Support platform and nuclear power plant reactor pressure vessel detection system

Abstract

The invention relates to the field of nuclear power plant detection, and discloses a support platform and a nuclear power plant reactor pressure vessel detection system. The support platform comprises a support, and the support comprises a main bearing column, a supporting leg installed on the outer side of the main bearing column, and an installation assembly and an auxiliary mechanism which are arranged on the outer sides of the main bearing column and the supporting leg; the auxiliary mechanism comprises a weight reduction cavity formed in the main bearing column and a reference block assembly embedded in the main bearing column, and the weight reduction cavity comprises a cavity, a drainage hole and an exhaust hole; the main bearing column body can be installed and fixed in the nuclear reactor pressure vessel by arranging the supporting feet, the weight and buoyancy borne by the main bearing column body can be reduced by arranging the weight reduction cavity, and therefore supporting force needing to be provided by a hydraulic rod is reduced, pressure borne by the inner surface of the pressure vessel and a surfacing layer is reduced, and the service life of the pressure vessel is prolonged. Therefore, the purpose of protecting the inner surface and the surfacing layer is achieved.

Description

Technical Field

[0001] The present invention relates to the field of nuclear power plant detection, in particular to a support platform and a nuclear power plant reactor pressure vessel detection system. Background Art

[0002] Reactor pressure vessels in nuclear power plants are exposed to high temperatures, high pressures, and strong radiation for a long time. Welds and weld overlays are prone to defects such as cracks and slag inclusions, which lead to corrosion and impurities, affecting medium quality and equipment safety. Containers are also prone to aging, so regular non-destructive testing and maintenance when necessary are required to ensure the safe operation of nuclear reactors and safe production in nuclear power plants.

[0003] During non-destructive testing, the testing equipment needs to be installed on a support platform, and then the support platform is installed inside the pressure vessel. However, the inner surface of the pressure vessel of the nuclear reactor pressure vessel should remain flat and smooth, without obvious unevenness and scratches, and the weld overlay layer should be uniform and dense, without defects such as cracks and pores.

[0004] The presence of scratches or other defects can significantly reduce the safety and reliability of nuclear reactor pressure vessels. Under the combined effects of corrosion (such as accelerated localized corrosion and increased risk of stress corrosion cracking) and irradiation (such as increased radiation loss), scratches can become crack initiation points, accelerating crack propagation and ultimately leading to vessel failure and leakage.

[0005] Therefore, when installing the support platform inside the pressure vessel, how to ensure that the support platform is installed stably without damaging the inner surface of the pressure vessel and the cladding layer becomes a difficulty.

[0006] In addition, the existing non-destructive testing system has not been managed in a standardized and integrated manner, resulting in complicated management and the inability to remotely control it. Inspectors need to work close to the reactor pressure vessel, exposing them to continuous radiation exposure and failing to implement the optimal ALARA principle for radiation protection. Summary of the Invention

[0007] Therefore, the technical problem to be solved by the present invention is: how to ensure that the support platform is installed stably without damaging the inner surface of the pressure vessel and the cladding layer.

[0008] The above technical problems are solved by the following technical solutions: The present invention proposes a support platform, which includes:

[0009] A bracket, the bracket comprising a main support column, a support leg mounted on the outside of the main support column, and a mounting assembly disposed on the outside of the main support column and the support leg;

[0010] The support legs are used to fix the main support column, and the mounting assembly is used to install the detection equipment;

[0011] An auxiliary mechanism, the auxiliary mechanism comprising a weight-reducing cavity provided inside the main support column, and a comparison test block assembly embedded inside the main support column;

[0012] The weight-reducing cavity includes a cavity, a drainage hole, and an exhaust hole;

[0013] The comparison test block assembly is used to calibrate and verify the sensitivity and parameters of the detection equipment, and the detection equipment installed by the installation assembly can perform non-destructive detection of defects in the pressure vessel.

[0014] In a preferred embodiment of the support platform of the present invention: the main support column includes a main support column body and a lifting groove provided at one end of the main support column body, and the lifting groove can be used to connect a crane to the main support column body.

[0015] In a preferred embodiment of the support platform of the present invention: the support leg comprises a hydraulic rod hingedly connected to the outside of the main support column body, and a pad foot fixedly connected to the output end of the hydraulic rod;

[0016] There are four support legs, with a 90° interval between two adjacent support legs. The support legs enable the main support column body to be installed and fixed inside the pressure vessel.

[0017] In a preferred embodiment of the support platform described in the present invention: the mounting assembly includes an underwater surveillance camera mounting point and a searchlight mounting point arranged on the outside of the hydraulic rod, and a robotic arm mounting ring fixedly connected to the other end of the main support column body. The mounting assembly can provide an installation position for the underwater surveillance camera, searchlight and robotic arm.

[0018] In a preferred embodiment of the bracket platform of the present invention: the cavity is opened inside the main supporting column body, the drainage hole is opened at one end of the main supporting column body close to the robot arm mounting ring, and the exhaust hole is opened at one end of the main supporting column body close to the lifting slot, and the cavity can reduce the weight of the bracket and the buoyancy it is subjected to.

[0019] In a preferred embodiment of the support platform described in the present invention: the comparison test block assembly includes an eddy current test comparison test block embedded in the main support column body, and an ultrasonic test comparison test block embedded in the main support column body. The eddy current test comparison test block and the ultrasonic test comparison test block can calibrate and verify the sensitivity and parameters of the eddy current and ultrasonic testing equipment, thereby making the test results more accurate.

[0020] The present invention also provides a nuclear power plant reactor pressure vessel detection system.

[0021] In a preferred embodiment of the nuclear power plant reactor pressure vessel detection system of the present invention: a nuclear power plant reactor pressure vessel detection system includes the support platform, and further includes:

[0022] Working units outside the nuclear reactor building, working units above the side of the nuclear reactor pressure vessel, and working units inside the nuclear reactor pressure vessel;

[0023] The working unit outside the nuclear reactor building is used for analyzing, storing and processing data; the working unit above the nuclear reactor pressure vessel side is used for controlling detection equipment; and the working unit inside the nuclear reactor pressure vessel is used for detecting data inside the pressure vessel;

[0024] The working unit outside the nuclear reactor building includes a first hub, and the working unit above the nuclear reactor pressure vessel side includes a second hub. The first hub and the second hub are connected through an optical fiber, and the working unit above the nuclear reactor pressure vessel side is electrically connected to the working unit inside the nuclear reactor pressure vessel. By setting the first hub and the second hub, workers can be prevented from being close to the nuclear reactor for a long time during work, thereby reducing the nuclear radiation hazards to the workers.

[0025] In a preferred embodiment of the nuclear power plant reactor pressure vessel detection system of the present invention, the nuclear reactor building external working unit includes a network switching system, a data storage system electrically connected to the network switching system, a data analysis system, a data processing system, a plan management system, a video monitor and a voice dialogue system, and a data acquisition working system;

[0026] The first hub is electrically connected to the network switching system, and the working unit outside the nuclear reactor building can analyze, process and store data.

[0027] In a preferred embodiment of the nuclear power plant reactor pressure vessel inspection system of the present invention: the upper working unit on the nuclear reactor pressure vessel side includes a control box electrically connected to the second hub, a pneumatic motion system, an eddy current ultrasonic system, an underwater television inspection system, and a video monitoring and voice system;

[0028] An ordinary surveillance camera is electrically connected to the video surveillance and voice system, and a UPS power supply is electrically connected to the control box. The UPS power supply can provide stable power for the control box.

[0029] In a preferred embodiment of the nuclear power plant reactor pressure vessel inspection system of the present invention: the internal working unit of the nuclear reactor pressure vessel includes a robotic arm electrically connected to the pneumatic motion system, a multifunctional probe electrically connected to the eddy current ultrasonic system, an underwater inspection camera electrically connected to the underwater television inspection system, and an underwater monitoring camera electrically connected to the video monitoring and voice system;

[0030] The robotic arm is adapted to be installed on the outside of the robotic arm mounting ring, the multifunctional probe and the underwater inspection camera are bolted to the outside of the robotic arm, the underwater monitoring camera is bolted to the underwater monitoring camera mounting point, the searchlight is bolted to the searchlight mounting point, the hydraulic rod is electrically connected to the control box, and the internal working unit of the nuclear reactor pressure vessel can detect the internal situation of the nuclear reactor pressure vessel.

[0031] The beneficial effects of the present invention are as follows: by providing support legs, the main support column body can be installed and fixed inside the nuclear reactor pressure vessel; by providing a weight-reducing cavity, the weight of the main support column body and the buoyancy it receives can be reduced, thereby reducing the supporting force required to be provided by the hydraulic rod, and further reducing the pressure on the inner surface of the pressure vessel and the weld overlay layer, thereby achieving the purpose of protecting the inner surface and the weld overlay layer. BRIEF DESCRIPTION OF THE DRAWINGS

[0032] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the following briefly introduces the drawings of the embodiments of the present invention. Obviously, the drawings described below only relate to some embodiments of the present invention and are not intended to limit the present invention. Among them:

[0033] Figure 1 A schematic top view of the support platform of the present invention is shown;

[0034] Figure 2 A schematic front view of the support platform of the present invention is shown;

[0035] Figure 3 A schematic diagram of the detection system of the present invention is shown. DETAILED DESCRIPTION

[0036] In order to enable those skilled in the art to better understand the present invention, the present invention is further described in detail below with reference to specific embodiments and the accompanying drawings.

[0037] The terms used in the present invention are those commonly used in the art in view of the functions of the present invention, but these terms may vary according to the intentions of those skilled in the art, precedents, or new technologies in the art. In addition, specific terms may be selected by the applicant, and in such cases, their detailed meanings will be described in the detailed description of the present invention. Therefore, the terms used in the specification should not be understood as simple names, but rather as the meanings of the terms and the overall description of the present invention.

[0038] Reference Figure 1 and Figure 2 , this embodiment provides a support platform, including,

[0039] The bracket 1 includes a main support column 11, a support leg 12 installed outside the main support column 11, and a mounting assembly 13 provided outside the main support column 11 and the support leg 12;

[0040] The support legs 12 are used to fix the main support column 11, and the mounting assembly 13 is used to install the testing equipment;

[0041] Auxiliary mechanism 2, the auxiliary mechanism 2 includes a weight-reducing cavity 21 provided inside the main support column 11, and a comparison test block assembly 22 embedded inside the main support column 11;

[0042] The weight-reducing chamber 21 includes a cavity 211 , a drainage hole 212 , and an exhaust hole 213 ;

[0043] The comparison test block assembly 22 is used to calibrate and verify the sensitivity and parameters of the detection equipment, and the weight reduction cavity 21 is used to reduce the weight of the bracket 1 and the buoyancy it is subjected to.

[0044] After the main support column 11 is hoisted into the pressure vessel and the main support column 11 is installed and fixed using the support legs 12, the installation of the support platform is completed.

[0045] A detection device is installed at the installation component 13, and the detection device can perform non-destructive detection on defects in the pressure vessel.

[0046] The weight-reducing cavity 21 can reduce the weight of the bracket 1 and the buoyancy it receives, so that the support legs 12 can be installed and fixed to the bracket 1 without much support force, thereby preventing the inner surface of the pressure vessel and the surfacing layer from being crushed by the support legs 12.

[0047] As an embodiment provided in this application, Figure 1 and Figure 2 The main support column 11 includes a main support column body 111 and a hoisting groove 112 opened at one end of the main support column body 111. The hoisting groove 112 is used to connect the crane to the main support column body 111.

[0048] The installation anchor point of the crane is fixed in the lifting groove 112. The main column body 111 can be lifted into the pressure vessel by the crane. After the main column body 111 is fixed and installed by the support legs 12, the installation anchor point of the crane can be separated from the lifting groove 112.

[0049] The main support column body 111 is connected to the crane by using the lifting groove 112, which can make the installation process simple and convenient.

[0050] As an embodiment provided in this application, Figure 1 and Figure 2 The support leg 12 includes a hydraulic rod 121 hinged to the outside of the main support column body 111, and a pad foot 122 fixedly connected to the output end of the hydraulic rod 121;

[0051] Among them, there are four supporting legs 12, and the interval between two adjacent supporting legs 12 is 90°. The friction at the hinge point between the hydraulic rod 121 and the main supporting column body 111 is relatively large, and the hydraulic rod 121 can only be rotated manually. The hydraulic rod 121 will not rotate under the action of its own gravity.

[0052] Before the main support column body 111 is hoisted into the pressure vessel, the hydraulic rod 121 should be rotated so that its axis is perpendicular to the axial direction of the main support column body 111. That is, the hydraulic rod 121 should be rotated to the adjacent Figure 2 Position shown.

[0053] After the main support column body 111 is hoisted into the interior of the pressure vessel, the four hydraulic rods 121 are driven to extend so that the four pads 122 are in close contact with the inner surface of the pressure vessel, thereby fixing the main support column body 111. Subsequently, even if the installation anchor point of the crane is detached from the hoisting groove 112, the installation of the main support column body 111 can be completed.

[0054] The main support column body 111 can be installed and fixed inside the pressure vessel by utilizing the supporting force provided by the four hydraulic rods 121 .

[0055] As an embodiment provided in this application, Figure 1 and Figure 2 The installation component 13 includes an underwater monitoring camera installation point 131 and a searchlight installation point 132 arranged on the outside of the hydraulic rod 121, and a robotic arm mounting ring 133 fixedly connected to the other end of the main column body 111. The underwater monitoring camera installation point 131 and the searchlight installation point 132 should be as close to the main column body 111 as possible.

[0056] The underwater surveillance camera mounting point 131 and the searchlight mounting point 132 can be bolted to the underwater surveillance camera and the searchlight, and the robotic arm mounting ring 133 can be used to install the robotic arm.

[0057] Eddy current and ultrasonic testing equipment for inspecting pressure vessels can be installed on the outside of the robotic arm.

[0058] By providing the mounting assembly 13, a mounting location can be provided for an underwater surveillance camera, a searchlight and a robotic arm.

[0059] As an embodiment provided in this application, Figure 1 and Figure 2 The cavity 211 is opened inside the main column body 111, the drainage hole 212 is opened at one end of the main column body 111 close to the robot arm mounting ring 133, and the exhaust hole 213 is opened at one end of the main column body 111 close to the lifting groove 112. The drainage hole 212 and the exhaust hole 213 can connect the cavity 211 with the outside world.

[0060] During the process of hoisting the main support column body 111 inside the pressure vessel, as the main support column body 111 is gradually placed inside the pressure vessel, the liquid inside the pressure vessel will gradually submerge the main support column body 111. During this process, the liquid inside the pressure vessel will gradually enter the cavity 211 through the drainage hole 212, and the air inside the cavity 211 will be gradually discharged through the exhaust hole 213.

[0061] When the main support column body 111 is completely submerged in the liquid inside the pressure vessel, the cavity 211 is filled with the liquid.

[0062] Since the cavity 211 is filled with liquid, the buoyancy of the main support column body 111 is smaller than that of the main support column without the cavity 211 .

[0063] Furthermore, compared to the main support column without the cavity 211 , the main support column body 111 with the cavity 211 has a smaller weight.

[0064] Since the buoyancy and gravity on the main support column body 111 are relatively small, when the main support column body 111 is fixedly installed using the support legs 12, the thrust required to be provided by the hydraulic rod 121 is relatively small, thereby reducing the pressure on the inner surface of the pressure vessel and the weld overlay layer, thereby protecting the inner surface of the pressure vessel and the weld overlay layer.

[0065] As an embodiment provided in this application, Figure 1 and Figure 2 The comparison block assembly 22 includes an eddy current test comparison block 221 embedded in the main support column body 111, and an ultrasonic test comparison block 222 embedded in the main support column body 111. When installing, the eddy current test comparison block 221 and the ultrasonic test comparison block 222 should avoid being installed on the rotation path of the hydraulic rod 121 to prevent the hydraulic rod 121 from colliding with it when it rotates.

[0066] When the eddy current and ultrasonic testing equipment set on the outside of the robotic arm performs testing, the eddy current test comparison block 221 and the ultrasonic test comparison block 222 can calibrate and verify the sensitivity and parameters of the eddy current and ultrasonic testing equipment, thereby making the test results more accurate.

[0067] In summary, by providing the support legs 12, the main support column body 111 can be installed and fixed inside the nuclear reactor pressure vessel. By providing the weight-reducing cavity 21, the weight of the main support column body 111 and the buoyancy it receives can be reduced, thereby reducing the supporting force required to be provided by the hydraulic rod 121, and further reducing the pressure on the inner surface of the pressure vessel and the weld overlay layer, so as to achieve the purpose of protecting the inner surface and the weld overlay layer.

[0068] Reference Figures 1 to 3 This embodiment provides a nuclear power plant reactor pressure vessel detection system, including a support platform, and further including:

[0069] A working unit 3 outside the nuclear reactor building, a working unit 4 above the side of the nuclear reactor pressure vessel, and a working unit 5 inside the nuclear reactor pressure vessel;

[0070] The working unit 3 outside the nuclear reactor building is used for analyzing, storing and processing data; the working unit 4 above the nuclear reactor pressure vessel side is used for controlling the detection equipment; and the working unit 5 inside the nuclear reactor pressure vessel is used for detecting the internal data of the pressure vessel;

[0071] The working unit 3 outside the nuclear reactor building includes a first hub 38, and the working unit 4 above the nuclear reactor pressure vessel side includes a second hub 48. The first hub 38 and the second hub 48 are connected by an optical fiber. The working unit 4 above the nuclear reactor pressure vessel side is electrically connected to the working unit 5 inside the nuclear reactor pressure vessel. When arranged, the working unit 3 outside the nuclear reactor building should be away from the working unit 4 above the nuclear reactor pressure vessel side and the working unit 5 inside the nuclear reactor pressure vessel.

[0072] The first hub 38 is connected to the second hub 48 by optical fiber to realize signal transmission between the working unit 3 outside the nuclear reactor building and the working unit 4 above the side of the nuclear reactor pressure vessel. When operating the working unit 3 outside the nuclear reactor building, the staff can stay away from the working unit 4 above the side of the nuclear reactor pressure vessel and the working unit 5 inside the nuclear reactor pressure vessel, thereby avoiding the staff from being close to the nuclear reactor for a long time while working, thereby reducing the nuclear radiation hazards to the staff.

[0073] As an embodiment provided in this application, Figures 1 to 3The nuclear reactor building external working unit 3 includes a network switching system 37, a data storage system 31 electrically connected to the network switching system 37, a data analysis system 32, a data processing system 33, a plan management system 34, a video monitor and voice dialogue system 35, and a collection work system 36;

[0074] The first hub 38 is electrically connected to the network switching system 37 . The data storage system 31 stores data signals including inspection records, voice communication records, and video surveillance records.

[0075] The data storage system 31 can record all data signals during the inspection process, enabling retrospective review of inspection data and processes. Inspection records can be used to compare defects across previous inspections, video surveillance records can be used to track and identify causes when resolving issues, and voice communication records and video surveillance records can be used for staff improvement and new member training.

[0076] The collection work system 36 sends out a work signal based on the inspection plan that has taken effect within the plan management system 34. The work signal passes through the network switching system 37 and the first hub 38 and is transmitted to the detection equipment through optical fiber. After the detection equipment receives the signal and performs detection, it transmits the detected data to the data analysis system 32 and the data processing system 33 for analysis and processing, and presents the detection results.

[0077] As an embodiment provided in this application, Figures 1 to 3 The working unit 4 above the nuclear reactor pressure vessel side includes a control box 41 electrically connected to the second hub 48, a pneumatic motion system 43, an eddy current ultrasonic system 44, an underwater television inspection system 45, and a video monitoring and voice system 46;

[0078] An ordinary surveillance camera 47 is electrically connected to the video surveillance and voice system 46 , and a UPS power supply 42 is electrically connected to the control box 41 . The UPS power supply 42 can provide a stable power supply for the control box 41 .

[0079] The working signal emitted by the acquisition working system 36 is transmitted to the control box 41, the eddy current ultrasonic system 44, the underwater television inspection system 45, the video monitoring and voice system 46 through the optical fiber between the first hub 38 and the second hub 48. The signal received by the control box 41 is then transmitted to the pneumatic motion system 43.

[0080] As an embodiment provided in this application, Figures 1 to 3The internal working unit 5 of the nuclear reactor pressure vessel includes a robotic arm 51 electrically connected to the pneumatic motion system 43, a multifunctional probe 52 electrically connected to the eddy current ultrasonic system 44, an underwater inspection camera 53 electrically connected to the underwater television inspection system 45, and an underwater monitoring camera 54 electrically connected to the video monitoring and voice system 46;

[0081] The robotic arm 51 is adapted to be installed on the outside of the robotic arm mounting ring 133. The multi-function probe 52 and the underwater inspection camera 53 are bolted to the outside of the robotic arm 51. The underwater monitoring camera 54 is bolted to the underwater monitoring camera mounting point 131. The searchlight 55 is bolted to the searchlight mounting point 132. The hydraulic rod 121 is electrically connected to the control box 41. The control box 41 can control the extension and contraction of the hydraulic rod 121.

[0082] After receiving the working signal, the eddy current ultrasonic system 44 and the underwater television inspection system 45 can control the multifunctional probe 52 and the underwater inspection camera 53 to perform the inspection work.

[0083] When performing eddy current and ultrasonic testing, the multifunctional probe 52 can be used in conjunction with the eddy current test comparison block 221 and the ultrasonic test comparison block 222 to calibrate and verify the sensitivity and parameters of the multifunctional probe 52 .

[0084] The data detected by the multifunctional probe 52 and the underwater inspection camera 53 can be transmitted to the data analysis system 32 and the data processing system 33 via the optical fiber between the second hub 48 and the first hub 38 for data analysis and processing, and transmitted to the data storage system 31 for data storage.

[0085] After receiving the working signal, the pneumatic motion system 43 can control the mechanical arm 51 to move, thereby driving the multi-function probe 52 and the underwater inspection camera 53 to move, thereby completing all-round detection.

[0086] Upon receiving the operating signal, the video surveillance and voice system 46 controls the operation of the conventional surveillance camera 47 and the underwater surveillance camera 54. The conventional surveillance camera 47 monitors the working unit 4 above the nuclear reactor pressure vessel and the area above the sealing surface of the nuclear reactor pressure vessel to prevent operational errors. The underwater surveillance camera 54, in conjunction with the searchlight 55, monitors whether the motion trajectory of the robotic arm 51 complies with the operating procedure.

[0087] The video monitoring and voice system 46 can transmit the monitoring images of the ordinary monitoring camera 47 and the underwater monitoring camera 54 to the video monitor and voice dialogue system 35 through the optical fiber between the second hub 48 and the first hub 38, thereby facilitating observation and communication by staff.

[0088] In summary, through the mutual cooperation of various working units, various systems can be managed in a unified and integrated manner, and by setting up a first hub 38 and a second hub 48, remote control can be achieved, so that workers do not need to stay close to the nuclear reactor pressure vessel for a long time, reducing the damage of nuclear radiation to the health of workers.

[0089] Finally, it should be pointed out that the methods and devices described in detail above are merely embodiments, and those skilled in the art can modify these embodiments in different ways without departing from the scope of the present invention.

Claims

1. A support platform, characterized in that: include, A bracket (1), the bracket (1) comprising a main support column (11), a support leg (12) mounted on the outside of the main support column (11), and a mounting assembly (13) arranged on the outside of the main support column (11) and the support leg (12); The support leg (12) is used to fix the main support column (11), and the mounting assembly (13) is used to install the detection equipment; An auxiliary mechanism (2), the auxiliary mechanism (2) comprising a weight-reducing cavity (21) provided inside the main support column (11), and a comparison test block assembly (22) embedded inside the main support column (11); The weight reduction cavity (21) includes a cavity (211), a drainage hole (212), and an exhaust hole (213); The comparison test block assembly (22) is used to calibrate and verify the sensitivity and parameters of the detection equipment.

2. The support platform according to claim 1, characterized in that: The main support column (11) comprises a main support column body (111) and a hoisting groove (112) provided at one end of the main support column body (111).

3. The support platform according to claim 2, characterized in that: The support leg (12) comprises a hydraulic rod (121) hingedly connected to the outside of the main support column body (111), and a pad foot (122) fixedly connected to the output end of the hydraulic rod (121); There are four supporting legs (12), and the interval between two adjacent supporting legs (12) is 90 degrees.

4. The support platform according to claim 3, characterized in that: The mounting assembly (13) includes an underwater surveillance camera mounting point (131) and a searchlight mounting point (132) arranged outside the hydraulic rod (121), and a mechanical arm mounting ring (133) fixedly connected to the other end of the main support column body (111).

5. The support platform according to claim 4, characterized in that: The cavity (211) is provided inside the main support column body (111), the drainage hole (212) is provided at one end of the main support column body (111) close to the robot arm mounting ring (133), and the exhaust hole (213) is provided at one end of the main support column body (111) close to the hoisting groove (112).

6. The support platform according to claim 4 or 5, characterized in that: The comparison test block assembly (22) comprises an eddy current test comparison block (221) embedded in the main support column body (111), and an ultrasonic test comparison block (222) embedded in the main support column body (111).

7. A nuclear power plant reactor pressure vessel detection system, characterized by: The support platform according to any one of claims 4 to 6 further comprises: A working unit (3) outside the nuclear reactor building, a working unit (4) above the side of the nuclear reactor pressure vessel, and a working unit (5) inside the nuclear reactor pressure vessel; The nuclear reactor building external working unit (3) is used for analyzing, storing and processing data, the nuclear reactor pressure vessel upper side working unit (4) is used for controlling detection equipment, and the nuclear reactor pressure vessel internal working unit (5) is used for detecting data inside the pressure vessel; The working unit (3) outside the nuclear reactor building includes a first hub (38), and the working unit (4) above the nuclear reactor pressure vessel side includes a second hub (48). The first hub (38) and the second hub (48) are connected via an optical fiber, and the working unit (4) above the nuclear reactor pressure vessel side is electrically connected to the working unit (5) inside the nuclear reactor pressure vessel.

8. The nuclear power plant reactor pressure vessel detection system according to claim 7, characterized in that: The nuclear reactor building external working unit (3) includes a network switching system (37), a data storage system (31) electrically connected to the network switching system (37), a data analysis system (32), a data processing system (33), a plan management system (34), a video monitor and voice dialogue system (35), and a data acquisition system (36); The first hub (38) is electrically connected to the network switching system (37).

9. The nuclear power plant reactor pressure vessel detection system according to claim 8, characterized in that: The nuclear reactor pressure vessel side upper working unit (4) includes a control box (41) electrically connected to the second hub (48), a pneumatic motion system (43), an eddy current ultrasonic system (44), an underwater television inspection system (45), and a video monitoring and voice system (46); A common monitoring camera (47) is electrically connected to the video monitoring and voice system (46), and a UPS power supply (42) is electrically connected to the control box (41).

10. The nuclear power plant reactor pressure vessel detection system according to claim 9, characterized in that: The nuclear reactor pressure vessel internal working unit (5) includes a mechanical arm (51) electrically connected to the pneumatic motion system (43), a multifunctional probe (52) electrically connected to the eddy current ultrasonic system (44), an underwater inspection camera (53) electrically connected to the underwater television inspection system (45), and an underwater monitoring camera (54) electrically connected to the video monitoring and voice system (46); The mechanical arm (51) is adapted to be mounted on the outside of the mechanical arm mounting ring (133); the multifunctional probe (52) and the underwater inspection camera (53) are bolted to the outside of the mechanical arm (51); the underwater monitoring camera (54) is bolted to the underwater monitoring camera mounting point (131); the searchlight (55) is bolted to the searchlight mounting point (132); and the hydraulic rod (121) is electrically connected to the control box (41).

Images