Steam generator dismounting and replacing device and method used in high-temperature nuclear radiation environment

Abstract

The application provides a steam generator dismounting and replacing device and method in a high-temperature nuclear radiation environment, and relates to the technical field of large equipment dismounting.The device comprises a moving positioning unit, a dismounting and replacing unit and a hoisting and transporting unit.The moving positioning unit and the dismounting and replacing unit are installed above a steam generator to be dismounted or replaced, and the hoisting and transporting unit has a space for accommodating the dismounting and replacing unit and the steam generator.The dismounting and replacing unit uses flexible isolation cloth to isolate radiation, which not only plays a role in sealing the radiation environment and reducing the splashing and leakage of harmful metal liquid during the dismounting of the steam generator, but also changes the occupied space volume of the device by folding the flexible isolation cloth in the limited operation space.The application can dismount and replace the steam generator in an extreme environment of high temperature and nuclear radiation, reduces the working time of the staff in the extreme dangerous environment, and improves the working efficiency of the steam generator dismounting operation.

Description

Technical Field

[0001] This invention relates to the field of large equipment disassembly and assembly technology, specifically to a device and method for disassembling and replacing a steam generator in a high-temperature nuclear radiation environment. Background Technology

[0002] Lead-bismuth cooled reactors hold immense potential in terms of safety, design simplification, non-proliferation, and economics. The steam generator, a heat transfer device in a lead-bismuth cooled reactor, transfers heat from the primary lead-bismuth alloy coolant to the secondary feedwater, heating the feedwater into saturated steam to drive a turbine and generate electricity. Due to the extreme and unique operating conditions of the steam generator under high-temperature nuclear radiation, operation by personnel in radiation suits is difficult and dangerous. The limited operating space for the auxiliary equipment and the poor reliability of electrical equipment at high temperatures make the safe and rapid disassembly and replacement of the steam generator during maintenance a pressing industry challenge.

[0003] Therefore, based on the structural characteristics, spatial constraints, and extreme operating conditions of existing lead-bismuth alloy reactor steam generators, this invention designs a steam generator disassembly and replacement device suitable for high-temperature nuclear radiation environments. Summary of the Invention

[0004] To address the shortcomings of the existing technology, this invention provides a device and method for disassembling and replacing steam generators in high-temperature nuclear radiation environments. Under the premise of ensuring radiation safety, it can quickly and conveniently disassemble and replace steam generators in reactors, and can also replace transport steam generators. This helps reduce the difficulty and time of work for personnel in extremely dangerous conditions, and improves the efficiency of steam generator maintenance. It has the advantages of high mechanization, simplicity, practicality, and strong operability.

[0005] The technical solution adopted in this invention is a steam generator disassembly and replacement device for a high-temperature nuclear radiation environment. It includes a mobile positioning unit, a disassembly and replacement unit, and a hoisting and transportation unit. The mobile positioning unit and the disassembly and replacement unit are installed above the steam generator to be disassembled or replaced. The hoisting and transportation unit has space to accommodate the disassembly and replacement unit and the steam generator. The mobile positioning unit includes a mechanical gripper, an anti-sway mechanism, a crane, and a position sensor. The mechanical gripper is connected to the crane and is equipped with a mechanical locking buckle. The anti-sway mechanism is located above the mechanical gripper and maintains the sway angle α and direction angle β of the disassembly and replacement device within a threshold range during operation. The crane is positioned above the space where the disassembly and replacement device is located. The position sensor is located inside the crane and is used to locate the spatial coordinates x, y, z.

[0006] The disassembly and replacement unit includes a sealing ring, an end plate, a detachable lifting ring, a support ring, flexible isolation components, an end cap fixing plate, an end cap, and a locking buckle. The end plate is a circular hollow annular plate. The end cap includes an upper end cap and a lower end cap. The end cap fixing plate includes an upper end cap fixing plate and a lower end cap fixing plate. The upper end cap is fixed by means of the upper end cap fixing plate, and the lower end cap is fixed by means of the lower end cap fixing plate. A locking buckle is provided between the upper end cap and the lower end cap. Multiple flexible isolation components are arranged sequentially between the end plate and the upper end cap. The upper surface of the upper flexible isolation component is connected to the lower surface of the end plate, and the lower surface of the lower flexible isolation component is connected to the upper surface of the upper end cap fixing plate. A support ring is provided between two adjacent flexible isolation components. Locking buckles are provided on the outer side walls of both the end plate and the support ring.

[0007] The end plate is installed above the steam generator, and sealing rings are provided on the lower surface of the lower end cover fixing plate and at the connection between the steam generator and the end plate.

[0008] The upper cover includes a first movable block and a second movable block, and the lower cover includes a first movable block and a second movable block. The first and second movable blocks are fixedly connected to the upper cover fixing plate at the end cover fixing point, and both the first and second movable blocks are provided with hooks and locking buckles for connecting with each other. The first and second movable blocks are fixedly connected to the lower cover fixing plate at the end cover fixing point, and both the first and second movable blocks are provided with hooks and locking buckles for connecting with each other. When the two movable blocks of the upper and lower covers are closed, they can seal the disassembly and replacement unit and the lead-bismuth alloy pool.

[0009] The hoisting and transport unit includes a release pad, a hoisting fixture, and fixture wheels. The hoisting fixture is a truss for placing a disassembled or replaced steam generator. The release pad is fixed on the top of the hoisting fixture, and the hoisting fixture is equipped with the fixture wheels.

[0010] Preferably, the sealing ring is an annular ring.

[0011] Preferably, the detachable lifting ring is disposed on the upper surface of the end plate, and multiple detachable lifting rings are circumferentially distributed on the upper surface of the end plate.

[0012] Preferably, the upper end cover and the lower end cover are arranged symmetrically.

[0013] Preferably, the flexible insulating component is a flexible insulating fabric.

[0014] Preferably, locking buckles are provided on the outer side walls of both the end plate and the support ring.

[0015] Preferably, the unhooking pad is a long strip-shaped load-bearing block placed on the overall disassembly device, and the two unhooking pads are arranged symmetrically.

[0016] On the other hand, the present invention also provides a method for disassembling and replacing a steam generator in a high-temperature nuclear radiation environment, which includes the following steps:

[0017] S1. Install, disassemble, and replace the unit and the moving positioning unit, and start the crane to control the movement of the mechanical gripper;

[0018] S2. The flexible insulating cloth in its folded state is fully unfolded for disassembly and replacement of the unit;

[0019] S3, push the end cap to merge and completely seal the disassembly and replacement unit and lead-bismuth alloy pool;

[0020] S4. Start the crane control to fully engage the disassembly and replacement unit and the moving positioning unit onto the unhooking pad of the hoisting and transport unit;

[0021] S5. Unload the mobile positioning unit and simultaneously start the tooling wheels to transport the steam generator to the designated placement area.

[0022] Compared with the prior art, the beneficial effects of the present invention are as follows:

[0023] (1) The present invention provides a steam generator disassembly and replacement device for high temperature nuclear radiation environment. The disassembly and replacement device is designed based on the structural characteristics and space layout limitations of the existing lead-bismuth alloy reactor steam generator. This ensures that the size ratio and positional relationship of the tooling equipment are equivalent to the actual working conditions, which is beneficial to practical application.

[0024] (2) The present invention provides a steam generator disassembly and replacement device for a high-temperature nuclear radiation environment. It uses a sealing rubber ring to seal and isolate radiation in the contact area between the end plate and the steam generator and the contact area between the end cover fixing plate and the device ground. It also uses a flexible isolation cloth made mainly of phenyl silicone rubber to isolate radiation. Under the premise of ensuring radiation safety, it not only plays the role of sealing the nuclear radiation environment and reducing the splashing and leakage of harmful metal liquids during the disassembly of the steam generator, but also changes the space occupied by the device in the limited operating space by folding the flexible isolation cloth, which improves the operational flexibility of the device and facilitates transportation and warehouse management.

[0025] (3) The present invention provides a steam generator disassembly and replacement device for high-temperature nuclear radiation environment. It takes into account the structural characteristics, space layout limitations and extreme working conditions of the steam generator of lead-bismuth alloy reactor. Under the premise of ensuring radiation safety, the steam generator in the reactor can be quickly and conveniently disassembled and replaced. The disassembled steam generator can also be transported. It is beneficial to reduce the working difficulty and working time of the staff in extreme dangerous working conditions, and to improve the working efficiency of steam generator maintenance. It has the advantages of high mechanization and reliability, simplicity and practicality, and strong operability. Attached Figure Description

[0026] Figure 1 This is a schematic diagram of the overall structure of the steam generator disassembly and replacement device for use in a high-temperature nuclear radiation environment according to the present invention.

[0027] Figure 2 This is a schematic diagram of the mobile positioning unit structure of the present invention;

[0028] Figure 3 This is a schematic diagram of the disassembly and replacement unit structure of the present invention;

[0029] Figure 4 This is a schematic diagram of the disassembly and replacement unit of the present invention in a folded state;

[0030] Figure 5 This is a schematic diagram of the hoisting and transportation unit structure of the present invention;

[0031] Figure 6 This is a schematic diagram of the sealing structure of the lower end cover of the disassembly and replacement unit of the present invention;

[0032] Figure 7 This is a schematic flowchart of the method for disassembling and replacing a steam generator in a high-temperature nuclear radiation environment according to the present invention.

[0033] Some of the attached figures are labeled as follows:

[0034] Steam generator 1; moving positioning unit 100; mechanical gripper 101; anti-sway mechanism 102; crane 103; position sensor 104; disassembly and replacement unit 200; end plate 202; detachable lifting ring 203; support ring 204; flexible isolation component 205; end cover fixing plate 206; end cover 207; locking buckle 208; hoisting and transportation unit 300; unhooking pad 301; hoisting fixture 302; fixture moving wheel 303; upper end cover 2071; lower end cover 2072; upper end cover first movable block 20711; upper end cover second movable block 20712; lower end cover first movable block 20721; lower end cover second movable block 20722; upper end cover fixing plate 2061; lower end cover fixing plate 2062. Detailed Implementation

[0035] Hereinafter, embodiments of the present invention will be described with reference to the accompanying drawings.

[0036] This invention provides a device for disassembling and replacing a steam generator in a high-temperature nuclear radiation environment, such as... Figure 1 As shown, it includes a mobile positioning unit 100, a disassembly and replacement unit 200, and a hoisting and transporting unit 300. The mobile positioning unit 100 and the disassembly and replacement unit 200 are installed above the steam generator 1. The hoisting and transporting unit 300 has a space inside to accommodate the disassembly and replacement unit 200 and the steam generator 1. The space is used to accommodate the steam generator 1 during use.

[0037] like Figure 2 As shown, the mobile positioning unit 100 includes a mechanical gripper 101, an anti-sway mechanism 102, a crane 103, and a position sensor 104. The mechanical gripper 101 and the crane 103 are interconnected. The anti-sway mechanism 102 is located above the mechanical gripper 103, and the position sensor 104 is located inside the crane 103. The mechanical gripper 101 is equipped with a mechanical locking buckle, which locks the steam generator 1 to be replaced after gripping it, preventing it from falling during movement. The anti-sway mechanism 102, located above the mechanical gripper 101, maintains the sway angle α and direction angle β of the disassembly and replacement device within a threshold range during operation, preventing large swaying of the entire device from affecting the movement process. The crane is positioned above the space where the disassembly and replacement device is located, and the position sensor 104 is located inside the crane and is used to locate the spatial coordinates (x, y, z) of the entire device in real time and provide feedback. In specific applications, the mechanical gripper 101 is configured as a three-jaw gripper, with its upper end hinged to the crane 103. The three-jaw gripper is used to lock the flange structure on the upper part of the steam generator 1. In other embodiments, the mechanical gripper 101 can also employ other multi-jaw grippers for grasping. Using the spatial coordinate information fed back by the position sensor 104, the crane is controlled to move the mechanical gripper to grasp and lift the entire dismantling device. The anti-sway mechanism 102 detects and compensates for the sway angle α and direction angle β, achieving a good anti-sway effect and reducing the interference of the swaying of the heavy object on the workers.

[0038] like Figure 3 and Figure 4As shown, the disassembly and replacement unit 200 includes a sealing ring, an end plate 202, a detachable lifting ring 203, a support ring 204, a flexible insulating component 205, an end cap fixing plate 206, an end cap 207, and a locking buckle 208. In this embodiment, the flexible insulating component 205 is a flexible insulating cloth, and the end plate 202 is a circular, hollow annular plate. The support ring 204 and the flexible insulating cloth 205 are sequentially and alternately connected between the end plate 202 and the end cap 207. The upper layer of the flexible insulating component 205 is connected to the end plate 202, and the lower layer of the flexible insulating component 205 is connected to the end cap 207. The two adjacent layers of flexible insulating components 205 in the middle are connected and fixed by means of the support ring 204. It can be unfolded when in use and folded when not in use to save storage space. Both the end plate 202 and the support ring 204 are equipped with multiple locking buckles 208. The lowest level flexible insulating cloth 205 is connected to one end of the end cover fixing plate 206, and the end cover 207 is connected to the end cover fixing plate 206. A sealing ring is located in the contact area between the end plate 202 and the steam generator 1, and in the contact area between the end cover fixing plate 206 and the ground of the device (not shown in the figure). In a specific embodiment, the sealing ring is an annular ring to achieve buffering and radiation isolation functions. The detachable lifting ring 203 is located at the upper end of the end plate 202, and the detachable lifting ring 203 can be matched and disconnected from the hook of the crane 103.

[0039] The structure of this invention uses sealing rings to seal and isolate radiation in the contact areas between the end plate and the steam generator, and between the end cover fixing plate and the device ground. It also uses a flexible isolation cloth made primarily of phenyl silicone rubber to isolate radiation. Under the premise of ensuring radiation safety, it not only plays a role in sealing the nuclear radiation environment and reducing the splashing and leakage of harmful molten metal during the disassembly of the steam generator, but also changes the space occupied by the device in a limited operating space by folding the flexible isolation cloth, which improves the operational flexibility of the device and facilitates transportation and warehouse management.

[0040] like Figure 6As shown, the end cap fixing plate 206 includes an upper end cap fixing plate 2061 and a lower end cap fixing plate 2062, and the end cap 207 includes an upper end cap 2071 and a lower end cap 2072, which are placed symmetrically. The upper end cap 2071 includes an upper end cap first movable block 20711 and an upper end cap second movable block 20712, and the lower end cap 2072 includes a lower end cap first movable block 20721 and a lower end cap second movable block 20722. The upper end cap first movable block 20711 and the upper end cap second movable block 20712 are connected and fixed to the upper end cap fixing plate 2061 at the end cap fixing point, and the lower end cap first movable block 20721 and the lower end cap second movable block 20722 are connected and fixed to the lower end cap fixing plate 2062 at the end cap fixing point. Both the first movable block 20711 and the second movable block 20722 of the upper end cover are equipped with hooks and locking buckles for connecting with each other; similarly, both the first movable block 20721 and the second movable block 20722 of the lower end cover are equipped with hooks and locking buckles for connecting with each other. A locking buckle is provided between the upper and lower end covers to achieve the locking and unlocking functions of the entire device. After the two movable blocks of the upper and lower end covers are closed and locked, they can seal the disassembly and replacement unit 200 and the lead-bismuth alloy tank.

[0041] like Figure 5 As shown, the hoisting and transport unit 300 includes a release pad 301, a hoisting fixture 302, and fixture wheels 303. The release pad 301 is fixed on top of the hoisting fixture 302 and is placed symmetrically. The hoisting fixture 302 is equipped with fixture wheels 303. The hoisting fixture 302 can be moved by means of the fixture wheels 303, realizing the convenient transport function of the entire device.

[0042] On the other hand, the present invention also provides a method for disassembling and replacing a steam generator in a high-temperature nuclear radiation environment, such as... Figure 7 As shown, it includes the following steps:

[0043] S1. Install, disassemble, replace the unit and move the positioning unit, start the crane to control the movement of the mechanical gripper, and move the entire device to the target position.

[0044] S2. The flexible insulating cloth in its folded state is fully unfolded for disassembly and replacement of the unit.

[0045] S3, push all end caps to merge and completely seal the disassembly and replacement unit and lead-bismuth alloy pool.

[0046] S4. Start the crane control to fully engage the disassembly and replacement unit and the moving positioning unit onto the unhooking pad of the hoisting and transport unit.

[0047] S5. Unload the mobile positioning unit and simultaneously start the tooling wheels to transport the steam generator to the designated placement area.

[0048] The working principle of the present invention will be further explained below with reference to the accompanying drawings:

[0049] like Figures 1-7 As shown, the present invention provides a steam generator disassembly and replacement device for use in a high-temperature nuclear radiation environment. In the specific working process, the disassembly and replacement unit 200 and the moving positioning unit 100 are first installed. The crane 103 is started to control the movement of the mechanical gripper 101, and the flexible insulating cloth 205 in a folded state is fully unfolded. The workers push the end cover 207 to close and completely seal the lead-bismuth alloy pool. The crane 103 is started to control the disassembly and replacement unit 200 and the moving positioning unit 100 to be fully engaged with the unhooking pad 301 of the hoisting and transporting unit 300. The moving positioning unit 100 is unloaded, and at the same time, the tooling moving wheels 303 are started to transport the steam generator 1 to the designated placement area.

[0050] The apparatus and method of the present invention are based on the structural characteristics, spatial arrangement constraints and extreme operating conditions of the steam generator of the lead-bismuth alloy reactor. Under the premise of ensuring radiation safety, the steam generator in the reactor can be quickly and conveniently disassembled and replaced, and the disassembled steam generator can also be transported. This helps to reduce the working time of the staff under extreme dangerous conditions and improve the work efficiency of steam generator maintenance. It has the advantages of high mechanization and reliability, simplicity and practicality, and strong operability.

[0051] The above embodiments are merely descriptions of preferred embodiments of the present invention and are not intended to limit the scope of the present invention. Various modifications and improvements made by those skilled in the art to the technical solutions of the present invention without departing from the spirit of the present invention should fall within the protection scope defined by the claims of the present invention.

Claims

1. A device for disassembling and replacing a steam generator in a high-temperature nuclear radiation environment, characterized in that: It includes a mobile positioning unit, a disassembly and replacement unit, and a hoisting and transportation unit. The mobile positioning unit and the disassembly and replacement unit are installed together above the steam generator to be disassembled or replaced. The hoisting and transportation unit has a space to accommodate the disassembly and replacement unit and the steam generator. The mobile positioning unit includes a mechanical gripper and a crane. The mechanical gripper and the crane are connected to each other, and the mechanical gripper is equipped with a mechanical locking buckle. The crane is positioned above the disassembly and replacement device. The disassembly and replacement unit includes a sealing ring, an end plate, a detachable lifting ring, a support ring, flexible isolation components, an end cap fixing plate, an end cap, and a locking buckle. The end plate is a circular hollow annular plate. The end cap includes an upper end cap and a lower end cap. The end cap fixing plate includes an upper end cap fixing plate and a lower end cap fixing plate. The upper end cap is fixed by means of the upper end cap fixing plate, and the lower end cap is fixed by means of the lower end cap fixing plate. A locking buckle is provided between the upper end cap and the lower end cap. Multiple flexible isolation components are arranged sequentially between the end plate and the upper end cap. The upper surface of the upper flexible isolation component is connected to the lower surface of the end plate, and the lower surface of the lower flexible isolation component is connected to the upper surface of the upper end cap fixing plate. A support ring is provided between two adjacent flexible isolation components. The upper end of the mechanical gripper is connected to the crane, and the opening and closing of the gripper locks the flange structure on the upper part of the steam generator; the detachable lifting ring is located at the upper end of the end plate, and the detachable lifting ring is matched with the crane's hook for connection and disconnection; The end plate is installed above the steam generator, and sealing rings are provided on the lower surface of the lower end cover fixing plate and at the connection between the steam generator and the end plate. The upper cover includes a first movable block and a second movable block, and the lower cover includes a first movable block and a second movable block. When the two movable blocks of the upper and lower covers are closed, they can seal the disassembly and replacement unit and the lead-bismuth alloy pool. The hoisting and transport unit includes a release pad, a hoisting fixture, and fixture wheels. The hoisting fixture is a truss for placing a disassembled or replaced steam generator. The release pad is fixed on the top of the hoisting fixture, and the hoisting fixture is equipped with the fixture wheels.

2. The steam generator disassembly and replacement device for high-temperature nuclear radiation environment according to claim 1, characterized in that: The mobile positioning unit also includes an anti-sway mechanism and a position sensor. The anti-sway mechanism is located above the mechanical gripper, and the position sensor is located inside the crane and is used to locate spatial coordinates.

3. The steam generator disassembly and replacement device for high-temperature nuclear radiation environment according to claim 1, characterized in that: The first movable block and the second movable block of the upper end cover are fixedly connected to the upper end cover fixing plate at the end cover fixing point, and both the first movable block and the second movable block of the upper end cover are provided with hooks and locking buckles for connecting with each other; the first movable block and the second movable block of the lower end cover are fixedly connected to the lower end cover fixing plate at the end cover fixing point, and both the first movable block and the second movable block of the lower end cover are provided with hooks and locking buckles for connecting with each other.

4. The steam generator disassembly and replacement device for high-temperature nuclear radiation environment according to claim 1, characterized in that: The sealing ring is an annular ring.

5. The steam generator disassembly and replacement device for a high-temperature nuclear radiation environment according to claim 1, characterized in that: Multiple detachable lifting rings are circumferentially distributed on the upper surface of the end plate.

6. The steam generator disassembly and replacement device for a high-temperature nuclear radiation environment according to claim 1, characterized in that: The upper end cover and the lower end cover are arranged symmetrically.

7. The steam generator disassembly and replacement device for a high-temperature nuclear radiation environment according to claim 1, characterized in that: The flexible insulating component is a flexible insulating fabric.

8. The steam generator disassembly and replacement device for a high-temperature nuclear radiation environment according to claim 1, characterized in that: Both the end plate and the outer wall of the support ring are provided with locking buckles.

9. The steam generator disassembly and replacement device for a high-temperature nuclear radiation environment according to claim 1, characterized in that: The unhooking pad is a long strip-shaped load-bearing block, and two unhooking pads are arranged symmetrically.

10. A method for disassembling and replacing a steam generator based on the steam generator disassembly and replacement device for a high-temperature nuclear radiation environment as described in claim 1, characterized in that: It includes the following steps: S1. Install, disassemble, and replace the unit and the moving positioning unit, and start the crane to control the movement of the mechanical gripper; S2. The flexible insulating cloth in its folded state is fully unfolded for disassembly and replacement of the unit; S3, push the end cap to merge and completely seal the disassembly and replacement device and lead-bismuth alloy pool; S4. Start the crane control to fully engage the disassembly and replacement unit and the moving positioning unit onto the unhooking pad of the hoisting and transport unit; S5. Unload the mobile positioning unit and simultaneously start the tooling wheels to transport the steam generator to the designated placement area.

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