A reactor structure deformation detection device
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2026-05-15
- Publication Date
- 2026-08-11
AI Technical Summary
目前国内外尚没有在运行反应堆结构压力容器贯穿件和堆内构件仪表套管的配合状态变化检测技术
本发明通过径向支承块位置模拟规模拟径向支承块在压力容器下端的真实位置,径向支承块位置模拟规与支承板刚性连接,在支承板上贯穿件真实位置处安装拓模套筒,拓模套筒内部装有能通过拓模操作记录仪表套管下端位置的可塑性物质,最终通过三维激光扫描提取堆内构件仪表套管组件下端在拓模套筒内部的拓痕与其对应的贯穿件相对位置信息,最终实现压力容器贯穿件和堆内构件仪表套管的配合状态变化检测。
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Figure CN122544665A_ABST
Abstract
Description
Technical Field
[0001] This invention belongs to the field of reactor structure technology, and specifically relates to a reactor structure deformation detection device. Background Technology
[0002] Reactor structures operate in extremely harsh environments. Under the coupled effects of high temperature, high pressure, strong radiation, transient temperature and pressure conditions, and flow-induced vibrations, reactor structures (including pressure vessels and in-core components) will undergo a certain degree of deformation. The fit between pressure vessel penetrations and instrumentation sleeves in in-core components will change to some extent. Detecting these changes in fit between pressure vessel penetrations and instrumentation sleeves in in-core components is of great practical significance for assessing the actual condition of the reactor structure and for its maintenance and replacement. Currently, there are no technologies available domestically or internationally for detecting changes in the fit between pressure vessel penetrations and instrumentation sleeves in operating reactor structures. Summary of the Invention
[0003] The purpose of this invention is to provide a reactor structure deformation detection device, which is suitable for checking the fit between the reactor pressure vessel penetration and the instrument sleeve of the in-core components after the reactor structure is put into operation.
[0004] To achieve the above objectives, the technical solution adopted by the present invention is as follows: A reactor structure deformation detection device: The positional relationship between the through-piece and the radial support block on the bottom end of the pressure vessel is realized by a pressure vessel bottom end simulation gauge. The bottom end simulation gauge includes a support plate, a radial support block position simulation gauge, and a mold sleeve. The mold sleeve is filled with sludge. The radial support block position simulation gauge is connected to the support plate. The mold sleeve is connected to the support plate. The bottom end simulation gauge is supported in the groove of the support ring and is axially limited by a pressure plate and appropriately tightened by bolts on the pressure plate. There is a gap between the lower surface of the pressure plate and the upper surface of the support plate. There is a lateral gap between the radial support block position simulation gauge and the pressure plate. There is a lateral gap between the support plate and the support ring.
[0005] The radial support block position simulation gauge is connected to the support plate via bolts and locating pins; the mold sleeve is connected to the support plate via bolts.
[0006] The radial support block position simulation gauge and the groove of the radial support key are used to realistically simulate the geometric position of the groove on the radial support block during reactor construction.
[0007] The lower end cap simulation gauge is hoisted by a lifting column, and the lifting screw-in part is connected to the lifting column by a thread.
[0008] The position of the mold sleeve accurately simulates the position of the through-piece during reactor construction.
[0009] The lower head simulation gauge is supported on the upper surface of the groove of the support ring and can move and rotate to a certain extent relative to the support ring, which is beneficial for the lower internal components to be molded on the lower head simulation gauge.
[0010] The upper and lower surfaces of the contact areas between the support plate and the support ring and pressure plate are coated with a special lubricant for in-core components.
[0011] The relative positions of the simulation gauge and the pressure plate of the lower end cap connected to the support cylinder are finely adjusted by adjusting the screws.
[0012] The lifting teeth for screwing in components have 3, 6, or 9 teeth.
[0013] Transport the testing device into the nuclear island plant platform; adjust the levelness of the testing device to ≤1 / 4000; adapt the lifting screw-in parts of the in-core components lifting tool and the lifting column, and adjust the lifting screw-in parts of the lifting column to match the lifting rod of the lifting tool. After adjustment, spot weld the lifting screw-in parts to the top of the lifting column; fine-tune the position of the support plate to ensure that the radial support block position simulates the uniform gap between the base side and the pressure plate; moderately tighten the bolts to ensure that the support plate will not slide relative to the support ring during hoisting; use the in-core components lifting tool to hoist the testing device as a whole into the pressure vessel and support it on the lifting basket support step of the pressure vessel; remove the in-core components lifting tool; under the supervision of underwater television, slowly hoist the lower in-core components for insertion; strictly control the insertion of the lower in-core components during the descent of the in-core components. The depth of the inspection is determined to ensure sufficient indentation to reflect the lower end position of the instrument sleeve, and to prevent rigid contact between the lower internal components and the inspection device. The lower internal components are then removed. The inspection device is lifted out using an internal component lifting tool. Residual water inside the mold sleeve is removed using a suction tool. A 3D laser scan of the inspection device is performed to complete the overall scanning and imaging of the instrument sleeve indentation, mold sleeve support rod, and radial support block position simulation gauge inside the mold sleeve. Using the 3D laser scanning software, the position information of the center of the lower indentation of the instrument sleeve relative to the centerline of the top groove of the radial support block position simulation gauge, and the position information of the center of the lower indentation of the instrument sleeve relative to the center of the corresponding mold sleeve support rod are extracted. The lower end of the instrument sleeve is cleaned with high-pressure water. The inspection is then complete.
[0014] The beneficial effects achieved by this invention are as follows: This invention simulates the actual position of a radial support block at the lower end of a pressure vessel by simulating the position of the radial support block. The radial support block position simulation gauge is rigidly connected to the support plate. A mold-forming sleeve is installed at the actual position of the through-piece on the support plate. The mold-forming sleeve contains a plastic material that can record the position of the lower end of the instrument sleeve through mold-forming operations. Finally, the relative position information of the mold-forming marks at the lower end of the in-core component instrument sleeve assembly inside the mold-forming sleeve and the corresponding through-piece is extracted by three-dimensional laser scanning. This ultimately realizes the detection of changes in the fit between the pressure vessel through-piece and the in-core component instrument sleeve. Attached Figure Description
[0015] Figure 1 This is a schematic diagram of a reactor structure deformation detection device. Figure 2 This is a sectional view of BB; Figure 3 This is a CC section view; Figure 4 A schematic diagram of the mold sleeve; Figure 5 This is a schematic diagram of a hanging column; Figure 6 This is a schematic diagram simulating the position of the radial support block. Detailed Implementation
[0016] The present invention will now be described in detail with reference to the accompanying drawings and specific embodiments.
[0017] The overall fit between the reactor in-core instrumentation sleeve and the pressure vessel bottom head penetration is determined by the fit between the radial support key and the radial support block (including the U-shaped insert). The positional relationship between the reactor pressure vessel bottom head penetration and the radial support block is fixed, as is the positional relationship between the in-core instrumentation sleeve and the radial support key. Therefore, the technical solution first involves reproducing the positional relationship between the penetration and the radial support block on the pressure vessel bottom head. This positional relationship is achieved using a pressure vessel bottom head simulation gauge, see [link to relevant documentation]. Figure 1 .
[0018] The lower head simulation gauge consists of a support plate 4, a radial support block position simulation gauge 1, and a mold sleeve 6. The mold sleeve is filled with sludge 10. (See...) Figure 4The radial support block position simulation gauge 1 is connected to the support plate 4 via bolts and locating pins. The groove of the radial support block position simulation gauge 1 and the radial support key accurately simulates the geometric position of the groove on the radial support block during reactor construction. The mold-forming sleeve 6 is connected to the support plate 4 via bolts, and the position of each mold-forming sleeve 6 accurately simulates the position of the through-piece during reactor construction. The lower head simulation gauge is supported in the groove of the support ring 3 and is axially limited by the pressure plate 2 and appropriately tightened by the bolts 8 on the pressure plate 2. There is a gap between the lower surface of the pressure plate 2 and the upper surface of the support plate 4. There is a lateral gap between the radial support block position simulation gauge 1 and the pressure plate 2. There is a lateral gap between the support plate 4 and the support ring 3. The support ring 3 is connected to the support cylinder 5 and is supported and fixed by the support cylinder 5. The lower head simulation gauge is not laterally fixed. The lower head simulation gauge is supported on the upper surface of the groove of the support ring 3 and can move and rotate to a certain extent relative to the support ring 3, which is beneficial for the molding of the lower in-reactor components on the lower head simulation gauge. The upper and lower surfaces of the contact points between the support plate 4 and the support ring 3 and pressure plate 2 are coated with a special lubricant for in-core components. The relative positional relationship between the lower head simulation gauge and the pressure plate 2 can be finely adjusted by adjusting screw 9. The lower head simulation gauge is hoisted by the lifting column 7.
[0019] The structure of the reactor structural deformation detection device is shown in the figure. Figure 1 The core technology for achieving its detection function is as follows: A radial support block position simulation is used to model the actual position of the radial support block at the lower end of the pressure vessel. The radial support block position simulation gauge is rigidly connected to the support plate. A mold-forming sleeve is installed at the actual position of the through-piece on the support plate. The mold-forming sleeve contains a plastic material that can record the position of the lower end of the instrument sleeve through mold-forming operations. Finally, three-dimensional laser scanning is used to extract the imprint of the lower end of the in-core component instrument sleeve assembly inside the mold-forming sleeve and its relative position information with the corresponding through-piece, thus completing the detection of changes in the fit between the pressure vessel through-piece and the in-core component instrument sleeve. The structural form of the mold-forming sleeve is shown in [reference needed]. Figure 4 The mold sleeve is filled with a plastic material called 10 clay; the structural form of the hanging column is shown in [reference needed]. Figure 5 The lifting and screwing-in component 11 is used for hoisting. The structure of the lifting and screwing-in component 11 is shown in [reference needed]. Figure 5 The lifting screw-in component 11 has 3, 6, or 9 teeth; the lifting screw-in component 11 is connected to the lifting column 7 by a thread; the radial support block position simulation structure is shown in the figure. Figure 6 The simulation gauge uses an eccentric setting to simulate the position of the radial support block.
[0020] The reactor structure deformation detection device can detect both the positional change of the lower end of the instrument sleeve relative to the radial support key and the positional relationship of the lower end of the instrument sleeve relative to the top of the through-hole. The operating procedure for using the reactor structure deformation detection device is as follows: Transport the device into the nuclear island building +20-meter platform; adjust the device's levelness to ≤1 / 4000; adapt the in-core component lifting equipment to the device's lifting column lifting screw. Adjust the lifting screw of the device's lifting column to match the lifting rod of the lifting equipment (one tooth must face radially outward), and after adjustment, spot weld the lifting screw to the top of the lifting column; use adjusting screw 9 to fine-tune the position of the support plate, ensuring that the radial support block position simulates the uniform gap between the base side and the pressure plate; moderately tighten bolt 8 to ensure that the support plate will not slide relative to the support ring during device hoisting, but will slide relative to the support ring under a horizontal thrust of 200N; use the in-core component lifting equipment to hoist the entire device into the pressure vessel and support it on the pressure vessel's lifting basket support steps; remove the in-core component lifting equipment; under the supervision of underwater television, slowly hoist the lower in-core components for insertion. During the descent of the in-core components, the insertion depth of the lower in-core components is strictly controlled to ensure that sufficient indentations are left inside the inspection sleeve to reflect the position of the lower end of the instrument sleeve, and to ensure that the lower in-core components do not make rigid contact with the device; the lower in-core components are hoisted away; the device is lifted out using an in-core component lifting tool; residual water inside the mold sleeve is removed using a suction tool; the device is subjected to three-dimensional laser scanning to complete the overall scanning imaging of the instrument sleeve indentations, mold sleeve support rods, and radial support block position simulation gauges inside the mold sleeve; using the three-dimensional laser scanning software, the position information of the center of the lower end indentation of the instrument sleeve relative to the centerline of the top groove of the radial support block position simulation gauge, and the position information of the center of the lower end indentation of the instrument sleeve relative to the center of the corresponding mold sleeve support rod are extracted; the lower end of the instrument sleeve is cleaned with high-pressure water; the inspection is completed.
Claims
1. A reactor structure deformation detection device, characterized in that: The positional relationship between the through-piece and the radial support block on the bottom head of the pressure vessel is achieved by a simulation gauge for the lower head of the pressure vessel. The simulation gauge includes a support plate, a radial support block position simulation gauge, and a mold sleeve. The mold sleeve is filled with sludge. The radial support block position simulation gauge is connected to the support plate, and the mold sleeve is also connected to the support plate. The lower head simulation gauge is supported in the groove of the support ring and is axially limited by the pressure plate and appropriately tightened by bolts on the pressure plate. There is a gap between the lower surface of the pressure plate and the upper surface of the support plate. There is a lateral gap between the radial support block position simulation gauge and the pressure plate, and a lateral gap between the support plate and the support ring.
2. The reactor structural deformation detection apparatus according to claim 1, characterized by: The radial support block position simulation gauge is connected to the support plate via bolts and locating pins; the mold sleeve is connected to the support plate via bolts.
3. The reactor structural deformation detection apparatus according to claim 1, characterized by: The radial support block position simulation gauge and the groove of the radial support key are used to realistically simulate the geometric position of the groove on the radial support block during reactor construction.
4. The reactor structural deformation detection apparatus according to claim 1, characterized by: The lower head simulation gauge is hoisted by a lifting column, and the lifting screw-in part is connected to the lifting column by a thread.
5. The reactor structural deformation detection apparatus according to claim 1, characterized by: The position of the mold sleeve accurately simulates the position of the through-piece during reactor construction.
6. The reactor structure deformation detection device according to claim 1, characterized in that: The lower head simulation gauge is supported on the upper surface of the groove of the support ring and can move and rotate to a certain extent relative to the support ring, which is beneficial for the lower internal components to be molded on the lower head simulation gauge.
7. The reactor structural deformation detection apparatus according to claim 1, characterized by: The upper and lower surfaces of the contact areas between the support plate and the support ring and pressure plate are coated with a special lubricant for in-core components.
8. The reactor structural deformation detection apparatus according to claim 1, characterized by: The relative positional relationship between the lower end cap simulation gauge and the pressure plate is finely adjusted using adjusting screws.
9. The reactor structural deformation detection apparatus according to claim 4, characterized by: The lifting teeth for screwing in components have 3, 6, or 9 teeth.
10. The reactor structural deformation detection apparatus according to claim 4, characterized by: Transport the testing device into the nuclear island plant platform; adjust the levelness of the testing device to ≤1 / 4000; adapt the lifting screw-in parts of the in-core components lifting tool and the lifting column, and adjust the lifting screw-in parts of the lifting column to match the lifting rod of the lifting tool. After adjustment, spot weld the lifting screw-in parts to the top of the lifting column; fine-tune the position of the support plate to ensure that the radial support block position simulates the uniform gap between the base side and the pressure plate; moderately tighten the bolts to ensure that the support plate will not slide relative to the support ring during hoisting; use the in-core components lifting tool to hoist the testing device as a whole into the pressure vessel and support it on the lifting basket support step of the pressure vessel; remove the in-core components lifting tool; under the supervision of underwater television, slowly hoist the lower in-core components for insertion; strictly control the insertion of the lower in-core components during the descent of the in-core components. The depth of the inspection is determined to ensure sufficient indentation to reflect the lower end position of the instrument sleeve, and to prevent rigid contact between the lower internal components and the inspection device. The lower internal components are then removed. The inspection device is lifted out using an internal component lifting tool. Residual water inside the mold sleeve is removed using a suction tool. A 3D laser scan of the inspection device is performed to complete the overall scanning and imaging of the instrument sleeve indentation, mold sleeve support rod, and radial support block position simulation gauge inside the mold sleeve. Using the 3D laser scanning software, the position information of the center of the lower indentation of the instrument sleeve relative to the centerline of the top groove of the radial support block position simulation gauge, and the position information of the center of the lower indentation of the instrument sleeve relative to the center of the corresponding mold sleeve support rod are extracted. The lower end of the instrument sleeve is cleaned with high-pressure water. The inspection is then complete.