching base (2) and is connected with the bottom of the switching base (2) through a screw; the connecting plate (3) is in an inverted U shape, the bottom and two side surfaces are straight plates, the left side surface and the right side surface of the connecting plate are respectively connected with the side surfaces of the switching base (2) through bolts, and the bottom surface of the connecting plate is connected with the switching plate (4); the connecting plate (3) and the switching base (2) are mutually up and down, and the camera (1) is limited in the switching base (2); the linear expansion device comprises: the shaft end fixing block (5) and the shaft fixing block (6) are cuboids, are consistent in size and shape, and are provided with three through holes from left to right; both ends of the shaft end fixing block (5) and the shaft fixing block (6) are fixedly connected with the bottom surface of the switching base (2) through bolts, the linear telescopic device is connected with the terminal monitoring device, and the terminal monitoring device is integrally located below the linear telescopic device.
2. The tool for detecting the weld overlay of the lower head of the reactor pressure vessel as claimed in claim 1, wherein: the linear expansion device further comprises: a stretching cylinder (16), a sliding shaft (7), a transfer block (15) and a shaft sleeve (11); the sliding shafts (7) are cylindrical straight rods, are two in total and are arranged in parallel, and penetrate through holes at two ends of the shaft end fixing block (5) and the shaft fixing block (6); the middle through holes of the shaft end fixing block (5) and the shaft fixing block (6) are threaded through holes, and the stretching cylinder (16) penetrates through the middle threaded through holes and is parallel to the sliding shaft (7); the shaft end fixing block (5) is fixedly installed at the rightmost end of the linear expansion device, and the adapter block (15) is fixedly installed at the leftmost end of the linear expansion device.
3. The tool for detecting the weld overlay of the lower head of the reactor pressure vessel as claimed in claim 2, wherein: the number of the shaft sleeves (11) is three, and the linear bearings (10) correspond to the shaft sleeves (11) one by one and are all loaded in the shaft sleeves (11); two of the shaft sleeves (11) are arranged in parallel, and the sliding shaft (7) passes through the shaft sleeves; the other shaft sleeve (11) is welded with the adapter block (15), and the linear shaft (12) penetrates through the other shaft sleeve.
4. The tool for detecting the weld overlay of the lower head of the reactor pressure vessel as claimed in claim 2, wherein: the adapter block (15) is in a convex shape as a whole, threaded through holes are formed in the two ends of the lower half part of the adapter block, and the sliding shaft (7) penetrates through the through holes and is fixedly connected with the adapter block (15) through bolts; the shaft sleeve (11) penetrates through the middle part of the transfer block (15); the bearing baffle (14) is tightly arranged at the left side of the transfer block (15), and the shaft sleeve (11) is attached to the bearing baffle (14).
5. The tool for detecting the weld overlay of the lower head of the reactor pressure vessel as claimed in claim 3, wherein: two parallel shaft sleeves (11) are connected with the constant force spring fixing seat (9) through bolts to form a linear bearing axial baffle.
6. The tool for detecting the weld overlay of the lower head of the reactor pressure vessel as claimed in claim 5, wherein: the constant force spring fixing seat (9) is connected with the air cylinder fixing seat (8) through a bolt; the cylinder fixing seat (8) and the stretching cylinder (16) are connected through a cylinder with threads.
7. The tool for detecting the weld overlay of the lower head of the reactor pressure vessel as claimed in claim 3, wherein: the linear shaft (12) penetrates through the bearing baffle (14) and is movably connected with the lower end enclosure inspection tray (13); an inspection probe is carried on the lower end enclosure inspection tray (13).
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201822151666.3U CN209822291U (en) | 2018-12-21 | 2018-12-21 | Detection tool for surfacing layer of lower end socket of reactor pressure vessel |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201822151666.3U CN209822291U (en) | 2018-12-21 | 2018-12-21 | Detection tool for surfacing layer of lower end socket of reactor pressure vessel |
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| CN209822291U true CN209822291U (en) | 2019-12-20 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111354487A (en) * | 2018-12-21 | 2020-06-30 | 核动力运行研究所 | Tool and method for detecting surfacing layer of lower end socket of reactor pressure vessel |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111354487A (en) * | 2018-12-21 | 2020-06-30 | 核动力运行研究所 | Tool and method for detecting surfacing layer of lower end socket of reactor pressure vessel |
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