CN109262267B - Bending equipment in nuclear power station refueling pool water - Google Patents

Bending equipment in nuclear power station refueling pool water Download PDF

Info

Publication number
CN109262267B
CN109262267B CN201811153078.1A CN201811153078A CN109262267B CN 109262267 B CN109262267 B CN 109262267B CN 201811153078 A CN201811153078 A CN 201811153078A CN 109262267 B CN109262267 B CN 109262267B
Authority
CN
China
Prior art keywords
bending
neutron measurement
finger sleeve
arc
guide rail
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201811153078.1A
Other languages
Chinese (zh)
Other versions
CN109262267A (en
Inventor
陈鲲
柳比茨基·亚历山大
任小省
普拉斯库林·亚历山大
朱智
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Zhongwu Xianchu Nuclear Energy Technology Co ltd
Original Assignee
Qingdao Xianchu Energy Development Group Co ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Qingdao Xianchu Energy Development Group Co ltd filed Critical Qingdao Xianchu Energy Development Group Co ltd
Priority to CN201811153078.1A priority Critical patent/CN109262267B/en
Publication of CN109262267A publication Critical patent/CN109262267A/en
Application granted granted Critical
Publication of CN109262267B publication Critical patent/CN109262267B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • BPERFORMING OPERATIONS; TRANSPORTING
    • B23MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23PMETAL-WORKING NOT OTHERWISE PROVIDED FOR; COMBINED OPERATIONS; UNIVERSAL MACHINE TOOLS
    • B23P23/00Machines or arrangements of machines for performing specified combinations of different metal-working operations not covered by a single other subclass
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B21MECHANICAL METAL-WORKING WITHOUT ESSENTIALLY REMOVING MATERIAL; PUNCHING METAL
    • B21DWORKING OR PROCESSING OF SHEET METAL OR METAL TUBES, RODS OR PROFILES WITHOUT ESSENTIALLY REMOVING MATERIAL; PUNCHING METAL
    • B21D5/00Bending sheet metal along straight lines, e.g. to form simple curves
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Optics & Photonics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Wire Processing (AREA)

Abstract

The invention relates to a bending device in water of a nuclear power station refueling pool, which comprises a bracket, a bending guide rod, an arc-shaped guide rail, a roller straightening device, a clamping device and a top steel wire control system. The support is used for installing the guide bar of bending and arc guide rail. The bending guide rod is used for extracting the finger sleeve and simultaneously completing bending and retracting the finger sleeve. The arc-shaped guide rail provides bending radian for the bending guide rod. The roller straightening device is used for accurately positioning the finger sleeve extraction process and straightening the finger sleeve when the finger sleeve is retracted. The clamping device is matched to finish clamping and fixing when the finger sleeve is lifted to a certain height. The top steel wire control system provides power for the bending guide rod. The device is safe to use, can carry out grading treatment and storage on high, medium and low radioactive pollution sections of the finger sleeve, reduces the influence of radioactive substances on the environment, reduces the storage volume of high radioactive pollution wastes, provides radiation protection optimization working conditions for workers, has a simple structure, and reduces the replacement cost of the finger sleeve.

Description

Bending equipment in nuclear power station refueling pool water
Technical Field
The invention relates to nonstandard equipment for operation and maintenance in the field of nuclear power stations, in particular to bending equipment in water of a nuclear power station refueling water tank. The device is used for extracting, bending, backing and straightening a finger sleeve of a damaged high-radiation neutron fluence rate measurement system which is arranged in a reactor pressure vessel, and is suitable for working in a radioactive environment.
Background
The neutron fluence rate measuring system is characterized in that a sleeve (simply referred to as sleeve) taking-out and processing device is dry (non-underwater) winding equipment, namely a closed metal container with a radiation shielding function is used, and the sleeve is wound into a spring coil-like process by using a spring mechanical forming principle in the container. In order to meet the radiation shielding requirement of the dry winding equipment, the wall thickness of the container is more than or equal to 360mm, and the whole weight is about 16.2T. The dry winding equipment cannot accurately position the finger sleeve to be taken out, the finger sleeve is required to be manually pulled out of the pressure vessel and fed into the winding equipment, personnel face the danger that the radiation dose exceeds a safe specified value when pulling out and feeding in the finger sleeve, and the unsafe factors can not meet the safe operation requirement of the nuclear power equipment.
The dry winding apparatus is a single apparatus, and the extraction of the finger-jointed pipes installed at different positions requires manual movement of the apparatus to the position of the finger-jointed pipe to be extracted, and automatic movement and accurate positioning in a three-dimensional space cannot be achieved.
The dry winding equipment winds a finger sleeve into a spring roll, simultaneously completes the extraction and winding of the finger sleeve once, can not carry out low-level and high-level waste sectional treatment on the finger sleeve, and the complete spring roll is put into a waste storage container to cause the capacity increase of high-level waste storage.
Another type of extraction and treatment equipment commonly used at present is to directly extract the finger sleeve by using a traveling crane on an operation site and a long rod with an extraction clamp, and the extraction mode enables a high-radiation pollution section of the finger sleeve to be exposed to safe water depth, so that the emission of harmful radiation sources to the environment is caused, and the safety principle of emission minimization is violated. The long rod of the device is hung on a travelling crane at a working site, the travelling crane hook is about 24 meters away from the plane of a water pool, the long rod is hung by a steel wire rope (hook) of a travelling crane winch, the connection is flexible, the long rod is inevitably rocked, the long rod cannot be accurately positioned at the position of a finger sleeve to be extracted, and the biggest problem is that manual long-time operation and matching are needed.
In view of the above-described drawbacks of the prior art, the present inventors have devised. Through continuous research and experiments, the invention with practical value is finally created.
Disclosure of Invention
The invention aims to overcome the defect that the problem that a high-radiation pollution section cannot be completely positioned under the effective water depth for radiation shielding in the sleeve replacement process of a neutron fluence rate measurement system in the prior art, and provides the bending equipment in the water of the nuclear power station refueling water tank with a novel structure.
The invention further aims to provide bending equipment in water of a refueling pool of a nuclear power station, which aims to solve the technical problem of automatically moving and positioning the bending equipment in a three-dimensional space, so that the bending equipment is more practical.
The invention further aims to provide the bending equipment in the water of the refueling water tank of the nuclear power station, which aims to solve the technical problems of simple structure, convenient operation, improved working efficiency and cost saving, thereby being more suitable for practical use.
The invention also aims to provide the bending equipment in the water of the refueling water tank of the nuclear power station, which aims to solve the technical problem that the bending equipment is more suitable for replacing the neutron fluence rate measuring system indicating sleeve in the water tank of the nuclear power station (replacing the neutron fluence rate measuring system indicating sleeve from the top of the reactor pressure vessel) of each technical type, and can also introduce the design thought into other fields. Therefore, the method is more practical and has industrial utilization value.
The invention is characterized in that the invention is based on the characteristic that water can shield radiation when the conventional dose sharing operation mode cannot resist strong radiation of an operation site, and the invention completes extraction and recovery of the radioactive pollution sleeve in water in order to meet the requirements of safe and effective operation of the nuclear power station and the requirement of sleeve operation maintenance of a neutron fluence measuring system of a nuclear power unit. The method which is not the traditional technology and has high efficiency and cost saving is adopted while the safe operation requirement of the nuclear power equipment is ensured, and a solution is provided for the maintenance of the nuclear power station.
The aim of the invention and the technical problems are solved by adopting the following technical proposal. The invention provides a bending device in water of a nuclear power station refueling water tank, which comprises
The top steel wire rope control system provides power for the bending guide rod;
the bracket is used for installing the bending guide rod and the arc-shaped guide rail; the support, the arc guide rail and the bending guide rod form a bending device together, the support is a main body of the bending device, and the neutron measurement finger sleeve finishes bending in the support and stores the bending state temporarily in the support;
the bending guide rod is a positioning channel of an extraction clamp system and an active rod system for continuously extracting and bending neutron measurement finger sleeves, the bending guide rod and an arc-shaped guide rail form a kinematic pair, a winch of a top steel wire rope control system is used as a driving force, and bending and backing actions are completed when the neutron measurement finger sleeves are extracted;
the arc-shaped guide rail is welded in the bracket, and provides a bending track and a bending radian for the neutron measurement finger sleeve, so that the neutron measurement finger sleeve can be bent;
The guide plate is arranged at the initial 0-degree position of the arc-shaped guide rail, the guide plate and the arc-shaped guide rail are connected together at the position close to the bottom of the bracket, and the guide plate and the arc-shaped guide rail form a channel through which the neutron measurement finger sleeve smoothly enters the bent bracket and changes the extraction direction;
the extracting clamp system is arranged on the table top at the top end of the bending device and is a device for vertically lifting the neutron measurement finger sleeve, and comprises a winch and a long rod carrying an end actuating mechanism (extracting clamp), is a component for initially extracting the neutron measurement finger sleeve, can extract the neutron measurement finger sleeve from a pressure container according to a set length, and is still in a static state for clamping the head of the neutron measurement finger sleeve after the neutron measurement finger sleeve timely enters the bracket for bending;
the lifting guide rod is fixed on the fixing device;
the fixing device is fixed on a trolley of a crane of a nuclear power station refueling pool, the fixing device is connected with a bending support through a lifting guide rod, and the bending support is connected with the crane trolley through the fixing device to conduct extraction, positioning and movement of neutron measurement finger sleeves in a X, Y area, and simultaneously provides a rigid foundation for extraction and bending of the neutron measurement finger sleeves.
The object of the present invention and the solution to the technical problems thereof can be further achieved by the following technical measures.
The clamping device is arranged at the top end of the support, the clamping device, the bending guide rod and the extraction clamp system are arranged on the same vertical axis, the clamping device is matched with the neutron measurement guide rod to extract a certain position, the neutron measurement guide rod is clamped and fixed, a fulcrum is provided for the neutron measurement guide rod to extract the neutron measurement guide rod, the neutron measurement guide rod is clamped before bending begins, the neutron measurement guide rod is always clamped in the whole bending process of the neutron measurement guide rod, and the neutron measurement guide rod is loosened when the bending guide rod is retracted to the initial 0-degree position.
The device for bending the nuclear power station refueling water pool in water further comprises a roller straightening device, wherein the roller straightening device is arranged at the bottom end of the support, and is used for accurately positioning a neutron measurement finger sleeve in the extraction process and straightening and feeding the neutron measurement finger sleeve when the neutron measurement finger sleeve is retracted, so that the neutron measurement finger sleeve is ensured to smoothly enter the shearing device in a vertical state;
The bottom straightening hydraulic system is connected with the roller straightening device through a hydraulic pipe, provides power for left and right movement and rotation feeding for the roller straightening device, and uses water as a medium of the bottom straightening hydraulic system so as to prevent pollution caused by oil leakage of equipment in a refueling water tank of a nuclear power station.
The device for bending the nuclear power station refueling water tank in water can fix the bending device in the nuclear power station refueling water tank in water on various bearing structures, and the structure of the device does not change greatly, so that the device is a component with strong universality.
The device for bending the nuclear power station refueling water pool in water further comprises an anti-deformation pressing device, wherein the anti-deformation pressing device is arranged on the side face of the arc-shaped guide rail of the bracket; the anti-deformation pressing device is provided with an arc surface matched with the outer diameter of the neutron measurement finger sleeve, the top end of the anti-deformation pressing device is provided with a baffle plate, the baffle plate can control the neutron measurement finger sleeve to move left and right on the arc-shaped guide rail, and the anti-deformation pressing device can press the neutron measurement finger sleeve on the arc-shaped guide rail; when the bending guide rod swings, the upper part of the deformation-preventing pressing device (the swing frame drives to change) can generate a swing angle on the X-plane and the Y-plane of the arc-shaped guide rail along with the advance and the retraction of the neutron measurement finger sleeve, the neutron measurement finger sleeve is assisted to complete bending action along the arc-shaped guide rail, and meanwhile, the arching and deformation knotting of the neutron measurement finger sleeve in the bending and retraction process can be prevented, and the resistance of the neutron measurement finger sleeve in the retraction process is reduced and eliminated.
According to the bending equipment in the nuclear power station refueling water pool, the bending guide rod consists of the rotary connecting block, the long rod rectangular pipe, the lifting guide pressing plate and the rollback guide plate, wherein the rotary connecting block is arranged at the upper end of the long rod rectangular pipe, and the bending guide rod is fixed with the support on the support through the rotary connecting block; the lower end face of the long rod rectangular pipe is connected with a rollback guide plate, the side face of the lower part of the long rod rectangular pipe is connected with a lifting guide pressing plate, the lifting guide pressing plate can compress and guide the neutron measurement finger sleeve when bending, the rollback guide plate can compress and guide the neutron measurement finger sleeve when rolling back, and the bending guide rod can swing by 0-82 degrees in an X plane and a Z plane of the support around a hinge shaft on the support upper support.
The device for straightening the rollers in the nuclear power station refueling water pool in water comprises a plurality of compression rollers, a shell, a telescopic frame and a hydraulic cylinder, wherein the hydraulic cylinder is connected with a bottom straightening hydraulic system, the telescopic frame and the plurality of compression rollers are arranged in the shell, the telescopic frame is connected with the hydraulic cylinder, and the plurality of compression rollers are arranged on the telescopic frame.
The anti-deformation compressing device consists of a compressing wheel, a swinging frame, a rotating shaft, a spring, a fixing frame and a fixing shaft, wherein the fixing frame is fixed at the lower part of the fixing shaft, the rotating shaft is fixed at the middle part of the fixing shaft, and the swinging frame is fixed at the upper part of the fixing shaft; one end of the spring is connected with the lower end face of one end of the swinging frame, the other end of the spring is connected with the upper end face of one end of the fixing frame, the deformation-preventing pressing device can swing around the fixing shaft by 0-70 degrees, the pressing wheel is provided with an arc surface matched with the outer diameter of the neutron measurement finger tube sleeve, the top end of the pressing wheel is provided with a baffle plate, and the baffle plate can control the neutron measurement finger tube sleeve to deviate from the arc-shaped track.
According to the bending equipment in the nuclear power station refueling water tank, the support is a polygonal rigid welding frame.
According to the bending equipment in the nuclear power station refueling water pool, the arc shape of the arc-shaped guide rail welded on the support is matched with the bending radius of the neutron measurement guide sleeve, and the length of the arc-shaped guide rail is matched with the movement angle of the bending guide rod.
According to the bending equipment in the nuclear power station refueling water pool, constant gaps are kept among the lifting guide plate, the rollback guide plate and the surfaces of the arc-shaped guide rails of the bending guide rods, and the constant gaps ensure the accuracy of bending and rollback of the bending guide rods and the mounting positions of the arc-shaped guide rails in the bracket; the length of the bending guide rod is determined according to different bending radiuses and bending lengths.
According to the bending equipment in the nuclear power station refueling water pool, the radian of the guide plate is used for guaranteeing the minimum bending radius when the neutron measurement finger sleeve enters the bracket for bending, and the guide plate has a guide function when the neutron measurement finger sleeve retreats away from the bending equipment.
Compared with the prior art, the invention has obvious advantages and beneficial effects. It has at least the following advantages:
1. The invention relates to equipment with functions of bending, moving, shearing, sealing and the like in water. All the technological processes are finished underwater, so that the device is safe, reliable, simple in structure, accurate in extraction and positioning and easy to operate and overhaul.
2. The invention solves the problems that the neutron fluence rate measuring system of the reactor is capable of bending the finger sleeve in water, so that the high radiation pollution section of the finger sleeve can be subjected to radiation shielding in enough water depth, and meanwhile, the high, medium and low radiation pollution sections of the finger sleeve can be subjected to grading treatment and storage, thereby reducing the storage and treatment cost of radioactive wastes, maximally reducing the influence of radioactive substances on the environment, reducing the storage volume of the high radiation pollution wastes, providing the most excellent radiation protection working condition for finger sleeve replacement personnel, and simultaneously reducing the replacement cost of the finger sleeve.
3. The invention can change the vertical extraction direction of the finger sleeve by bending the finger sleeve in water in the process of replacing the finger sleeve of the neutron fluence measuring system, so that the high-lying section of the finger sleeve changes the extraction direction and shape in an area with about 1/4 circumference arc length, and the problem that the high-radiation pollution section of the finger sleeve is completely below the effective water depth for radiation shielding is solved. The invention fully utilizes the advantage of water on radiation shielding, reduces the radiation protection design of the structure, and meets the first requirement of safe operation of nuclear power equipment.
4. The invention adopts the bending guide rod and the arc guide rail to form a kinematic pair, and utilizes the winch as the driving force to extract the finger sleeve and simultaneously complete bending and retreating actions.
5. The invention can be fixed on a loading and reloading crane on a working site by utilizing the rigid connecting rod, and can move and accurately position in a three-dimensional space by means of digital control, thereby reducing the extraction, bending and shearing time of the finger sleeve and improving the maintenance and replacement efficiency of the finger sleeve.
6. The invention uses a simple winch (which is not installed underwater and is connected with the bending guide rod through the winch wire rope) as a drive, the bending guide rod as a driving roller, the arc-shaped guide rail as a bending die, and the invention realizes the process functions of bending, rollback, feeding, straightening and the like in water with a simple mechanical structure. The use of expensive waterproof electrical elements is reduced, and the cost performance is high.
7. According to the invention, a winch replaces part of the functions of the extraction clamp system, and the bending guide rod is used for extracting the high-level section of the neutron measurement finger sleeve, so that the friction force to the clamping jaw caused by the clamping of the extraction clamp and the extraction of the finger sleeve of an actuating mechanism in the extraction clamp system is reduced, and the service life of the clamp is prolonged.
8. The invention can be rigidly connected on the trolley of the loading and reloading crane of the nuclear power station through a fixing frame, and the precise positioning of the extracting finger sleeve is realized by utilizing the rigid connection and the motion precision of the loading and reloading crane.
9. The invention uses the winch to replace the extraction clamp system to provide power for the bending process of the finger sleeve, reduces the on-line working time of the extraction clamp system (used for clamping and extracting when the finger sleeve is initially extracted from the pressure vessel) by about 50 percent, and prolongs the service life of the extraction clamp. The problem of the complicated structure that uses when using extraction clamp to draw the dactylotheca pipe to bend is solved.
The foregoing description is only an overview of the present invention, and is intended to be implemented in accordance with the teachings of the present invention, as well as the preferred embodiments thereof, together with the following detailed description of the invention given in conjunction with the accompanying drawings.
Drawings
FIG. 1 is a schematic diagram of the combined structure of the present invention.
There is shown an assembly view of a bending device in the water of a nuclear power plant refueling water pond according to one embodiment of the present invention.
Fig. 2 is a schematic view of the initial position of the bend of the present invention.
The drawing shows a schematic diagram of the initial position of the extraction clamp system 2 in fig. 1 when the bending guide rod 8 starts to extract the neutron measurement finger sleeve 14 upwards and moves after the neutron measurement finger sleeve 14 reaches the bending size requirement. The clamping device 7 at the top of the support 9 should clamp the neutron measurement finger sleeve, and the lifting rod clamp of the extraction clamp system 2 keeps the function of vertically clamping the neutron measurement finger sleeve 14, and the continuous extraction of the neutron measurement finger sleeve is carried out by the bending guide rod 8.
Fig. 3A is a schematic view of the bending limit position of the present invention.
The figure shows a schematic view when bending the guide rod 8 to extract neutron measurement finger sleeve 14 and simultaneously complete bending and reach the limit positions of finger sleeve extraction and bending, and the guide rod 8 is at the 82-degree position.
Fig. 3B is a schematic structural diagram of the a-direction tightening device in fig. 3A.
The direction of movement of the movable end of the clamping device 4 is shown.
FIG. 4A is an initial schematic of neutron measurement finger sleeve rollback alignment.
The initial schematic of the bending guide bar 8 driving the finger sleeve 14 to begin to retract and straighten is shown.
Fig. 4B is a schematic diagram of a neutron measurement finger sleeve rollback alignment process.
The figure shows a schematic view of the finger sleeve 14 entering the roller straightening device 13 through the guide plate 12 and entering the shearing device after roller straightening under the auxiliary compression of the deformation-preventing compression device 10 in the retraction process.
Fig. 5 is a schematic view of the structure of the bending guide bar of the present invention.
Fig. 6A is a schematic elevational view of the roller straightening device of the present invention.
The roller straightening device 13 is shown in an uncoupled state.
Fig. 6B is a schematic view of the structural operation of the roller straightening device according to the present invention.
The roller straightening device 13 is shown in a straightening operating state.
Fig. 7 is a structural view of the deformation preventing pressing device of the present invention.
Wherein:
1: top wire rope control system 2: extraction clamp system
3: bottom alignment hydraulic system 4: fixing device
5: lifting guide rod 6: wire rope
7: clamping device 8: bending guide rod
8-1: rotating the connecting block 8-2: rectangular tube with long rod
8-3: wire rope fixed ring 8-4: lifting guide pressing plate
8-5: rollback guiding pressing plate
9: support 10: anti-deformation compacting device
10-1: pinch roller 10-2: swing frame
10-3: turning to shaft 10-4: spring
10-5: fixing frame 10-6: fixed shaft
11: arcuate guide rail 12: guide plate
13: roller straightening device
13-1, press roller 13-2: outer casing
13-3: telescoping rack 13-4: hydraulic cylinder
14: neutron measurement fingerstall 15: extraction clamp
Detailed Description
In order to further describe the technical means and effects adopted by the invention to achieve the preset aim, the following detailed description refers to the specific implementation, structure, characteristics and effects of the bending equipment in the water of the refueling water tank of the nuclear power station according to the invention by combining the accompanying drawings and the preferred embodiment.
The following describes in detail an embodiment of the present invention, and as shown in fig. 1, the bending device in water of a refueling water tank of a nuclear power station according to a preferred embodiment of the present invention mainly includes: the device comprises a top steel wire rope control system 1, an extraction clamp system 2, a bottom straightening hydraulic system 3, a fixing device 4, a lifting guide rod 5, a steel wire rope 6, a clamping device 7, a bending guide rod 8, a bracket 9, an anti-deformation pressing device 10, an arc-shaped guide rail 11, a guide plate 12, a roller straightening device 13 and a neutron measurement finger sleeve 14.
In the embodiment of the invention, the top wire rope control system 1 provides power for the bending guide bar 8.
The extraction clamp system 2 is arranged on the table top at the top end of the bending device and is a device for vertically lifting the neutron measurement finger sleeve 14. The extracting clamp system 2 comprises a winch and a long rod carrying an end effector clamp, is a component for initially extracting the neutron measurement fingerstall 14, can extract the neutron measurement fingerstall 14 from a pressure container according to a set length, and is still in a static state for clamping the head of the neutron measurement fingerstall 14 after the neutron measurement fingerstall 14 timely enters the bracket 9 to be bent.
And a lifting guide rod 5 fixed on the fixing device 4. The fixing device 4 is fixed on a trolley of a nuclear power station refueling pool crane, the fixing device 4 is connected with the bending support 9 through the lifting guide rod 5, the bending support 9 is connected with the crane trolley through the fixing device 4 to conduct extraction, positioning and movement of the neutron measurement finger sleeve 14 in a X, Y area, and meanwhile a rigid foundation is provided for extraction and bending of the neutron measurement finger sleeve 14. The fixing device 4 can fix the bending device in the water of the refueling water tank of the nuclear power station on various bearing structures, and the structure of the bending device does not change greatly, so that the bending device is a component with strong universality.
In the present embodiment, the bracket 9 is a typical welded structure. During welding, the support 9 needs to ensure that the radial movement of the arc-shaped guide rail 11 and the lifting guide rod 5 is on a plane. The bracket 9 is not only a weight carrier of the arc-shaped guide rail 11 and the bending guide rod 8, but also a carrier for bending work, and must have necessary rigidity. The present design performs a finite element analysis of the stent 9.
In the embodiment shown in fig. 1, a bracket 9 is used for installing a bending guide rod 8 and an arc-shaped guide rail 11; the bracket 9, the arc-shaped guide rail 11 and the bending guide rod 8 jointly form a bending device, the bracket 9 is a main body of the bending device and is used for bending a neutron measurement finger sleeve 14, temporarily storing and retracting and preserving the bending state, temporarily storing the bending state in the bracket 9, and forming a bending channel by a guide plate 12, the arc-shaped guide rail 11 and the bending guide rod 8 which are arranged at the bottom of the bracket 9.
In the embodiment shown in fig. 1, the support 9 as the main body of the bending device can be rigidly connected with the fixing device 4 fixed on the field loading and unloading trolley through two lifting guide rods 5, and the accurate positioning of the bending device is realized by the trolley. The bracket 9 is fixed on the lifting guide rod 8 by bolts and pins.
According to a preferred embodiment of the invention, the support 9 is a polygonal rigid welded frame, and the curved guide rail 11 and the bending guide bar 8 are mounted on the support 9 to form a bending tool.
In the embodiment of the present invention, the design of the bending guide rod 8 is mainly based on the shape, structure and design of the neutron measurement thimble 14 to be extracted and bent, so that the length and other structural characteristics of the bending guide rod 8 are matched with the bending radius and length requirements to be finally obtained. The inner cavity of the bending guide rod 8 can be used for the lifting rod of the extraction clamp system to pass through, so that the accurate positioning channel of the neutron measurement finger sleeve 14 is extracted from the extraction clamp system 2 initially, and the active rod system for finishing the direction change of the neutron measurement finger sleeve 14 and continuing extraction and bending is also adopted, and therefore the extraction clamp system 2, the bending guide rod 8 and the clamping device 7 are ensured to be positioned on the same vertical axis when the neutron measurement finger sleeve 14 is extracted.
The upper end of the bending guide rod 8 is fixedly connected with the upper part of the bracket 9, the bending guide rod 8 is used for extracting a neutron measurement finger sleeve 14 to be bent and completing bending and retreating processes at the same time, the bending guide rod 8 and the arc-shaped guide rail 11 form a kinematic pair, and the winch of the top steel wire rope control system 1 is used as driving force to extract the neutron measurement finger sleeve 14 and complete bending and retreating actions at the same time. When the neutron measurement thimble 14 is lifted to a certain height by the extraction clamp system 2 (the height is to ensure that the high radiation pollution section of the thimble is all below 2 meters deep water), the neutron measurement thimble 14 extracted from the upper end of the bracket 9 is clamped by the clamping device 7 arranged at the top end of the bracket 9. The winch drives the bending guide rod 8 to move upwards along the arc-shaped guide rail 11, and the bending of the finger sleeve is completed while the neutron measurement finger sleeve 14 is extracted. The bending guide rod 8 finishes the alignment and vertical downward feeding of the neutron measurement finger sleeve 14 while finishing the retraction of the neutron measurement finger sleeve when moving downwards.
According to a preferred embodiment of the invention, the long rod of the bending guide rod 8 is a rectangular tube, the cavity of which is capable of allowing the lifting rod of the extraction clamp system 2 with the terminal extraction clamp 15 to pass through, so that the extraction clamp system 2, the bending guide rod 8 and the clamping device 7 are located on the same vertical axis when the neutron measurement thimble 14 is extracted.
According to a preferred embodiment of the present invention, as shown in fig. 5, the bending guide rod 8 is composed of a rotary connection block 8-1, a long rod rectangular tube 8-2, a lifting guide pressing plate 8-4 and a retraction guide plate 8-5, wherein the rotary connection block 8-1 is arranged at the upper end of the long rod rectangular tube 8-2, and the bending guide rod 8 is fixed with a support on the bracket 9 through the rotary connection block 8-1; the lower end face of the long rod rectangular tube 8-2 is connected with a rollback guide plate 8-5, the side face of the lower part of the long rod rectangular tube 8-2 is connected with a lifting guide pressing plate 8-4, the lifting guide pressing plate 8-4 can compress and guide neutron measurement finger sleeve 14 when bending, the rollback guide plate 8-5 can compress and guide neutron measurement finger sleeve 14 when rolling back, the bending guide rod is connected with a support in a support through a rotating connecting shaft, and can swing by 0-82 degrees in an X plane and a Z plane of the support 9 around a hinge shaft on the upper support of the support 9. Constant gaps are kept among the lifting guide plates 8-4, the retreating guide plates 8-5 and the surfaces of the arc-shaped guide rails 11 of the bending guide rods 8, and the constant gaps ensure the accuracy of the bending guide rods 8 in executing bending and retreating and the mounting positions of the arc-shaped guide rails 11 in the brackets 9; the bending guide rod 8 applies pressure to the neutron measurement finger sleeve while extracting the finger sleeve, so that the neutron measurement finger sleeve is bent along the track of the arc-shaped guide rail. The length of the bending guide rod 8 is determined according to different bending radiuses and bending lengths. The steel wire rope fixing ring 8-3 is used for connecting a winch steel wire rope and is welded on the bending guide rod 8.
As shown in fig. 5, the bottom of the bending guide rod 8 is designed with a lifting guide pressing plate 8-4 and a retraction guide plate 8-5. The lifting guide pressing plate 8-4 is used for pressing when the neutron measurement finger sleeve 14 is bent. The farther the portion pressed by the lifting guide pressing plate 8-4 moves along the arc-shaped guide rail 11, the longer the neutron measurement finger sleeve 14 is bent. The retraction guide plate 8-5 is used for compression and guiding of the neutron measurement thimble 14 as it is retracted.
As shown in fig. 1, 3A, 4B, 5, the bending guide bar 8 is connected to a support mounted on the bracket 9 by means of its own rotating connection assembly, the bending guide bar 8 being rotatable about the rotating connection assembly in a designed area, in the illustrated embodiment the movement area of the bending guide bar 8 being 0-82 °. However, the present invention is not limited thereto, and the bending guide rod 8 may change its own length and movement area according to the length of the part to be bent and the requirement of the bending site environment. However, the structure of the bending guide bar 8 can be standardized and can be used in common.
As shown in fig. 2, when the bending guide bar 8 is in the initial 0 ° position, the lifting bar of the extraction clamp system 2 is accurately positioned to the position of the neutron measurement thimble 14 to be extracted by the long bar rectangular tube of the bending guide bar 8. The lifting rod end effector of the extraction clamp system 2, the extraction clamp 15, grasps the neutron-finger sleeve 14 for vertical upward extraction movement. When the extracted length is such that the highly radioactive contaminated section of the neutron measurement fingerstall 14 is fully under shielding below 2 meters water depth, the clamping device 10 mounted on top of the support 9 clamps the neutron measurement fingerstall 14.
As shown in fig. 3A, the steel wire rope of the winch pulls the bending guide rod 11 to move upwards to be continuously extracted in the neutron measurement finger sleeve 14, and bends and moves to an 82-degree position along the arc-shaped guide rail 11. At this time, a part of the high-level section of the neutron measurement finger sleeve 14 is bent in the support 9, and a part of the straight section is left in the roller straightening device 13 at the bottom of the support 9 and in the water below the support 9, and the bent section in the support 9 and the straight section at the lower end of the support 9 are the high-radiation pollution sections of the neutron measurement finger sleeve 14. Because the bending device is installed under water deep enough, the highly radioactive contaminated section of neutron measurement pointer sleeve 14 can be protected from radiation under water.
Fig. 4A and 4B show a schematic view of the bending guide rod 8 gradually retreating from 82 °. The neutron measurement thimble 14 is moved from the reactor pressure vessel position to a nearby shearing device that shears the neutron measurement thimble 14 by the previous bending device (in which case the neutron measurement thimble 14 is temporarily stored in the cradle 9), this movement being accomplished by the crane at the job site.
After the bending device reaches the shearing position, the bending guide rod 8 starts to move back, in the moving process, the lifting winch and the back winch work together, the back neutron measurement finger sleeve 14 straightens the bending part of the neutron measurement finger sleeve 14 under the guidance of the guide plate 12 through the roller straightening device 13, and meanwhile, the neutron measurement finger sleeve 14 is fed smoothly into the shearing device to be sheared.
In one embodiment of the present invention, the arc-shaped guide rail 11 is designed to have a circular arc shape and length according to the shape and required bending length of the neutron measurement thimble 14, and functions as a bending die for the neutron measurement thimble 14. The arc shape of the arc-shaped guide rail 11 is matched with the bending radius of the neutron measurement finger sleeve 14, and the length of the arc-shaped guide rail 11 is matched with the movement angle of the bending guide rod 8.
The arc-shaped guide rail 11 is welded in the bracket 9, and the arc-shaped guide rail 11 provides a bending track and a bending radian for the neutron measurement finger sleeve 14, so that the neutron measurement finger sleeve 14 can be bent.
By performing simulation experiments on neutron measurement finger sleeve 14 to be bent, the welding position of arc guide rail 11 on bracket 9, the gap between arc guide rail 11 and bending guide rod 8, and the driving power of the winch can be checked and detected.
As shown in fig. 1, in one embodiment of the present invention, a guide plate 12 is disposed at an initial 0 ° position of the arc-shaped guide rail 11, and the guide plate 12 is connected to the arc-shaped guide rail 11 near the bottom of the bracket 9, and the guide plate 12 and the arc-shaped guide rail 11 together form a channel through which the neutron measurement finger sleeve 14 smoothly enters the bent bracket 9 and changes the extraction direction. The cambered surface of the guide plate 12 is the same as the minimum bending radian of the neutron measurement finger sleeve 14, and is used for ensuring the minimum bending radius when the neutron measurement finger sleeve 14 enters the bracket 9 for bending. The guide plate 12 is used to ensure that the smallest bend radius is at the exit of the bending device when extracting the neutron measurement thimble 14 and has a guide function when the neutron measurement thimble 14 enters the bending device and retreats away from the bending device.
As shown in fig. 1, 3A, 4B and 7, in one embodiment of the present invention, the arc-shaped guide rail 11 is provided with an anti-deformation pressing device 10, which is capable of swinging around its fixed shaft and using spring force to achieve pressing during bending of the neutron measurement finger sleeve 14, and this pressing limits possible arching and loose joint generated when the neutron measurement finger sleeve 14 is bent, and controls the neutron measurement finger sleeve 14 to extract bending without departing from the arc-shaped rail 11.
The deformation-preventing pressing device 10 is arranged on the side surface of the arc-shaped guide rail 11 of the bracket 9; the anti-deformation pressing device 10 is provided with an arc surface matched with the outer diameter of the neutron measurement finger sleeve 14, the top end of the anti-deformation pressing device 10 is provided with a baffle plate, the baffle plate can control the neutron measurement finger sleeve 14 to move left and right on the arc-shaped guide rail 11, and the anti-deformation pressing device 10 can press the neutron measurement finger sleeve 14 on the arc-shaped guide rail 11; when the bending guide rod 8 swings, the upper part of the anti-deformation pressing device 10 (namely, the swinging frame 10-2 drives the pressing wheel 10-1 to change) can generate a swinging angle on the X and Y planes of the arc guide rail 11 along with the advancing and retreating of the neutron measurement finger sleeve 14, the neutron measurement finger sleeve 14 is assisted to complete the bending action along the arc guide rail 11, and meanwhile, the arching, deformation and knotting of the neutron measurement finger sleeve 14 in the bending and retreating processes can be prevented, and the resistance of the neutron measurement finger sleeve 14 in the retreating process is reduced and eliminated.
According to a preferred embodiment of the present invention, as shown in FIG. 7, the anti-deformation compressing device 10 is composed of a compressing wheel 10-1, a swing frame 10-2, a rotating shaft 10-3, a spring 10-4, a fixing frame 10-5 and a fixing shaft 10-6, the fixing frame 10-5 is fixed at the lower part of the fixing shaft 10-6, the rotating shaft 10-3 is fixed at the middle part of the fixing shaft 10-6, and the swing frame 10-2 is fixed at the upper part of the fixing shaft 10-6; one end of a spring 10-4 is connected with the lower end face of one end of the swinging frame 10-2, the other end of the spring 10-4 is connected with the upper end face of one end of the fixed frame 10-5, the deformation-preventing pressing device 10 can swing around a fixed shaft by 0-70 degrees, the pressing wheel 10-1 is provided with an arc face matched with the outer diameter of the neutron measurement finger tube sleeve 14, the top end of the pressing wheel 10-1 is provided with a baffle plate, and the baffle plate can control the neutron measurement finger tube sleeve 14 to deviate from the arc-shaped track 11.
In the embodiment of the present invention, as shown in fig. 6A and 6B, a roller straightening device 13 is designed at the bottom of the support 9, where the roller straightening device 13 is used to ensure that the tolerance of the motion track deviating from the axis when the neutron measurement finger sleeve 14 is extracted and retracted is kept within the range of the design allowable value, and at the same time, has a straightening function for the retraction process of the curved neutron measurement finger sleeve 14, so as to ensure that the neutron measurement finger sleeve 14 smoothly enters the shearing device in the vertical state. The roller straightening device 13 has two actions on the retracted neutron measurement finger sleeve 14, namely straightening, and feeding the neutron measurement finger sleeve 14 into a shearing device to shear the neutron measurement finger sleeve 14 according to the designed size, and then sealing and storing the neutron measurement finger sleeve 14 in a waste storage container. At this time, the windlass, the bending guide rod 8 and the roller straightening device 13 are all in a working state until the shearing device is in a working state.
According to the preferred embodiment of the present invention, as shown in fig. 6A and 6B, the roller straightening device 13 is composed of a plurality of press rollers 13-1, a housing 13-2, a telescopic frame 13-3 and a hydraulic cylinder 13-4. The hydraulic cylinder 13-4 is connected with the bottom straightening hydraulic system 3, the telescopic frame 13-3 and the compression rollers 13-1 are arranged in the shell 13-2, the telescopic frame 13-3 is connected with the hydraulic cylinder 13-4, and the compression rollers 13-1 are arranged on the telescopic frame 11-3.
In the embodiment of the invention, the bottom straightening hydraulic system 3 is connected with the roller straightening device 13 through a hydraulic pipe, the bottom straightening hydraulic system 3 provides power for the roller straightening device 13 to move left and right and feed in a rotating manner, and because equipment in a nuclear power station refueling water tank is not allowed to cause pollution caused by oil leakage, water is used as a medium of the bottom straightening hydraulic system 3.
The invention determines the optimal value of the roller compaction force when neutron measurement finger sleeve 14 is retracted through experimentation. The number of shears varies depending on the size of the neutron measurement finger sleeve 14 shears.
In the embodiment of the invention, the clamping device 7 is arranged at the top end of the bracket 9, the clamping device 7, the bending guide rod 8 and the extraction clamp system 2 are arranged on the same vertical axis, when the clamping device 7 is matched with the neutron measurement finger sleeve 14 to extract a certain position, the neutron measurement finger sleeve 14 is clamped and fixed, a fulcrum is provided for the bending guide rod 8 to extract the neutron measurement finger sleeve 14, the neutron measurement finger sleeve 14 is clamped before the bending begins, the neutron measurement finger sleeve 14 is always clamped in the whole bending process of the neutron measurement finger sleeve 14, and the neutron measurement finger sleeve 14 is released when the bending guide rod 8 is retracted to the initial 0 DEG position.
The invention is designed for the most critical maintenance equipment needed in the working area of the reactor of the nuclear power station, but can be expanded to other places needing bending in water for use.
The working principle is as follows:
1. the bending guide rod 8 carrying the neutron measurement finger sleeve 14 rotates around the support hinge shaft arranged on the support 9 under the drive of an external winch, and the neutron measurement finger sleeve 14 is extracted and simultaneously the neutron measurement finger sleeve 14 is bent along the arc-shaped guide rail 11. When the neutron measurement finger sleeve 14 is extracted and bent, the bent part is positioned on the arc-shaped guide rail 11 and is pressed by the lifting guide pressing plate 8-4. Therefore, the farther the portion pressed by the lift guide pressing plate 8-4 moves along the arc-shaped guide rail 11, the longer the neutron measurement pointer tube 14 is bent, and there is no limitation in space except for the reaction generated at the bending position of the neutron measurement pointer tube 14. The function of the anti-deformation pressing device 10 is to swing around the self structural shaft and to press the neutron measurement finger sleeve 14 in the bending process by using the spring 10-4, the pressing limits the arch and the slipknot which can be generated when the neutron measurement finger sleeve 14 is bent, and the neutron measurement finger sleeve 14 is controlled not to separate from the arc-shaped guide rail 11 in the bending process. Neutron measurement means that the sleeve 14 is controlled by a limiter to stop extraction and bending when bent to 82 degrees, see fig. 3.
2. The neutron measurement finger sleeve 14 is temporarily stored in the bracket after being bent, and the bracket 9 is moved to the finger sleeve shearing position by the loading and unloading crane.
3. In the shearing position, the bent guide rod 8 moves downward to retract the neutron measurement thimble, see FIG. 4. In order to enable the neutron measurement finger sleeve to smoothly enter the shearing equipment, the neutron measurement finger sleeve 14 temporarily stored in the bending support 9 needs to be on the same vertical line with the shearing opening of the shearing device. The neutron measurement finger sleeve 14 is in a bending state before retreating, the neutron measurement finger sleeve 14 is straightened during retreating, and the neutron measurement finger sleeve 14 enters a shearing process after being straightened by a roller straightening device 13 (see fig. 6) arranged at the bottom of the support 9.
4. The arc-shaped guide rail 11 arranged in the bracket 9 is designed according to the shape and the required bending length of the neutron measurement finger sleeve 14 and plays a role of a neutron measurement finger sleeve bending die.
5. The length and structure of the bending guide rod 8 can be designed in advance according to the shape and structure of the neutron measurement finger sleeve to be extracted and bent, so that the length and other structural characteristics of the bending guide rod 8 are matched with the bending radius and length requirements to be finally obtained.
6. Neutron measurement means that the design of the extraction length and bending radius of the thimble 14 needs to satisfy two conditions:
(1) Neutron measurement means that the highly radioactive contaminated section of the sleeve must always be below 2 meters deep in water.
(2) The bending device has the advantages that the structure meets the bending rigidity requirement, and the weight cannot exceed the load requirement of the loading and reloading crane.
7. When bending is implemented, the bending device is required to be rigidly connected to the loading and unloading trolley, an extraction clamp system 2 provided with an end actuating mechanism (clamp) is used (a lifting rod of the extraction clamp system 2 vertically passes through a bending guide rod 8, see figure 2, a neutron measurement finger sleeve 14 arranged in a reactor pressure vessel is vertically extracted to a position required for bending, a clamping device 7 positioned at the top of a bracket 9 clamps the neutron measurement finger sleeve 14, and the bending guide rod 8 completes the neutron measurement finger sleeve 14 extraction and bending composite movement in a 0-82 DEG region, see figure 3.
After bending, the bending guide rod 8 drives the neutron measurement finger sleeve 14 to move back along the arc-shaped guide rail 11, and the neutron measurement finger sleeve 14 is straightened through the roller straightening device 13 while backing back, as shown in fig. 6. The aligned neutron measurement pointer sleeve 14 enters a shearing device connected to the waste container to complete shearing and containment.
8. Repeating the above process flow, and continuing to extract, bend, shear and seal the other multiple finger sleeves.
The present invention is not limited to the above-mentioned embodiments, but is intended to be limited to the following embodiments, and any modifications, equivalents and modifications can be made to the above-mentioned embodiments without departing from the scope of the invention.

Claims (9)

1. The utility model provides a nuclear power station reload pond aquatic equipment of bending which characterized in that includes
The top steel wire rope control system (1) provides power for the bending guide rod (8);
the bracket (9) is used for installing the bending guide rod (8) and the arc-shaped guide rail (11); the support (9), the arc-shaped guide rail (11) and the bending guide rod (8) form a bending device together, the support (9) is a main body of the bending device, and the neutron measurement finger sleeve (14) finishes bending in the support (9) and stores a bending state temporarily in the support (9);
The bending guide rod (8) consists of a rotary connecting block (8-1), a long rod rectangular pipe (8-2), a lifting guide pressing plate (8-4) and a rollback guide plate (8-5), wherein the rotary connecting block (8-1) is arranged at the upper end of the long rod rectangular pipe (8-2), and the long rod rectangular pipe (8-2) is fixed with a support on the support (9) through the rotary connecting block (8-1); the lower end face of the long rod rectangular tube (8-2) is connected with a rollback guide plate (8-5), the side face of the lower part of the long rod rectangular tube (8-2) is connected with a lifting guide pressing plate (8-4), the lifting guide pressing plate (8-4) can compress and guide a neutron measurement finger sleeve (14) when bending, the rollback guide plate (8-5) can compress and guide the neutron measurement finger sleeve (14) when rolling back, and the bending guide rod (8) can swing by 0-82 degrees in an X plane and a Z plane of a bracket (9) around a hinge shaft on a support of the bracket (9);
the bending guide rod (8) is used for extracting neutron measurement finger sleeves (14) to be bent and completing bending and backing processes at the same time, the bending guide rod (8) is used for extracting a positioning channel of a clamp system (2) and is a driving rod system for continuously extracting and bending the neutron measurement finger sleeves (14), the bending guide rod (8) and an arc-shaped guide rail (11) form a kinematic pair, a winch of a top steel wire rope control system (1) is used as a driving force, and bending and backing actions are completed when the neutron measurement finger sleeves (14) are extracted;
The anti-deformation compressing device (10) is arranged on the side face of the arc-shaped guide rail (11) of the bracket (9); the anti-deformation pressing device (10) is provided with an arc surface matched with the outer diameter of the neutron measurement finger sleeve (14), the top end of the anti-deformation pressing device (10) is provided with a baffle plate, the baffle plate can control the neutron measurement finger sleeve (14) to move left and right on the arc-shaped guide rail (11), and the anti-deformation pressing device (10) can press the neutron measurement finger sleeve (14) on the arc-shaped guide rail (11); when the bending guide rod (8) swings, the upper part of the deformation-preventing pressing device (10) can generate a swinging angle on the X and Y planes of the arc guide rail (11) along with the advancing and retreating of the neutron measurement finger sleeve (14), the neutron measurement finger sleeve (14) is assisted to complete bending action along the arc guide rail (11), and meanwhile, the arching, deformation and knotting of the neutron measurement finger sleeve (14) in the bending and retreating processes can be prevented, and the resistance of the neutron measurement finger sleeve (14) in the retreating process is reduced and eliminated;
the anti-deformation compressing device (10) consists of a compressing wheel (10-1), a swinging frame (10-2), a rotating shaft (10-3), a spring (10-4), a fixing frame (10-5) and a fixing shaft (10-6), wherein the fixing frame (10-5) is fixed at the lower part of the fixing shaft (10-6), the rotating shaft (10-3) is fixed at the middle part of the fixing shaft (10-6), and the swinging frame (10-2) is fixed at the upper part of the fixing shaft (10-6); one end of the spring (10-4) is connected with the lower end face of one end of the swinging frame (10-2), the other end of the spring (10-4) is connected with the upper end face of one end of the fixing frame (10-5), the deformation-preventing pressing device (10) can swing around the fixing shaft by 0-70 degrees, the pressing wheel (10-1) is provided with an arc face matched with the outer diameter of the neutron measurement finger sleeve (14), the top end of the pressing wheel (10-1) is provided with a baffle plate, and the baffle plate can control the neutron measurement finger sleeve (14) to deviate from the arc guide rail (11);
The arc-shaped guide rail (11), the arc-shaped guide rail (11) is welded in the bracket (9), the arc-shaped guide rail (11) provides a bending track and a bending radian for the neutron measurement finger sleeve (14), and the neutron measurement finger sleeve (14) can be bent;
the guide plate (12) is arranged at the initial 0-degree position of the arc-shaped guide rail (11), the guide plate (12) is connected with the arc-shaped guide rail (11) at the bottom close to the bracket (9), and the guide plate (12) and the arc-shaped guide rail (11) form a channel through which the neutron measurement finger sleeve (14) smoothly enters the bent bracket (9) and changes the extraction direction;
the extracting clamp system (2) is arranged on the table top at the top end of the bending device and is a device for vertically lifting the neutron measurement finger sleeve (14), the extracting clamp system (2) comprises a winch and a long rod carrying an end actuating mechanism, is a component for initially extracting the neutron measurement finger sleeve (14), can extract the neutron measurement finger sleeve (14) from a pressure container according to a set length, and is still in a static state for clamping the tube head of the neutron measurement finger sleeve (14) after the neutron measurement finger sleeve (14) timely enters the bracket (9) to be bent;
the lifting guide rod (5) is fixed on the fixing device (4);
the fixing device (4) is fixed on a trolley of a nuclear power station refueling pool crane, the fixing device (4) is connected with the bracket (9) through the lifting guide rod (5), and the bracket (9) is connected with the crane trolley through the fixing device (4) to perform extraction, positioning and movement of the neutron measurement finger sleeve (14) in a X, Y area, and simultaneously provides a rigid foundation for extraction and bending of the neutron measurement finger sleeve (14).
2. The bending equipment in the nuclear power station refueling pool water according to claim 1, further comprising a clamping device (7), wherein the clamping device (7) is arranged at the top end of the bracket (9), the clamping device (7) is on the same vertical axis with the bending guide rod (8) and the extraction clamp system (2), the clamping device (7) clamps and fixes the neutron measurement guide sleeve (14) when being matched with the neutron measurement guide sleeve (14) to extract a certain position, the neutron measurement guide sleeve (14) is provided with a fulcrum for extracting the neutron measurement guide sleeve (14) by the bending guide rod (8), the neutron measurement guide sleeve (14) is clamped before bending begins, the neutron measurement guide sleeve (14) is clamped all the time in the whole bending process of the neutron measurement guide sleeve (14), and the neutron measurement guide sleeve (14) is released when the bending guide rod (8) is retracted to an initial 0 DEG position.
3. The bending equipment in water of the nuclear power station refueling pool according to claim 1, further comprising a roller straightening device (13), wherein the roller straightening device (13) is arranged at the bottom end of the bracket (9), and the roller straightening device (13) is used for accurately positioning a neutron measurement finger sleeve (14) in the extraction process and straightening and feeding the neutron measurement finger sleeve (14) when the neutron measurement finger sleeve (14) is retracted, so that the neutron measurement finger sleeve (14) smoothly enters the shearing device in a vertical state;
The hydraulic device is characterized by further comprising a bottom straightening hydraulic system (3), wherein the bottom straightening hydraulic system (3) is connected with the roller straightening device (13) through a hydraulic pipe, the bottom straightening hydraulic system (3) provides power for the roller straightening device (13) to move left and right and rotationally feed, water is used as a medium of the bottom straightening hydraulic system (3), and pollution caused by oil leakage of equipment in a nuclear power station refueling pool is prevented.
4. The bending equipment in the water of the refueling water tank of the nuclear power station according to claim 1, wherein the fixing device (4) can fix the bending equipment in the water of the refueling water tank of the nuclear power station on various bearing structures without greatly changing the structure of the bending equipment.
5. A nuclear power station refueling pool water bending apparatus as recited in claim 3, wherein the roller straightening device (13) is composed of a plurality of press rollers (13-1), a housing (13-2), a telescopic frame (13-3) and a hydraulic cylinder (13-4), the hydraulic cylinder (13-4) is connected with the bottom straightening hydraulic system (3), the telescopic frame (13-3) and the plurality of press rollers (13-1) are arranged in the housing (13-2), the telescopic frame (13-3) is connected with the hydraulic cylinder (13-4), and the plurality of press rollers (13-1) are arranged on the telescopic frame (13-3).
6. The nuclear power plant refueling pool in-water bending apparatus as claimed in claim 1, wherein the bracket (9) is a polygonal rigid welded frame.
7. The bending equipment in water of a refueling pool of a nuclear power station according to claim 1, wherein the arc shape of the arc-shaped guide rail (11) welded on the bracket (9) is matched with the bending radius of the neutron measurement finger sleeve (14), and the length of the arc-shaped guide rail (11) is matched with the movement angle of the bending guide rod (8).
8. The bending equipment in the water of the refueling pool of the nuclear power station according to claim 1, wherein constant gaps are kept between the lifting guide pressing plate (8-4) of the bending guide rod (8) and the surface of the arc-shaped guide rail (11) and between the retreating guide plate (8-5) and the surface of the arc-shaped guide rail (11), and the constant gaps ensure the precision of the bending guide rod (8) for executing bending, retreating and installing the arc-shaped guide rail (11) in the bracket (9); the length of the bending guide rod (8) is determined according to different bending radiuses and bending lengths.
9. The bending equipment in the water of the refueling pool of the nuclear power station according to claim 1, wherein the radian of the guide plate (12) is used for ensuring the minimum bending radius when the neutron measurement finger sleeve (14) enters the bracket (9) for bending, and has a guiding function when the neutron measurement finger sleeve (14) is retracted out of the bending equipment.
CN201811153078.1A 2018-09-29 2018-09-29 Bending equipment in nuclear power station refueling pool water Active CN109262267B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201811153078.1A CN109262267B (en) 2018-09-29 2018-09-29 Bending equipment in nuclear power station refueling pool water

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201811153078.1A CN109262267B (en) 2018-09-29 2018-09-29 Bending equipment in nuclear power station refueling pool water

Publications (2)

Publication Number Publication Date
CN109262267A CN109262267A (en) 2019-01-25
CN109262267B true CN109262267B (en) 2023-07-28

Family

ID=65196210

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201811153078.1A Active CN109262267B (en) 2018-09-29 2018-09-29 Bending equipment in nuclear power station refueling pool water

Country Status (1)

Country Link
CN (1) CN109262267B (en)

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1155256A (en) * 1966-06-03 1969-06-18 Smeralovy Zd Y Narodni Podnik Improvements in or relating to Plate Bending Machines.
AT393639B (en) * 1990-03-15 1991-11-25 Lift Verkaufsgeraete Gmbh SHEET BENDING DEVICE
DE502004004723D1 (en) * 2004-04-06 2007-10-04 Trumpf Maschinen Austria Gmbh Bending tool for bending workpieces, in particular sheets and bending machine with such a bending tool
NZ564570A (en) * 2007-12-18 2010-02-26 Scott Technology Ltd Metal folding apparatus
CN102049439B (en) * 2010-09-30 2012-08-29 黄伟明 Pipe bending machine integrating straightening, cutting and three-dimensional numerical control pipe bending functions
CN103433338B (en) * 2013-08-20 2015-04-01 蚌埠通达汽车零部件有限公司 Numerical control metal plate coiling machine
CN103658250A (en) * 2013-12-18 2014-03-26 郑子姣 Automatic synchronization bending machine
CN106975928B (en) * 2017-05-04 2022-12-20 浙江钲浩建筑科技有限公司 Bending and welding combined device
CN107695682B (en) * 2017-10-27 2024-03-12 东莞市健耀烨电子科技有限公司 Machine for improving automatic feeding bending efficiency
CN209453129U (en) * 2018-09-29 2019-10-01 青岛先楚能源发展集团有限公司 Bending equipment in nuclear power station refuelling pool water

Also Published As

Publication number Publication date
CN109262267A (en) 2019-01-25

Similar Documents

Publication Publication Date Title
CN104084948B (en) A kind of lid robot of Kaifeng automatically
US4788028A (en) Machine and method for handling a nuclear fuel assembly
EP2957394A1 (en) Remote operation manipulator
KR101534675B1 (en) Remote dismantling robotic system for decommissioning nuclear reactor pressure vessel
CN111617974A (en) Movable radioactive waste sorting device and using method thereof
CN109262267B (en) Bending equipment in nuclear power station refueling pool water
CN110444304A (en) A kind of nuclear power station In-core Instrumentation instrument replaces system and method under water
US8811565B2 (en) Integrated reactor missile shield and crane assembly
CN205122210U (en) Filter core transfer device
US20150321299A1 (en) Water jet peening device
CN209453129U (en) Bending equipment in nuclear power station refuelling pool water
US5084231A (en) Cylindrical refueling mast with longitudinal guide grooves
CN204545179U (en) Mechanical composite tube Full-automatic bushing device
CN112489838A (en) Extraction equipment and method for nuclear detection instrument assembly of reactor core
CN112259266B (en) Shielding structure and shielding system for dismantling reactor detector assembly and using method
CN217239054U (en) Remote installation tool for irradiation monitoring pipe of reactor pressure vessel of nuclear power plant
CN112259267B (en) Nuclear reactor detector assembly removal device
CN104492986A (en) Fully-automatic tube sleeving device for mechanical composite tube
CN214175701U (en) Extraction equipment for nuclear detection instrument assembly of reactor core
CN103925412A (en) Cable tray structure for nuclear power plant reactor top cable arrangement
CN102486943A (en) Automatic shifting platform for welding inspection of adapter of pressure vessel
JPS6116038B2 (en)
CN201886790U (en) Automatic shifting platform for welding inspection of adapter of pressure vessel
RU2569334C1 (en) Pick-and-place device for installation and extraction from reactor of lengthy equipment
CN111477371A (en) Pressure vessel top cover and in-pile component guiding device and hoisting method

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant
TR01 Transfer of patent right
TR01 Transfer of patent right

Effective date of registration: 20230828

Address after: 266000 Electronic Production and Assembly Plant, No. 88 Huanghe West Road, Huangdao District, Qingdao, Shandong Province

Patentee after: ZHONGWU XIANCHU NUCLEAR ENERGY TECHNOLOGY Co.,Ltd.

Address before: 266000 Floor 26, No. 5, Donghai West Road, Shinan District, Qingdao, Shandong

Patentee before: QINGDAO XIANCHU ENERGY DEVELOPMENT GROUP CO.,LTD.