Supporting device and system for reactor internals of nuclear reactor and operation method

Abstract

The invention relates to a supporting device and system for reactor internals of a nuclear reactor and an operation method. The supporting device for the reactor internals of the nuclear reactor comprises a bridge assembly, a plurality of overhauling platforms, a plurality of cage assemblies, a shearing assembly, a plurality of stabilizing platforms and a plurality of stabilizing assemblies in one-to-one correspondence with the stabilizing platforms. The device reaches the cage assembly through the beam bridge assembly, an operator stands on the cage assembly so as to get close to the high-level radioactive detector, and after the high-level radioactive detector is detached from the reactor internals, the shearing assembly shears the high-level radioactive detector, so that the operator can conveniently carry out various operations on corresponding positions of the reactor internals of the nuclear reactor; the plurality of stabilizing assemblies are connected with the plurality of guide cylinders, so that the reactor internals can be kept stable, the winch platform equipment on the shielding transfer device is subjected to emergency maintenance and operation, and the operations such as disassembly and shearing of the high-level detector are more stable.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear reactor equipment disassembly, and in particular to a supporting device, system and operating method for nuclear reactor internal components. Background Art

[0002] The internal components of the reactor pressure vessel of a nuclear power plant are used to support and fix the nuclear fuel assembly of the reactor. They are divided into two parts: the upper internal components and the lower internal components. There are 46 sets of high-level detector components in the upper internal components, including 42 sets of neutron measurement components and 4 sets of water level measurement components, which are used to monitor the status of the reactor in real time when the nuclear reactor is running. The high-level detectors work in a high-temperature and high-irradiation dose environment for a long time and need to be replaced after two cycles of reactor operation.

[0003] When replacing the high-level radioactivity detector assembly, the in-pile components are located in the middle of the component pool side, and most of the structure is below the water surface. There is a lack of auxiliary support devices. Conventional devices are unable to provide auxiliary support for the in-pile components and allow operators to approach the high-level radioactivity detector assembly layout.

[0004] Therefore, there is an urgent need for a support device and method for nuclear reactor internal components, which can assist in supporting the internal components while allowing operators to reach all high-radiation detector assembly layout locations and perform related operations.

[0005] The object of the present invention is to provide a supporting device and method for nuclear reactor internal components, so as to realize auxiliary support of the internal components and facilitate various operations at corresponding positions of the internal components. Summary of the invention

[0006] Based on this, it is necessary to provide a support device, system and operating method for nuclear reactor internal components to address the problem that when replacing high-radiation detector assemblies in a component pool, there is a lack of auxiliary support devices, and conventional devices cannot provide auxiliary support for the internal components, making it impossible for operators to get close to the layout of the high-radiation detector assemblies.

[0007] A supporting device for a nuclear reactor internal component, wherein the internal component is provided with a plurality of guide cylinders, and the supporting device for the nuclear reactor internal component comprises:

[0008] A bridge assembly, wherein the bridge assembly is arranged around the pool mouth of the component pool;

[0009] A plurality of maintenance platforms, which are connected to the inner side of the bridge assembly in the circumferential direction and are located above the component pool, and are used for emergency maintenance and operation of the hoisting platform equipment on the shielding transfer device;

[0010] A plurality of cage assemblies, the cage assemblies are connected to the inner side of the bridge assembly in the circumferential direction and are located above the component pool, and are used for disassembling and installing high-level detectors; the plurality of cage assemblies and the plurality of maintenance platforms correspond to each other one by one and are arranged in sequence around the circumference of the bridge assembly;

[0011] A shearing assembly, arranged on the inner side of the bridge assembly in the circumferential direction, for shearing the high-radiation detector;

[0012] A plurality of stable platforms and a plurality of stable components corresponding thereto;

[0013] The plurality of stabilizing components correspond to the plurality of guide cylinders one by one; the stabilizing platform is connected to the inner side of the bridge component in the circumferential direction and is located above the component pool, the stabilizing component is arranged on the corresponding stabilizing platform, and one end of the stabilizing component extending into the component pool is connected to the corresponding guide cylinder;

[0014] The plurality of stabilizing platforms, the plurality of cage assemblies and the plurality of maintenance platforms correspond to each other one by one and are arranged in sequence and at intervals around the circumference of the bridge assembly.

[0015] When performing corresponding operations through the above-mentioned support device of the nuclear reactor internal components, the support device of the nuclear reactor internal components is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform through the bridge assembly. Since the maintenance platform is connected to the inner side of the bridge assembly in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform to perform emergency maintenance and operation on the winch platform equipment on the shielding transfer device, and then reach the cage assembly through the beam bridge assembly. Since the cage assembly is connected to the inner side of the bridge assembly in the circumferential direction and is located above the component pool, the operating personnel standing on the cage assembly can get close to the high-level detector, so that the high-level detector can be removed from the internal components, and the high-level detector can be cut through the shearing assembly, so that it is convenient for the operating personnel to perform various operations on the corresponding positions of the nuclear reactor internal components. At the same time, multiple guide cylinders are connected through multiple stabilizing components, so that the internal components can remain stable, and emergency maintenance and operation of the winch platform equipment on the shielding transfer device, disassembly and shearing of the high-level detector and other operations are more stable.

[0016] In one embodiment, the stabilizing component includes a connecting component, a first moving component, a second moving component, and a third moving component;

[0017] The first moving component is disposed on the stable platform, the second moving component is connected to the first moving component, and the first moving component drives the second moving component to move along a first direction;

[0018] The third moving component is connected to the second moving component, and the second moving component drives the third moving component to move along the second direction;

[0019] One end of the connecting component is detachably connected to the guide cylinder, and the other end is connected to the third moving component, and the third moving component drives the connecting component to move along the third direction;

[0020] The third direction is the depth direction of the component pool, and the first direction, the second direction and the third direction are perpendicular to each other.

[0021] In one embodiment, the first moving assembly includes a first base and a first top screw, the second moving assembly includes a second base and a second top screw, and the third moving assembly includes a third base and a third top screw;

[0022] The first base and the second base are spaced apart on the stable platform along a first direction, and the first top screw passes through the first base along the first direction and abuts against the second base;

[0023] The second top screw is passed through the second base along the second direction and abuts against the third base arranged on the second base;

[0024] The third top screw is arranged along the third direction through the third base and is connected to the connecting assembly.

[0025] In one embodiment, the connecting assembly includes a connecting head, a connecting rod and a connecting piece which are connected in sequence, the connecting head is connected to the third moving assembly, and the connecting piece is detachably connected to the guide cylinder.

[0026] In one embodiment, the bridge assembly comprises two main beams and two end beams, the two main beams are respectively a first main beam and a second main beam, and the two end beams are respectively a first end beam and a second end beam;

[0027] The first main beam and the second main beam are arranged at intervals along the second direction at the pool opening of the component pool and extend along the first direction;

[0028] The first end beam and the second end beam are spaced apart along the first direction and extend along the second direction;

[0029] One end of the first end beam is connected to the first main beam, and the other end is connected to the second main beam;

[0030] One end of the second end beam is connected to the first main beam, and the other end is connected to the second main beam;

[0031] The inspection platform and the cage assembly are both arranged at the connection between the end beam and the main beam, the inspection platform is located on the side of the cage assembly away from the bottom of the component pool along the third direction, and the stabilizing platform is connected to the inner side of the end beam or the main beam around the circumference of the bridge assembly;

[0032] The shear assembly is arranged on a side of the first end beam away from the second end beam, the third direction is the depth direction of the component pool, and the first direction, the second direction and the third direction are perpendicular to each other.

[0033] In one embodiment, the support device for the nuclear reactor internals further comprises an auxiliary bridge;

[0034] The auxiliary bridge is located on a side of the first end beam away from the second end beam, one end of the auxiliary bridge is movably connected to the first main beam along the first direction, and the other end of the auxiliary bridge is movably connected to the second main beam along the first direction.

[0035] In one embodiment, the support device for the nuclear reactor internals further comprises a first displacement assembly and a second displacement assembly;

[0036] The first displacement assembly and the second displacement assembly are arranged at intervals along the second direction at the pool opening of the component pool and extend along the first direction;

[0037] The first main beam is arranged on the first displacement assembly, and the second main beam is arranged on the second displacement assembly. The first displacement assembly drives the first main beam to move along the second direction, and the second displacement assembly drives the second main beam to move along the second direction.

[0038] In one embodiment, the support device for the nuclear reactor internal components further includes a hanger assembly, which is arranged on a side of the first end beam away from the second end beam and is used to hang the high-level detector removed from the internal components for shearing by the shear assembly.

[0039] In one embodiment, the support device for the nuclear reactor internals further comprises a plurality of first telescopic assemblies;

[0040] The plurality of first telescopic components correspond one-to-one to the plurality of cage components. The telescopic components are arranged on the cage components and can extend out of the cage components in a horizontal direction and be located above the component pool.

[0041] In one embodiment, the support device for the nuclear reactor internals further comprises a second telescopic assembly, wherein the second telescopic assembly is arranged on the first end beam;

[0042] The second telescopic assembly can extend out of the first end beam along the first direction away from the second end beam.

[0043] An embodiment of the present application further provides a support system for a nuclear reactor internal component, the support system for a nuclear reactor internal component comprising: a support assembly and the support device for the nuclear reactor internal component;

[0044] The support assembly includes a base and a plurality of support frames extending along a third direction, one end of the support frame is connected to the base and the other end is detachably connected to the bridge assembly, and is used to support the support device of the nuclear reactor internal components, and the third direction is the depth direction of the component pool.

[0045] The above-mentioned support system for the internal components of the nuclear reactor supports the support device for the internal components of the nuclear reactor through the support assembly, and the support device for supporting the internal components of the nuclear reactor is placed on a transport vehicle, passes through the circular arch of the component pool of the internal components of the nuclear reactor, and is transported to the side of the component pool of the internal components. Since one end of the support frame is connected to the base and the other end is detachably connected to the bridge assembly, it can be hoisted to the side of the component pool of the internal components by a hoisting machine and placed there. The bridge assembly is surrounded at the pool mouth of the component pool. At this time, the support assembly completes the functions of transportation and support.

[0046] Specifically, when performing corresponding operations through the above-mentioned support device of the nuclear reactor internal components, the support device of the nuclear reactor internal components is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform through the bridge assembly. Since the maintenance platform is connected to the inner side of the bridge assembly in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform to perform emergency maintenance and operation on the winch platform equipment on the shielding transfer device, and then reach the cage assembly through the beam bridge assembly. Since the cage assembly is connected to the inner side of the bridge assembly in the circumferential direction and is located above the component pool, the operating personnel stand on the cage assembly to get close to the high-level detector, so that the high-level detector can be removed from the internal components, and then the high-level detector can be cut through the shear assembly, thereby facilitating the operating personnel to perform various operations on the corresponding positions of the nuclear reactor internal components.

[0047] An embodiment of the present application further provides an operating method of a supporting device for a nuclear reactor internal component, wherein the supporting device for a nuclear reactor internal component is used to allow an operator to operate the internal component at a corresponding position, and the operating method of the supporting device for a nuclear reactor internal component comprises the following steps:

[0048] Entering the maintenance platform from the pool opening of the component pool through the bridge assembly;

[0049] Connecting the plurality of stabilizing components to the plurality of guide cylinders in a one-to-one correspondence;

[0050] Carry out emergency maintenance and operation of the hoisting platform equipment on the shielded transfer device through the maintenance platform;

[0051] reaching the cage assembly from the inspection platform via the bridge assembly;

[0052] Remove and install high-level detectors through the cage assembly.

[0053] When performing corresponding operations through the above-mentioned support device of the nuclear reactor internal components, the support device of the nuclear reactor internal components is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform through the bridge assembly. Since the maintenance platform is connected to the inner side of the bridge assembly in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform to perform emergency maintenance and operation on the winch platform equipment on the shielding and transfer device, and then reach the cage assembly through the beam bridge assembly. Since the cage assembly is connected to the inner side of the bridge assembly in the circumferential direction and is located above the component pool, the operating personnel standing on the cage assembly can get close to the high-level detector, so that the high-level detector can be removed from the internal components, and the high-level detector can be cut through the shearing assembly, so that the operating personnel can perform various operations on the corresponding positions of the nuclear reactor internal components. Multiple guide cylinders are connected through multiple stabilizing components, so that the internal components can remain stable, and emergency maintenance and operation of the winch platform equipment on the shielding and transfer device, and disassembly and shearing of the high-level detector are more stable. Alternatively, a plurality of operators may stand in turn at various operating positions of the supporting device of the nuclear reactor internal components to perform synchronous operations to improve operating efficiency. BRIEF DESCRIPTION OF THE DRAWINGS

[0054] Figure 1 It is a schematic diagram of a supporting device for a nuclear reactor internal component installed in a component pool according to an embodiment.

[0055] Figure 2 for Figure 1 Top view of the .

[0056] Figure 3 for Figure 2 A zoomed-in view from another angle.

[0057] Figure 4 for Figure 2 Another enlarged view from another angle.

[0058] Figure 5 for Figure 3 A magnified view of the medium stable platform.

[0059] Figure 6 for Figure 5 A magnified view of the stabilizing component.

[0060] Figure 7 for Figure 4Magnified view of the first displacement component.

[0061] Figure 8 for Figure 4 Enlarged view of the middle cage assembly.

[0062] Fig. 9 for Figure 4 An enlarged view of the second telescopic component.

[0063] Fig.10 for Figure 4 Enlarged view of the middle railing.

[0064] Fig.11 for Figure 4 Magnified view of the mid-shear component.

[0065] Fig.12 for Figure 4 Enlarged view of the central inspection platform.

[0066] Fig.13 for Fig.11 Enlarged view of the center bracket assembly.

[0067] Fig.14 Schematic diagram of the support system for nuclear reactor internals.

[0068] Description of Figure Numbers:

[0069] 100-Supporting device for nuclear reactor internals;

[0070] 110-bridge assembly; 111-first main beam; 1111-positioning pin; 112-second main beam; 113-first end beam; 114-second end beam; 115-connecting platform; 116-connecting slot; 117-hanging protrusion; 1181-enclosing plate; 1182-installation tube; 1183-pin; 1184-installation piece;

[0071] 120-maintenance platform; 121-ladder; 122-protection cage; 123-upper platform; 124-outrigger; 125-reinforcement beam;

[0072] 130-cage assembly;

[0073] 140-stable platform; 141-stable assembly; 142-connecting assembly; 143-first moving assembly; 1431-first base; 1432-first top screw; 144-second moving assembly; 1441-second base; 1442-second top screw; 145-third moving assembly; 1451-third base; 1452-third top screw; 146-connecting head; 147-connecting rod; 148-connecting piece; 1491-shackle; 1492-chain;

[0074] 150- shearing assembly; 151- underwater camera mount; 152- poolside camera; 153- long rod tool mount;

[0075] 160- auxiliary bridge;

[0076] 170-first displacement assembly; 171-second displacement assembly; 172-mounting seat; 173-first limit block; 174-needle row; 175-adjustment base; 176-adjustment top screw;

[0077] 180-first telescopic assembly; 181-second telescopic assembly; 182-first slide rail; 183-first sliding plate; 184-first railing; 185-limiting pin; 186-locking bolt; 187-second sliding plate; 1871-second slide rail; 1872-telescopic pulley; 1873-second limiting block; 1874-second railing;

[0078] 190-hanging frame assembly; 191-hanging plate; 192-mounting plate; 193-slide rail; 194-pulley block; 195-hook block;

[0079] 200-support system of nuclear reactor internal components; 201-support assembly; 202-base; 203-support frame;

[0080] 210-core components; 211-high-level detector; 212-guide tube; 213-component pool;

[0081] OX-first direction; OY-second direction; OZ-third direction. DETAILED DESCRIPTION

[0082] In order to make the above-mentioned purposes, features and advantages of the present application more obvious and easy to understand, the specific implementation methods of the present application are described in detail below in conjunction with the accompanying drawings. In the following description, many specific details are set forth to facilitate a full understanding of the present application. However, the present application can be implemented in many other ways different from those described herein, and those skilled in the art can make similar improvements without violating the connotation of the present application, so the present application is not limited by the specific embodiments disclosed below.

[0083] In the description of the present application, it should be understood that if the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "up", "down", "front", "back", "left", "right", "vertical", "horizontal", "top", "bottom", "inside", "outside", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. appear, the orientation or position relationship indicated by these terms is based on the orientation or position relationship shown in the accompanying drawings, which is only for the convenience of describing the present application and simplifying the description, and does not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as a limitation on the present application.

[0084] In addition, if the terms "first" or "second" appear, these terms are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Therefore, a feature defined as "first" or "second" may explicitly or implicitly include at least one of the features. In the description of this application, if the term "plurality" appears, the meaning of "plurality" is at least two, such as two, three, etc., unless otherwise clearly and specifically defined.

[0085] In this application, unless otherwise clearly specified and limited, if the terms "installed", "connected", "connected", "fixed" and the like appear, these terms should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integrated connection; it can be a mechanical connection or an electrical connection; it can be a direct connection or an indirect connection through an intermediate medium, it can be the internal connection of two elements or the interaction relationship between two elements, unless otherwise clearly defined. For ordinary technicians in this field, the specific meanings of the above terms in this application can be understood according to the specific circumstances.

[0086] In the present application, unless otherwise clearly specified and limited, if there is a description that a first feature is "above" or "below" a second feature, etc., or similar descriptions appear, it may mean that the first and second features are in direct contact, or that the first and second features are in indirect contact through an intermediate medium. Moreover, the first feature being "above", "above" and "above" the second feature may mean that the first feature is directly above or obliquely above the second feature, or simply means that the first feature is higher in level than the second feature. The first feature being "below", "below" and "below" the second feature may mean that the first feature is directly below or obliquely below the second feature, or simply means that the first feature is lower in level than the second feature.

[0087] It should be noted that if an element is referred to as being "fixed to" or "disposed on" another element, it may be directly on the other element or there may be a central element. If an element is considered to be "connected to" another element, it may be directly connected to the other element or there may be a central element at the same time. If any, the terms "vertical", "horizontal", "upper", "lower", "left", "right" and similar expressions used in this application are for illustrative purposes only and do not represent the only implementation method.

[0088] See also Figure 1 , Figure 1 A structural schematic diagram of a support device 100 for a nuclear reactor internal component in an embodiment of the present application is shown. The support device 100 for a nuclear reactor internal component provided in an embodiment of the present application includes: a bridge assembly 110, a plurality of maintenance platforms 120, a plurality of cage assemblies 130 and a shear assembly 150.

[0089] The present application provides auxiliary support for the operation and maintenance of the nuclear reactor internals 210, so that the operating personnel can reach the position where the operation is required, perform emergency maintenance and operation on the hoisting platform equipment on the shielding transfer device, and disassemble the high-level detector 211.

[0090] In the above-mentioned support device 100 for nuclear reactor internal components, the bridge assembly 110 is arranged around the pool mouth of the component pool. The maintenance platform 120 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, which is used to shield the emergency maintenance and operation of the hoisting platform equipment on the transfer device. The cage assembly 130 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, which is used to disassemble and install the high-level detector 211. Multiple cage assemblies 130 and multiple maintenance platforms 120 correspond to each other one by one and are arranged in sequence around the circumference of the bridge assembly 110. The shearing assembly 150 is arranged on the inner side of the bridge assembly 110 in the circumferential direction, and is used to shear the high-level detector 211. The internal component 210 is provided with multiple guide cylinders 212 evenly arranged around the circumference of the component pool, and the support device 100 for nuclear reactor internal components also includes multiple stabilizing platforms 140 and multiple stabilizing assemblies 141 corresponding to each other one by one. Multiple stabilizing assemblies 141 correspond to multiple guide cylinders 212 one by one. The stabilizing platform 140 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool. The stabilizing assembly 141 is arranged on the corresponding stabilizing platform 140. One end of the stabilizing assembly 141 extending into the component pool is connected to the corresponding guide cylinder 212. Multiple stabilizing platforms 140, multiple cage assemblies 130, and multiple maintenance platforms 120 correspond to each other and are arranged in sequence around the circumference of the bridge assembly 110.

[0091] When performing corresponding operations through the above-mentioned support device 100 for the internal components of the nuclear reactor, the support device 100 for the internal components of the nuclear reactor is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform 120 through the bridge assembly 110. Since the maintenance platform 120 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform 120 to perform emergency maintenance and operation on the hoisting platform equipment on the shielding transfer device, and then reach the cage assembly 130 through the beam bridge assembly. Since the cage assembly 130 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool Therefore, the operator standing on the cage assembly 130 can get close to the high-radiation detector 211, so that after the high-radiation detector 211 is disassembled from the in-core component 210, the high-radiation detector 211 can be sheared by the shearing assembly 150, so that it is convenient for the operator to perform various operations on the corresponding positions of the in-core component 210 of the nuclear reactor. At the same time, multiple guide cylinders 212 are connected through multiple stabilizing components 141, so that the in-core component 210 can remain stable and will not roll over, making emergency maintenance and operation of the winch platform equipment on the shielding transfer device, and the disassembly and shearing operations of the high-radiation detector 211 more stable.

[0092] See also Figure 2 , Figure 3 as well as Figure 4 Specifically, there are four guide cylinders 212, stabilizing components 141, stabilizing platforms 140, cage components 130, and maintenance platforms 120. Thus, through the four stabilizing components 141, the stabilizing platform 140 is arranged above the component pool, and the stabilizing components 141 can be placed directly on the stabilizing platform 140, or a through hole can be opened at the bottom of the stabilizing platform 140, and the stabilizing components 141 are connected to the stabilizing platform 140, and extend into the component pool through the through hole and connected to the guide cylinder 212, and multiple guide cylinders 212 are connected through multiple stabilizing components 141, so that the internal component 210 can remain stable and will not roll over, so that the emergency maintenance and operation of the hoisting platform equipment on the shielding transfer device, and the disassembly and shearing of the high-level detector 211 are more stable.

[0093] Specifically, the bridge component 110 has a connecting platform 115 extending horizontally toward the axis of the component pool. The connecting platform 115 has a connecting slot 116 along the direction of the bridge component 110. The connecting slot 116 extends along the direction in which the corresponding beam extends. The stabilizing platform 140 has a hanging protrusion 117 close to the connecting platform 115. The hanging protrusion 117 is inserted into the connecting slot 116, so that the stabilizing platform 140 and the bridge component 110 form a cantilever beam structure, thereby realizing a detachable connection between the stabilizing platform 140 and the bridge component 110.

[0094] See also Fig.12Specifically, the maintenance platform 120 includes: a ladder 121, a protective cage 122, an upper platform 123, a plurality of legs 124 and a plurality of reinforcing beams 125, the plurality of legs 124 are connected to the bridge assembly 110, the two ends of the reinforcing beam 125 are respectively connected to two adjacent legs 124, the upper platform 123 is connected to the plurality of legs 124, the protective cage 122 is connected to the upper platform 123, one end of the ladder 121 is connected to the bridge assembly 110, and the other end is connected to the protective cage 122, so that the workers can climb from the bridge assembly 110 to the protective cage 122, and the top of the cage assembly 120 is connected to the bridge assembly 110, so that the protective cage 122 is located on the upper part of the protective cage 1222 along the third direction OZ.

[0095] See also Figure 5 and Figure 6 In one embodiment, the stabilizing assembly 141 includes a connecting assembly 142, a first moving assembly 143, a second moving assembly 144 and a third moving assembly 145. The first moving assembly 143 is disposed on the stabilizing platform 140, the second moving assembly 144 is connected to the first moving assembly 143, and the first moving assembly 143 drives the second moving assembly 144 to move along the first direction OX. The third moving assembly 145 is connected to the second moving assembly 144, and the second moving assembly 144 drives the third moving assembly 145 to move along the second direction OY. One end of the connecting assembly 142 is detachably connected to the guide cylinder 212, and the other end is connected to the third moving assembly 145, and the third moving assembly 145 drives the connecting assembly 142 to move along the third direction OZ. The third direction OZ is the depth direction of the component pool, and the first direction OX, the second direction OY and the third direction OZ are perpendicular to each other.

[0096] In this embodiment, since the stabilizing platform 140 extends from the bridge assembly 110 to the top of the component pool, the connection direction and extension direction between the connecting assembly 142 and the guide cylinder 212 are both the third direction OZ. Therefore, it is necessary to move the connecting assembly 142 in the horizontal direction so that the connecting assembly 142 is aligned with the guide cylinder 212, and then adjust the distance between the connecting assembly 142 and the guide cylinder 212 along the third direction OZ through the third moving assembly 145, and then connect the connecting assembly 142 and the guide cylinder 212. At this time, the force of the connecting assembly 142 on the guide cylinder 212 is along the third direction OZ, so that the in-pile component 210 can be more stable and will not roll over. At the same time, due to the stability of the pulling force along the third direction OZ, the various components in the in-pile component 210 can be protected from damage.

[0097] In one embodiment, the first moving assembly 143 includes a first base 1431 and a first top screw 1432, the second moving assembly 144 includes a second base 1441 and a second top screw 1442, and the third moving assembly 145 includes a third base 1451 and a third top screw 1452. The first base 1431 and the second base 1441 are arranged on the stable platform 140 at intervals along the first direction OX, the first top screw 1432 is arranged through the first base 1431 along the first direction OX and abuts against the second base 1441, and the second base 1441 is driven to move along the first direction OX by the rotation of the first top screw 1432. The second top screw 1442 is arranged through the second base 1441 along the second direction OY and abuts against the third base 1451 arranged on the second base 1441, and the third base 1451 is driven to move along the second direction OY by the rotation of the second top screw 1442. The third top screw 1452 is passed through the third base 1451 along the third direction OZ and connected to the connecting assembly 142, and the connecting assembly 142 is driven to move along the third direction OZ by the rotation of the third top screw 1452. Thus, the thrust can be converted into torque, saving the force of moving the second base 1441, the third base 1451 and the connecting assembly 142, and at the same time, the moving distance of the second base 1441, the third base 1451 and the connecting assembly 142 can be controlled more accurately, ensuring that the connecting assembly 142 is accurately aligned with the guide cylinder 212 and connected to the guide cylinder 212. The fine adjustment of the third top screw 1452 along the third direction OZ allows the connecting assembly 142 to finely adjust the force on the guide cylinder 212, ensuring the stable and balanced tension of the connecting assembly 142 on the internal component 210.

[0098] In one embodiment, the connection assembly 142 includes a connection head 146, a connection rod 147 and a connection member 148 connected in sequence, the connection head 146 is connected to the third movable assembly 145, and the connection member 148 is detachably connected to the guide cylinder 212. The connection member 148 can be detachably connected to the guide cylinder 212 by rotating or telescopic snap-fitting, and the connection member 148 is connected to the third movable assembly 145 by snap-fitting or other means. Specifically, the connection assembly 142 also includes a shackle 1491 and a chain 1492, one end of the shackle 1491 is connected to the chain 1492, and the other end is snap-fitted to the connection head 146, and one end of the chain 1492 away from the connection rod 147 is connected to the third movable assembly 145, and the connection rod 147 can ensure that the tension is along the extension direction of the connection rod 147 to prevent the tension from being offset by other plastic materials.

[0099] In one embodiment, the bridge assembly 110 includes two main beams and two end beams, the two main beams are respectively a first main beam 111 and a second main beam 112, and the two end beams are respectively a first end beam 113 and a second end beam 114. The first main beam 111 and the second main beam 112 are arranged at intervals at the pool mouth of the component pool along the second direction OY and extend along the first direction OX. The first end beam 113 and the second end beam 114 are arranged at intervals along the first direction OX and extend along the second direction OY. One end of the first end beam 113 is connected to the first main beam 111, and the other end is connected to the second main beam 112. One end of the second end beam 114 is connected to the first main beam 111, and the other end is connected to the second main beam 112. The maintenance platform 120 and the cage assembly 130 are both arranged at the connection between the end beam and the main beam, and the maintenance platform 120 is located on the side of the cage assembly 130 away from the pool bottom of the component pool along the third direction OZ, and the stabilizing platform 140 is connected to the inner side of the end beam or the main beam around the circumference of the bridge assembly 110. The shear assembly 150 is disposed on a side of the first end beam 113 away from the second end beam 114 . The third direction OZ is the depth direction of the component pool. The first direction OX, the second direction OY and the third direction OZ are perpendicular to each other.

[0100] In this embodiment, when performing corresponding operations through the support device 100 of the nuclear reactor internal component, the support device 100 of the nuclear reactor internal component is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform 120 through the four beams of the bridge assembly 110. Since the maintenance platform 120 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform 120 to perform emergency maintenance and operation on the hoisting platform equipment on the shielding transfer device, and then reach the cage assembly 130 through the four beams of the beam bridge assembly. Since the cage assembly 130 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, the operating personnel can stand on the cage assembly 130. The assembly 130 can thus be close to the high-radiation detector 211, so that after the high-radiation detector 211 is disassembled from the in-core component 210, the high-radiation detector 211 can be sheared by the shearing assembly 150, so as to facilitate the operators to perform various operations on the corresponding positions of the in-core component 210 of the nuclear reactor. The operators remove the cover of the high-radiation detector 211 on the cage assembly 130, install the pull-out connecting sleeve to the high-radiation detector 211, and then install the lifting chain of the crane to the connecting sleeve. The crane pulls out the high-radiation detector 211 along the third direction OZ, and then moves to the side of the first end beam 113 away from the second end beam 114, and the operators shear the high-radiation detector 211 on this side by the shearing assembly 150.

[0101] The main beam includes: a bottom plate, a cover plate, a web plate, a walking platform, two weighing plates, multiple partitions, and multiple reinforcing plates. The cover plate is located at the upper part of the bottom plate, and the two sides of the web plate are respectively connected to the bottom plate and the cover plate. The bottom plate, the cover plate, and the web plate extend along the first direction OX. The two weighing plates are respectively arranged at the two ends of the bottom plate and are located at the bottom of the bottom plate. The two sides of the partition plate are respectively connected to the bottom plate and the cover plate. Multiple partitions are arranged in sequence along the first direction OX. Multiple reinforcing plates are arranged in sequence along the first direction OX. The two ends of the reinforcing plate are respectively connected to the bottom plate and the cover plate. The walking platform is located on one side of the web plate or the walking platform is arranged on both sides of the web plate. The walking platform is connected to the web plate, the cover plate, and the bottom plate for workers to walk.

[0102] The main beam is also provided with a railing, and the length, width and height of the main beam are 8735mm, 2076mm, and 1438mm respectively, with a total weight of 2.65t. The first end beam 113 and the second end beam 114 are also provided with a railing, wherein the length, width and height of the first end beam 113 are 5300mm, 2030mm, and 1634mm respectively, with a total weight of 2.25t. The length, width and height of the second end beam 114 are 5300mm, 2054mm, and 1647mm respectively, with a total weight of 2.2t.

[0103] See also Fig.10 A panel 1181 is welded on both sides of each beam, and a mounting tube 1182 is provided on the panel 1181 for inserting the railing. A latch 1183 and a mounting piece 1184 are provided on the mounting tube 1182. The railing is placed out of the mounting tube 1182 by cooperating with the latch 1183 and the mounting piece 1184.

[0104] In one embodiment, the support device 100 for the nuclear reactor internals further includes an auxiliary bridge 160. The auxiliary bridge 160 is located on a side of the first end beam 113 away from the second end beam 114, one end of the auxiliary bridge 160 is movably connected to the first main beam 111 along the first direction OX, and the other end of the auxiliary bridge 160 is movably connected to the second main beam 112 along the first direction OX.

[0105] Thus, the auxiliary bridge 160 can be moved along the first direction OX by means of an active connection, so that when multiple high-radiation detectors 211 are transported to the space between the auxiliary bridge 160 and the first end beam 113 for shearing operations, the auxiliary bridge 160 can make room for transportation and can return to the shearing assembly 150 and perform shearing operations.

[0106] Optionally, the first main beam 111 and the second main beam 112 are provided with a slide groove along the first direction OX, and both ends of the auxiliary bridge 160 are provided with a sliding part, which is correspondingly located in the slide groove and moves along the first direction OX. The movement can also be achieved by providing a pulley and a slide rail 193, and the specific movement method between the auxiliary bridge 160 and the first main beam 111 and the second main beam 112 is not limited here.

[0107] Preferably, both the first main beam 111 and the second main beam 112 are provided with positioning pins 1111 for preliminarily connecting the end beam to the main beam.

[0108] In one embodiment, the support device 100 for the nuclear reactor internals further includes a first displacement assembly 170 and a second displacement assembly 171. The first displacement assembly 170 and the second displacement assembly 171 are arranged at intervals at the pool mouth of the component pool along the second direction OY and extend along the first direction OX. The first main beam 111 is arranged on the first displacement assembly 170, and the second main beam 112 is arranged on the second displacement assembly 171. The first displacement assembly 170 drives the first main beam 111 to move along the second direction OY, and the first displacement assembly 170 drives the second main beam 112 to move along the second direction OY. In this embodiment, the first displacement assembly 170 drives the first main beam 111 to move along the second direction OY, and the first displacement assembly 170 drives the second main beam 112 to move along the second direction OY. Both ends of the second first end beam 113 are connected to the first main beam 111 and the second main beam 112, and both ends of the second end beam 114 are connected to the first main beam 111 and the second main beam 112. Therefore, the first displacement assembly 170 and the second displacement assembly 171 can drive the entire bridge assembly 110 to move, and then drive the entire nuclear reactor internal component support device 100 to move along the first direction OX, so that the nuclear reactor internal component support device 100 can be moved according to demand.

[0109] Specifically, the first displacement assembly 170 and the second displacement assembly 171 have the same structure. Taking the first displacement assembly 170 as an example:

[0110] See also Figure 7 The first displacement assembly 170 includes: a mounting seat 172, a first limiting block 173, a needle roller row 174, an adjustment base 175 and an adjustment top screw 176. The mounting seat 172 and the adjustment base 175 are connected and arranged along the first direction OX. The mounting seat 172 extends along the first direction OX. The needle roller row 174 is arranged on the mounting seat 172 and extends along the first direction OX. The top screw is arranged on the adjustment base 175 along the first direction OX and abuts against the first main beam 111. The first limiting block 173 is arranged at one end of the mounting seat 172 away from the adjustment top screw 176 along the first direction OX, and protrudes in the direction close to the first main beam 111 along the third direction OZ. The first main beam 111 is arranged on the needle roller row 174 along the first direction OX. The top screw is rotated to drive the first main beam 111 to move along the first direction OX on the needle roller row 174. The limiting block is used to prevent the first main beam 111 from escaping from the top screw row. This method makes the movement and adjustment of the first main beam 111 more labor-saving and accurate. The first displacement assembly 170 and the second displacement assembly 171 jointly move the support device 100 of the nuclear reactor internals, making the movement and adjustment of the support device 100 of the nuclear reactor internals more labor-saving and accurate.

[0111] Specifically, the bottom of the mounting seat 172 and the adjustment base 175 has a slide groove, and a slide rail extending along the first direction OX is provided at the pool mouth of the component pool, and the slide rail is partially located in the slide groove, so as to realize the movement of the mounting seat 172 and the adjustment base 175 along the first direction OX. The first displacement assembly 170 also includes a fastener, which is passed through the side wall of the slide groove and abuts against the slide rail to fix the mounting seat 172 and the adjustment base 175 to the slide rail or release the mounting seat 172 and the adjustment base 175 from the slide rail.

[0112] In other embodiments, the first displacement assembly 170 and the second displacement assembly 171 may also be a sliding structure of a slide rail and a slide groove, or may be a moving method of pneumatic, electric, hydraulic or other power.

[0113] In one embodiment, the support device 100 for the nuclear reactor internal component further includes a hanger assembly 190, which is disposed on a side of the first end beam 113 away from the second end beam 114 and is used to hang the high-level radiation detector 211 removed from the internal component 210 for shearing by the shear assembly 150.

[0114] See also Fig.13 Specifically, the hanger assembly 190 includes a hanger plate 191, a mounting plate 192, a slide rail 193, a pulley block 194, and a hook block 195. One end of the hanger plate 191 is connected to the slide rail 193, and the other end is connected to the first end beam 113. One end of the mounting plate 192 is connected to the slide rail 193, and the other end is connected to the first end beam 113. The pulley block 194 is slidably matched with the slide rail 193. One end of the hook block 195 is connected to one end of the pulley, and the other end is used to hang the high-level detector 211. Specifically, the hook block 195 has a plurality of hooks, specifically 46 hooks, which can meet the needs of hanging 46 high-level detectors 211.

[0115] In one embodiment, the support device 100 for the nuclear reactor internals further comprises a plurality of first telescopic assemblies 180. The plurality of first telescopic assemblies 180 correspond one to one with the plurality of cage assemblies 130, and the telescopic assemblies are arranged on the cage assemblies 130, and can extend out of the cage assemblies 130 in the horizontal direction and be located above the component pool.

[0116] See also Figure 8Specifically, the first telescopic assembly 180 includes a slide rail 193 assembly including a first slide rail 182, a first sliding plate 183, a first railing 184, a limit pin 185 and a locking bolt 186. The first railing 184 is arranged on the first sliding plate 183. The first slide rail 182 is arranged on the cage assembly 130, and the first sliding plate 183 is slidably matched with the first slide rail 182 and can move in a direction close to or away from the axis of the component pool. The first sliding plate 183 is sequentially provided with a plurality of positioning holes and a plurality of adjustment holes along a direction close to the axis of the component pool. The locking bolt 186 can be inserted into the positioning hole or the adjustment hole to fix the first sliding plate 183 at different positions relative to the first slide rail 182. The limit pin 185 is arranged at the bottom of the first sliding plate 183 to prevent the first sliding plate 183 from slipping off the first slide rail 182.

[0117] See also Fig. 9 In one embodiment, the support device 100 for the nuclear reactor internals further comprises a second telescopic assembly 181, which is disposed on the first end beam 113. The second telescopic assembly 181 can extend out of the first end beam 113 in the first direction OX away from the second end beam 114.

[0118] The second telescopic assembly 181 includes: a second sliding plate 187, a second slide rail 1871, a second rail 1874, a telescopic pulley 1872, and a second stop block 1873. The second rail 1874 is disposed on the second sliding plate 187. The second slide rail 1871 is disposed on the first end beam 113, and the second sliding plate 187 is provided with a telescopic pulley 1872, which is slidably matched with the second slide rail 1871 along the first direction OX so that the second sliding plate 187 extends out of the first end beam 113, and the stop block is disposed at one end of the second sliding plate 187 to prevent the second sliding plate 187 from slipping off the second slide rail 1871.

[0119] Specifically, the first end beam 113 is in the shape of a "J", that is, the two ends of the first end beam 113 are connected to the first main beam 111 and the second main beam 112, wherein the second telescopic component 181 is arranged along the third direction OZ on one side of the main beam close to the bottom of the component pool, and the second telescopic component 181 is lower than the main beam.

[0120] See also Fig.11 Specifically, the support device 100 for the internal components of the nuclear reactor also includes: a poolside camera 152, an underwater camera bracket 151 and a long rod tool bracket 153. The underwater camera bracket 151, the poolside camera 152, the bracket assembly 190 and the long rod tool bracket 153 are arranged in sequence along the second direction OY. The tool bracket, the underwater camera bracket 151, the poolside camera 152, the bracket assembly 190 are all arranged on the side of the first end beam 113 away from the second end beam 114, and the long rod tool bracket 153 is arranged on the first main beam 111 or the second main beam 112.

[0121] An embodiment of the present application further provides a support system 200 for a nuclear reactor internal component, and the support system 200 for a nuclear reactor internal component includes: a support assembly 201 and a support device 100 for a nuclear reactor internal component. The support assembly 201 includes a base 202 and a plurality of support frames 203 extending along a third direction OZ, one end of the support frame 203 is connected to the base 202 and the other end is detachably connected to the bridge assembly 110, so as to support the support device 100 for a nuclear reactor internal component, and the third direction OZ is the depth direction of the component pool.

[0122] See also Fig.14 The above-mentioned support system 200 for the internal components of a nuclear reactor supports the support device 100 for the internal components of a nuclear reactor through the support assembly 201, and the support device 100 for supporting the internal components of a nuclear reactor is placed on a transport vehicle, passes through the circular arch of the component pool of the internal components 210 of the nuclear reactor, and is transported to the side of the component pool of the internal components 210 of the nuclear reactor. Since one end of the support frame 203 is connected to the base 202 and the other end is detachably connected to the bridge assembly 110, it can be hoisted to the side of the component pool of the internal components 210 by a hoisting machine, and the bridge assembly 110 is surrounded at the pool mouth of the component pool. At this time, the support assembly 201 completes the transportation and support functions. If the height of the maintenance platform 120 is sufficient to pass through the circular arch of the component pool of the internal components 210 of the nuclear reactor, the support device 100 for the internal components of the nuclear reactor can be transported as a whole into the circular arch of the component pool of the internal components 210 of the nuclear reactor through the support system 200 for the internal components of the nuclear reactor. If the maintenance platform 120 is too high, when passing through the circular arch of the component pool of the nuclear reactor's internal components 210, the maintenance platform 120 can be transported alone to the pool mouth of the component pool of the internal components 210 first, and then installed on the bridge assembly 110 in sequence.

[0123] Specifically, the support frame 203 includes a support rod and a groove member, one end of the support rod is connected to the base 202, and the other end is connected to the groove member, the groove member has a groove that is recessed away from the bridge assembly 110, and is used to accommodate the bridge assembly 110, so as to position the bridge assembly 110 and ensure the stability of the bridge assembly 110 during transportation. Multiple support frames 203 are divided into two groups and are respectively arranged at both ends of the base 202 along the second direction OY and arranged in sequence along the first direction OX, so as to mainly support the first main beam 111 and the second main beam 112. The base 202 is connected by two bottom frames, and each component of the support assembly 201 is welded from 304 stainless steel rectangular steel pipes.

[0124] Specifically, when performing corresponding operations through the above-mentioned support device 100 of the nuclear reactor internal component, the support device 100 of the nuclear reactor internal component is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform 120 through the bridge assembly 110. Since the maintenance platform 120 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform 120 to perform emergency maintenance and operation on the winch platform equipment on the shielding transfer device, and then reach the cage assembly 130 through the beam bridge assembly. Since the cage assembly 130 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, the operating personnel stand on the cage assembly 130 to get close to the high-radiation detector 211, so that the high-radiation detector 211 can be disassembled from the internal component 210, and then the high-radiation detector 211 can be cut through the shear assembly 150, so that the operating personnel can perform various operations on the corresponding positions of the nuclear reactor internal component 210.

[0125] An embodiment of the present application also provides an operating method of a support device 100 for a nuclear reactor internal component, wherein the support device 100 for a nuclear reactor internal component is used for operators to operate the internal component at a corresponding position, and the operating method of the support device 100 for a nuclear reactor internal component comprises the following steps: entering the maintenance platform 120 from the pool mouth of the component pool through the bridge assembly 110. A plurality of stabilizing assemblies 141 are matched one by one with a plurality of guide cylinders 212 and connected. Emergency maintenance and operation of the hoisting platform equipment on the shielding transfer device are performed through the maintenance platform 120. Reach the cage assembly 130 from the maintenance platform 120 through the bridge assembly 110. Specifically, it is necessary to go down to the bridge assembly 110 from the maintenance platform through a ladder, and then reach the cage assembly 130 through the connected bridge assembly 110, and vice versa. Disassemble and install the high-level detector 211 through the cage assembly 130.

[0126] When performing corresponding operations through the above-mentioned support device 100 for the internal components of the nuclear reactor, the support device 100 for the internal components of the nuclear reactor is installed at the pool mouth of the component pool, and the operating personnel reach the maintenance platform 120 through the bridge assembly 110. Since the maintenance platform 120 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool, the operating personnel can stand on the maintenance platform 120 to perform emergency maintenance and operation on the hoisting platform equipment on the shielding transfer device, and then reach the cage assembly 130 through the beam bridge assembly. Since the cage assembly 130 is connected to the inner side of the bridge assembly 110 in the circumferential direction and is located above the component pool Therefore, the operator standing on the cage assembly 130 can get close to the high-radiation detector 211, so that after the high-radiation detector 211 is disassembled from the internal component 210, the high-radiation detector 211 can be sheared by the shearing assembly 150, so that the operator can perform various operations on the corresponding positions of the nuclear reactor internal component 210. At the same time, multiple guide cylinders 212 are connected through multiple stabilizing assemblies 141, so that the internal component 210 can remain stable and will not tip over, making emergency maintenance and operation of the hoisting platform equipment on the shielding transfer device, and the disassembly and shearing of the high-radiation detector 211 more stable. Multiple operators can also stand in each operating position of the support device 100 of the nuclear reactor internal component in turn to perform synchronous operations to improve operating efficiency.

[0127] The technical features of the above-described embodiments may be arbitrarily combined. To make the description concise, not all possible combinations of the technical features in the above-described embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0128] The above-described embodiments only express several implementation methods of the present application, and the descriptions thereof are relatively specific and detailed, but they cannot be construed as limiting the scope of the patent application. It should be pointed out that, for a person of ordinary skill in the art, several variations and improvements can be made without departing from the concept of the present application, and these all belong to the protection scope of the present application. Therefore, the protection scope of the patent application shall be subject to the attached claims.

Claims

1. A support device for nuclear reactor internals, characterized in that: The internals of the reactor are provided with a plurality of guide cylinders, and the supporting device of the internals of the nuclear reactor comprises: A bridge assembly, wherein the bridge assembly is arranged around the pool mouth of the component pool; A plurality of maintenance platforms, which are connected to the inner side of the bridge assembly in the circumferential direction and are located above the component pool, and are used for emergency maintenance and operation of the hoisting platform equipment on the shielding transfer device; A plurality of cage assemblies, the cage assemblies are connected to the inner side of the bridge assembly in the circumferential direction and are located above the component pool, and are used for disassembling and installing high-level detectors; the plurality of cage assemblies and the plurality of maintenance platforms correspond to each other one by one and are arranged in sequence around the circumference of the bridge assembly; A shearing assembly, arranged on the inner side of the bridge assembly in the circumferential direction, for shearing the high-radiation detector; A plurality of stable platforms and a plurality of stable components corresponding thereto; The plurality of stabilizing components correspond to the plurality of guide cylinders one by one; the stabilizing platform is connected to the inner side of the bridge component in the circumferential direction and is located above the component pool, the stabilizing component is arranged on the corresponding stabilizing platform, and one end of the stabilizing component extending into the component pool is connected to the corresponding guide cylinder; The plurality of stabilizing platforms, the plurality of cage assemblies and the plurality of maintenance platforms correspond to each other one by one and are arranged in sequence and at intervals around the circumference of the bridge assembly.

2. The support device for nuclear reactor internals according to claim 1, characterized in that: The stabilizing component includes a connecting component, a first moving component, a second moving component and a third moving component; The first moving component is disposed on the stable platform, the second moving component is connected to the first moving component, and the first moving component drives the second moving component to move along a first direction; The third moving component is connected to the second moving component, and the second moving component drives the third moving component to move along the second direction; One end of the connecting component is detachably connected to the guide cylinder, and the other end is connected to the third moving component, and the third moving component drives the connecting component to move along the third direction; The third direction is the depth direction of the component pool, and the first direction, the second direction and the third direction are perpendicular to each other.

3. The support device for nuclear reactor internals according to claim 2, characterized in that: The first moving assembly includes a first base and a first top screw, the second moving assembly includes a second base and a second top screw, and the third moving assembly includes a third base and a third top screw; The first base and the second base are spaced apart on the stable platform along a first direction, and the first top screw passes through the first base along the first direction and abuts against the second base; The second top screw is passed through the second base along the second direction and abuts against the third base arranged on the second base; The third top screw is arranged along the third direction through the third base and is connected to the connecting assembly.

4. The support device for nuclear reactor internals according to claim 2, characterized in that: The connecting assembly includes a connecting head, a connecting rod and a connecting piece which are connected in sequence, the connecting head is connected to the third moving assembly, and the connecting piece is detachably connected to the guide cylinder.

5. The support device for nuclear reactor internals according to claim 1, characterized in that: The bridge assembly comprises two main beams and two end beams, the two main beams are respectively a first main beam and a second main beam, and the two end beams are respectively a first end beam and a second end beam; The first main beam and the second main beam are arranged at intervals along the second direction at the pool opening of the component pool and extend along the first direction; The first end beam and the second end beam are spaced apart along the first direction and extend along the second direction; One end of the first end beam is connected to the first main beam, and the other end is connected to the second main beam; One end of the second end beam is connected to the first main beam, and the other end is connected to the second main beam; The inspection platform and the cage assembly are both arranged at the connection between the end beam and the main beam, the inspection platform is located on the side of the cage assembly away from the bottom of the component pool along the third direction, and the stabilizing platform is connected to the inner side of the end beam or the main beam around the circumference of the bridge assembly; The shear assembly is arranged on a side of the first end beam away from the second end beam, the third direction is the depth direction of the component pool, and the first direction, the second direction and the third direction are perpendicular to each other.

6. The support device for nuclear reactor internals according to claim 5, characterized in that: The supporting device for the nuclear reactor internals also includes an auxiliary bridge; The auxiliary bridge is located on a side of the first end beam away from the second end beam, one end of the auxiliary bridge is movably connected to the first main beam along the first direction, and the other end of the auxiliary bridge is movably connected to the second main beam along the first direction.

7. The support device for nuclear reactor internals according to claim 5, characterized in that: The support device for the nuclear reactor internals also includes a first displacement assembly and a second displacement assembly; The first displacement assembly and the second displacement assembly are arranged at intervals along the second direction at the pool opening of the component pool and extend along the first direction; The first main beam is arranged on the first displacement assembly, and the second main beam is arranged on the second displacement assembly. The first displacement assembly drives the first main beam to move along the second direction, and the second displacement assembly drives the second main beam to move along the second direction.

8. The support device for nuclear reactor internals according to claim 5, characterized in that: The support device for the nuclear reactor internal components also includes a hanger assembly, which is arranged on the side of the first end beam away from the second end beam and is used to hang the high-level detector removed from the internal components for shearing by the shearing assembly.

9. The support device for nuclear reactor internals according to claim 1, characterized in that: The support device for the nuclear reactor internals also includes a plurality of first telescopic assemblies; The plurality of first telescopic components correspond one-to-one to the plurality of cage components. The telescopic components are arranged on the cage components and can extend out of the cage components in a horizontal direction and be located above the component pool.

10. The support device for nuclear reactor internals according to claim 5, characterized in that: The support device for the nuclear reactor internals further comprises a second telescopic assembly, wherein the second telescopic assembly is arranged on the first end beam; The second telescopic assembly can extend out of the first end beam along the first direction away from the second end beam.

11. A support system for nuclear reactor internals, characterized in that: The support system for the nuclear reactor internals comprises: a support assembly and a support device for the nuclear reactor internals according to any one of claims 1 to 10; The support assembly includes a base and a plurality of support frames extending along a third direction, one end of the support frame is connected to the base and the other end is detachably connected to the bridge assembly, and is used to support the support device of the nuclear reactor internal components, and the third direction is the depth direction of the component pool.

12. A method for operating a support device for a nuclear reactor internal component, using the support device for a nuclear reactor internal component as claimed in claims 1 to 10 to allow an operator to operate the internal component at a corresponding position, characterized in that: The operating method of the support device for the nuclear reactor internals comprises the following steps: Entering the maintenance platform from the pool opening of the component pool through the bridge assembly; Connecting the plurality of stabilizing components to the plurality of guide cylinders in a one-to-one correspondence; Carry out emergency maintenance and operation of the hoisting platform equipment on the shielded transfer device through the maintenance platform; reaching the cage assembly from the inspection platform via the bridge assembly; Remove and install high-level detectors through the cage assembly.

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