CN112489838A - Extraction equipment and method for nuclear detection instrument assembly of reactor core - Google Patents

Abstract

The invention belongs to the technical field of nuclear power station operation and maintenance. The invention provides a device and a method for extracting a reactor core detection instrument assembly, aiming at the problem that the existing extraction tool of the reactor core detection instrument assembly is restricted by the length of the instrument assembly and the environmental radiation dose exceeds the standard in the extraction process. The extraction process comprises the steps of descending the clamp, grabbing the target IITA component by the clamp, lifting the clamp, clamping by the clamping roller, bending the IITA component, winding, extracting and returning for shearing. The length range of the instrument assembly capable of being extracted through the extraction equipment is larger, the irradiation dose risk can be effectively avoided, the equipment is flexible to move, and the extraction positioning is accurate.

Description

Extraction equipment and method for nuclear detection instrument assembly of reactor core

Technical Field

The invention belongs to the technical field of nuclear power station operation and maintenance, and particularly relates to extraction equipment and method for a nuclear detection instrument assembly of a reactor core.

Background

The replacement of the nuclear instrumentation of the reactor core is a necessary process flow for daily operation and maintenance of the nuclear power station, and the replacement flow mainly comprises extraction and encapsulation of a target nuclear instrumentation component (IITA component) of the reactor core and installation of a new IITA component. The core requirements of the nuclear power station on the IITA component extraction tool mainly comprise the following 4 points: 1. the equipment is convenient to install and does not influence the existing equipment in the containment; 2. the target IITA component to be replaced can be accurately positioned and grabbed; 3. radiation protection is optimized, so that an operator is prevented from being influenced by radiation extracted from the activated IITA component; 4. the follow-up packaging scheme can be matched to effectively package the extracted target IITA component, and the volume reduction treatment requirement of the radioactive waste is met.

At present, two common IITA component extraction and processing tools exist in the nuclear power field. A dry (non-underwater) winding device uses a closed metal container with a radiation shielding function, and an IITA component is drawn out and wound into a spring coil by using the spring mechanical forming principle in the container. In order to meet the requirement of shielding radiation, the wall thickness of the self-contained container is more than or equal to 360mm, and the overall weight of the self-contained container is about 16.2T. The equipment can not automatically move in a three-dimensional space, the IITA component to be taken out is accurately positioned, the IITA component needs to be manually extracted from the reactor pressure vessel and sent into the winding equipment, and personnel face the danger that the radiation dose exceeds a safe specified value when the IITA component is extracted and sent. This solution has two major drawbacks. Firstly, the method comprises the following steps: the target IITA component cannot be autonomously positioned, and manual assistance is needed when the work starts; secondly, the method comprises the following steps: the operation personnel can not be protected from being influenced by radiation, and the environmental radiation dose can exceed the standard in the extraction process.

Another extraction tool commonly used is a long-rod tool with clamps, using a job-site loop crane as extraction power. And (3) manually operating the long rod tool, directly extracting the IITA components after the front section clamp grabs the IITA components, and vertically extracting the whole IITA components. The extraction mode is influenced by the length of the IITA component (the length of a single IITA component is more than or equal to 10m, and the depth of a shielding water pool is about 8m), and the problem that the radiation dose of the working environment of an operator exceeds the standard due to the fact that a high radiation section of the IITA component is exposed out of a shielding water layer exists. Meanwhile, in the process of extracting the IITA component by the clamp type extracting tool, obvious lateral force can be generated, and abrasion is caused to the connecting part of the installation guide pipe of the IITA component. This solution also has three major drawbacks. Firstly, the method comprises the following steps: because the whole IITA component is vertically pulled out and limited by the depth of a shielding water layer, the risk that part of the IITA component activation section is exposed out of the water surface exists, and operators cannot be protected from radiation; secondly, the method comprises the following steps: the connecting part of the IITA component installation guide pipe cannot be replaced, and permanent damage can be caused after abrasion; thirdly, the method comprises the following steps: after the whole IITA component is extracted, the subsequent packaging process is very difficult for the IITA component with a single length of more than 10 m.

Disclosure of Invention

The invention provides a device and a method for extracting a nuclear detection instrument assembly of a reactor, aiming at the problem that the environmental radiation dose exceeds the standard in the extraction process because the existing extraction tool of the nuclear detection instrument assembly of the reactor is restricted by the length of the instrument assembly. The length range of the instrument assembly that this extraction equipment can extract is bigger, and can effectively avoid the irradiation dose risk to can realize fixing a position and returning and tell the IITA subassembly of taking out.

The invention is realized by the following technical scheme:

a kind of reactor core nuclear detection instrument assembly draw-out equipment, including clamp and its aqueous medium hydraulic drive system, hoist engine, draw-out device, keep in the tube, braced frame and link frame;

the supporting frame is vertically arranged, the top of the supporting frame is fixedly provided with a connecting frame, the top of the connecting frame is provided with a lifting appliance, the side part of the connecting frame is provided with a sliding connection assembly, and the sliding connection assembly is in sliding connection with a fence of the nuclear fuel refueling machine; a winch and a driving motor are arranged in the connecting frame, a rope of the winch is fixedly connected with the clamp, and the clamp is driven to open or close by a water medium hydraulic driving system;

a winch rope guide frame, a winch coder and a tension meter are arranged in the supporting frame, and a rope of the winch passes through the coder and the tension meter and is lifted and lowered along the length direction of the supporting frame;

the bottom of the supporting frame is fixedly provided with an extraction device, the extraction device comprises an extraction shell, a clamping roller, a driving roller, a bending roller and a straightening roller, and the hydraulic cylinder group is arranged in the extraction shell; the upper end and the lower end of the extraction shell are oppositely provided with guide openings, the driving roller and the clamping roller are oppositely arranged at the bottom of the extraction shell, a channel for an IITA component to pass through is reserved between the driving roller and the clamping roller, and the bending roller is arranged above the extraction shell; the straightening roller is arranged between the bending roller and the clamping roller;

the output end of the driving motor is connected with a rotating shaft of the driving roller through a transmission shaft assembly to drive the driving roller to rotate forwards and backwards, and a motor encoder is further arranged on the driving motor; the hydraulic cylinder group comprises a plurality of hydraulic cylinders which respectively drive the clamping roller, the bending roller and the straightening roller to be close to or far away from the IITA component in the horizontal direction;

the temporary storage barrel is arranged on one side of the extraction shell, and the diameter of the temporary storage barrel is matched with the bending angle of the bending roller.

Further, the sliding connection assembly is a connecting support arranged on the side portion of the connecting frame, fixed rollers are arranged on the connecting support, the distance between the fixed rollers is adjustable, a fence of the nuclear fuel refueling machine is arranged between the fixed rollers, the distance between the fixed rollers is adjusted, and the connecting frame is connected to the fence and can move along the fence.

Furthermore, a rope guide frame is further arranged in the supporting frame, and the rope of the winch is arranged in the rope guide frame.

Further, the clamp is a long rod type clamp.

Further, a guide plate is arranged on the temporary storage cylinder and is arranged below the winding starting position of the IITA component.

Further, a torque limiter is installed at the output end of the driving motor.

Further, the hydraulic system also comprises a hydraulic pump station, and the hydraulic cylinder groups are respectively connected to the hydraulic pump station; and the water medium hydraulic driving system of the clamp is integrated in the hydraulic pump station.

Furthermore, the device also comprises an electric control cabinet and a handheld control console.

The invention also provides a method for extracting the nuclear detection instrument assembly of the reactor core, which comprises the following steps:

step (1), descending a clamp: moving the extraction apparatus of claim 1 over the target instrumentation assembly using the lifting device, the clamp lowering through the extraction device to directly over the IITA assembly;

step (2), the clamp grabs the target IITA component: after the clamp is aligned with the position of the electric connector end of the target IITA component, the clamp is opened, descended and then closed to finish the grabbing action;

and (3) lifting the clamp: starting a winch to lift the clamp, vertically and upwardly withdrawing the target IITA component, and stopping withdrawing after the clamp is lifted to a specified height;

clamping rollers: starting a clamping roller hydraulic cylinder under the condition that the clamp is not loosened, pushing the clamping roller and the driving roller to clamp the extracted IITA component, and opening the clamp and lifting the clamp upwards to the IITA component to be completely separated from the clamp;

and (5) bending the IITA component: starting a bending hydraulic cylinder, pushing a bending roller forward, and pushing an IITA component to bend towards the inlet direction of the temporary storage cylinder;

and (6) winding and extracting: starting a driving motor to drive a driving roller to rotate, wherein under the action of the driving roller and a clamping roller, the IITA component is drawn out from the reactor, forms a circumference and is wound on a temporary storage cylinder under the action of a bending roller, and after the target IITA component is completely drawn out from the reactor, the drawing process is finished;

and (7) spit-back shearing: the equipment is moved above a shearing tool by using hoisting equipment, a collecting barrel is arranged below the shearing tool, the tail part of the extracted IITA component is aligned to the shearing tool, a driving roller is started and rotates reversely, the IITA component is spit back, the spit back process is linked with shearing action, the rotation angle of the driving roller is controlled by a driving motor encoder, so that the IITA component is controlled to spit back and fall down by unit length, and the spit back and shearing circulation is realized by matching with a shearing tool proximity switch; the spitback IITA assembly is gradually advanced into the shear tool. The IITA components are cut into small sections by the shearing tool, and fall into the collecting barrel, and the collecting barrel is packaged independently.

Further, the spit-back shearing in the step (7) adopts the following method:

straightening the end of an IITA component electric connector: starting the driving roller and reversely rotating, spitting the IITA component back, returning the end head of the IITA component electric connector into the extracting device, retreating the bending roller, starting the straightening roller, pushing the end head of the IITA component electric connector back, enabling the end head of the electric connector after being pushed back to enter a clamp grabbing range, and then opening the clamp to fall to complete re-grabbing;

clamp shearing: the straightening roller and the clamping roller are retreated, the winch is started to enable the clamp and the grabbed IITA component to descend together, the IITA component is sent into the shearing tool, the IITA component is sheared into small sections by the shearing tool, the falling process of the clamp is linked with the shearing action, the falling unit length of the clamp is controlled through the encoder of the winch, and the falling and shearing circulation is realized through the cooperation of the encoder of the winch and the proximity switch of the shearing tool; and after the IITA component only remains the end of the upper electric connector, the clamp is released, the end of the electric connector directly falls into the collecting barrel, and the single IITA component is processed.

The invention provides a novel structural device for completely extracting and winding IITA components under a certain water depth of a reactor refueling water pool, which effectively shields irradiation dose by means of the water layer depth, overcomes the defects that the IITA component extraction process exists in the prior art, a high radioactive pollution section cannot be completely positioned under the effective shielding water depth, and irradiation protection has risks, and completely solves the irradiation shielding safety problem during IITA component replacement, thereby protecting field operators and being more practical;

the invention can realize the movement in the three-dimensional space above the reactor, directly and remotely position the extracted target IITA component, and perform the operations of extraction, winding and the like;

according to the invention, the IITA component is vertically and stably extracted above the reactor, so that the IITA component can not generate obvious lateral force in the whole process, the connecting part of the IITA component installation guide pipe is ensured not to be obviously abraded, and other parts in the reactor are protected to the maximum extent.

The invention can realize the positioning and the feedback of the extracted IITA component, can participate in the subsequent packaging process of the extracted IITA component, can realize the segmentation cutting and the sealing of the extracted IITA component by the equipment, realizes the volume reduction and the storage of the radioactive waste, and meets the post-treatment requirement of the radioactive waste of the nuclear power plant.

Drawings

FIG. 1 is a schematic front view of an extraction apparatus of a nuclear instrumentation assembly of a reactor core;

FIG. 2 is a schematic side view of an extraction apparatus of the nuclear instrumentation assembly of the reactor core;

FIG. 3 is a side view of the connecting frame;

FIG. 4 is a top view of the linking frame;

FIG. 5 is a schematic illustration of the installation of the extraction equipment of the nuclear instrumentation assembly of the reactor core;

FIG. 6 is a schematic view showing the connection relationship between the clamp, the hoist and the water direct drive system;

FIG. 7 is a schematic front view of a support frame structure;

FIG. 8 is a side view of the support frame structure;

FIG. 9 is a rear view of the drawing device and the buffer cartridge;

FIG. 10 is a schematic side view of the drawing device and the buffer cartridge;

FIG. 11 is a schematic front view of the drawing device and the buffer cartridge;

FIG. 12 is a schematic view of a drive motor system;

FIG. 13 is a schematic view of the extraction and winding process;

FIG. 14 is a schematic view of the clamp being lowered;

FIG. 15 is a schematic view of a gripper grasping;

FIG. 16 is a schematic view of the clamp being lifted;

FIG. 17 is a schematic view of the pinch roller pinch;

FIG. 18 is a schematic view of an IITA module bending;

FIG. 19 is a schematic drawing of the winding;

FIG. 20 is a schematic view of the winding of IITA onto the escrow cartridge;

FIG. 21 is a schematic view of a spit-back shear;

FIG. 22 is a schematic view of alignment;

FIG. 23 is a schematic view of shear after straightening.

FIG. 24 is a control relationship diagram of the apparatus of the present invention.

In the above figures, 1-the gripper and drive system; 1.1-clamp; 1.2-a winch; 1.3-pipe rolling device; 1.4-aqueous medium hydraulic drive system; 2-a motor drive system; 2.1 driving the motor; 2.2-torque limiter; 2.3-motor encoder; 2.4-driveshaft assembly; 3-a connection frame; 3.1-hoisting ring; 3.2-mounting frame; 3.3-water pipe guide frame; 3.4-rope guide; 3.5-connecting the stent; 3.5.1-fixed rollers; 4-a support frame; 4.1-a hoist encoder; 4.2-tensiometer; 4.3-supporting structural members; 5-an extraction device; 5.1-extracting the shell; 5.2-bending the roller; 5.3-straightening the roller; 5.4-clamping the roller; 5.5-gearbox; 5.6-the roller drives the hydraulic cylinder group; 5.7-a guide port; 5.8-driving the roller; 6-temporary storage cylinder; 6.1-guide plate; 7-nuclear fuel refueling machine; 7.1-monorail crane; 7.2 nuclear fuel refueling machine fencing; 8-IITA components; 9-a shearing tool; 10-a collecting bucket.

Detailed Description

The present invention will be described in further detail with reference to the accompanying drawings.

The utility model provides a reactor core instrumentation subassembly extraction equipment, as shown in figure 1, top-down includes connecting frame 3, sets up driving motor 2.1 and hoist engine 1.2 in connecting frame 3, still includes braced frame 4, the clamp 1.1 that can reciprocate along braced frame 4, still includes draw-out device 5 and the section of thick bamboo of keeping in 6 of setting in braced frame 4 bottom.

The top of the connection frame 3 is provided with a spreader for lifting the equipment during installation by the monorail crane 7.2 of the nuclear fuel refueling machine. As shown in fig. 3 and 4, four suspension rings 3.1 are attached to the connecting frame.

The lateral part of the connecting frame 3 is provided with a fixed connecting assembly, and the connecting frame is connected with the rail 7.2 of the nuclear fuel refueling machine in a sliding manner through the fixed connecting assembly. As shown in fig. 4 and 5, the sliding connection assembly is preferably a connection bracket 3.5 arranged at the side of the connection frame, the connection bracket is provided with fixed rollers 3.5.1, the distance between the fixed rollers 3.5.1 is adjustable, the rail 7.2 of the nuclear fuel refueling machine is placed in the gap between the fixed rollers, and the distance between the fixed rollers is adjusted so as to realize the relative position fixation of the connection frame 3 on the rail and move along the rail.

As shown in fig. 5, after installation, the connecting frame 3 is arranged above the refueling water pool, and the winch 1.2 and the driving motor 2.1 are arranged in the connecting frame 3, so that the radiation protection and waterproof design of electronic components can be avoided. As shown in fig. 6, the rope of the hoist 1.2 is fixedly connected to the clamp 1.1, so that the clamp 1.1 is lifted and lowered along the length of the support frame 4. The clamp 1.1 is driven by an aqueous medium hydraulic drive system 1.4 to open or close. The pliers (1.1) are preferably long rod type pliers (as shown in figure 15).

As a further improvement, a winch rope guide frame 3.4 is arranged in the connecting frame 3 to ensure that a rope of the winch moves in a certain direction; as a further improvement, a water pipe guide frame is also arranged in the connecting frame 3 for ensuring the water pipe of the hydraulic water medium driving system 1.4 to move directionally.

Still include hoist engine encoder 4.1 and tensiometer 4.2, hoist engine 1.2's rope passes hoist engine encoder 4.1 and tensiometer 4.2, through hoist engine encoder 4.1 control clamp 1.1's lift height, but the pulling force of real-time supervision clamp 1.1 of tensiometer 4.2. The shutdown protection can be set according to the reading of the tension meter, and the winch is stopped when the reading of the tension meter exceeds the preset value, so that the danger of breakage in the extraction process of the target IITA component is avoided. As shown in fig. 7, the hoist encoder 4.1 and the tension gauge 4.2 are preferably provided at a position above the liquid level of the refueling water pool at the upper end of the support frame 4.

As shown in fig. 7 and 8, the supporting frame 4 is a frame structure formed by connecting vertical rods, horizontal rods and reinforcing rods, the vertical length is greater than the horizontal width, and the supporting frame mainly plays a role in supporting and connecting and provides a channel for lifting and lowering the clamp. The existing frame structure design can be adopted, or simple deformation and improvement can be carried out on the basis of the existing product.

The bottom of the supporting frame 4 is fixedly provided with an extracting device 5, as shown in fig. 9-11, the extracting device 5 comprises an extracting housing 5.1, a clamping roller 5.4, a driving roller 5.8, a bending roller 5.2 and a straightening roller 5.3 which are arranged in the extracting housing, and further comprises a gear box 5.5 and a hydraulic cylinder group 5.6. The upper end and the lower end of the extracting shell 5.1 are oppositely provided with guide ports 5.7, and the guide ports 5.7 are used for limiting the moving direction of the clamp, so that the extracting direction is vertical. The driving roller 5.8 and the clamping roller 5.4 are oppositely arranged at the bottom of the extraction shell, a channel for a detection instrument assembly to pass through is reserved between the driving roller 5.8 and the clamping roller 5.4, and the bending roller 5.2 is arranged above the extraction shell 5.1; straightening roller 5.3 is arranged between bending roller 5.2 and clamping roller 5.4.

The driving roller 5.8 is driven by a driving motor 2.1, and the output end of the driving motor 2.1 is connected with the rotating shaft of the driving roller 5.8 through a transmission shaft assembly 2.4 to drive the driving roller 5.8 to rotate forwards and backwards. As shown in fig. 11, a motor encoder 2.3 is mounted on the driving motor 2.1, and controls the number of rotation turns of the driving motor, so that the equipment can be precisely controlled to extract or retract the length of the target IITA component.

As a further improvement, the output end of the driving motor 2.1 is provided with the torque limiter 2.2, the torque limiter 2.2 can realize overload protection of the extraction force of the equipment, when the extraction force generated by driving the driving roller 5.8 is greater than a set value, the torque limiter 2.2 can be disengaged, the motor can not drive the rotating shaft to rotate, and the torque limiter automatically resets after rotating for one circle after the load disappears.

The hydraulic cylinder group 5.6 comprises a plurality of hydraulic cylinders which respectively drive the clamping roller 5.4 to be close to or far from the driving roller 5.8 and drive the bending roller 5.2 and the straightening roller 5.3 to be close to or far from the IITA component in the horizontal direction.

The temporary storage barrel 6 is of a wire coil structure and is arranged on one side of the extraction shell 5.1 and between the driving roller 5.8 and the bending roller 5.2, and the extracted IITA component is bent and then wound on the temporary storage barrel. As a further improvement, a guide plate 6.1 is arranged on the temporary storage cylinder, the guide plate 6.1 is arranged below the initial position of winding of the IITA component, and the extracted IITA component forms a spiral shape with a fixed pitch under the action of the guide plate.

The extraction device 5 clamps the target IITA component by using the driving roller 5.8 and the clamping roller 5.4, and extracts and spits back the IITA component by forward rotation and reverse rotation of the driving roller 5.8; meanwhile, the upper bending roller 5.2 can push the withdrawn IITA component to form a stable spiral structure, so that the IITA component is wound in the temporary storage cylinder 6 in a spring shape, as shown in FIG. 12. When the target IITA component is extracted, the IITA component is completely wound on the temporary storage cylinder and can move to a designated station along with the equipment. The temporary storage cylinder is positioned below the liquid level of the reloading water pool by 3m, so that the radioactivity carried by the extracted IITA component can be completely shielded by a water layer.

As a further improvement, the hydraulic cylinder group device also comprises hydraulic pump stations, and the hydraulic cylinder groups 5.6 are respectively connected to the hydraulic pump stations. As a further improvement, the aqueous medium hydraulic drive system 1.4 of the gripper 1.1 is integrated in a hydraulic pump station.

As a further improvement, the system further comprises an electric control cabinet (an electric control cabinet) and a handheld control console (HMI), wherein each electric control element is integrated in the electric control cabinet, all action commands of the equipment are sent by the handheld control console and display operation parameters of the equipment, such as pressure values of each hydraulic cylinder, tension of an extracted IITA component, cutting cycle times and the like, and the control relationship is shown in fig. 24.

The extraction working process comprises the following steps:

the main work purpose of the equipment is to extract the IITA component needing to be replaced in the reactor pressure vessel out of the reactor, so that the target IITA component can be accurately grabbed and extracted in the extraction process, and the irradiation influence of the reactor on an operator can be maximally guaranteed. After the extraction is finished, the IITA component can be moved to an IITA component sealing station, the extracted IITA component is spit back, the IITA component is cut into small sections by matching with a shearing tool installed on the sealing station, and finally the IITA component falls into a collecting barrel to finish sealing. To meet the requirements of the above purposes, the equipment work flow is as follows:

step (1), descending a clamp: the equipment extraction target IITA component is divided into two stages, namely clamp extraction and winding extraction, and initial clamp extraction. At the start of the extraction operation the gripper 1.1 moves with the entire extraction apparatus over the target IITA component and the gripper is lowered through the extraction device 5 as shown in figure 13.

Step (2), the clamp grabs the target IITA component: after reaching the position where the connector end of the target IITA module can be accurately aligned, the clamp 1.1 is opened, lowered and then closed, and the grabbing action is completed, as shown in figure 14.

And (3) lifting the clamp: after the clamp is grabbed, the winch 1.2 is started to lift the clamp, the target IITA component is pulled out, and the pulling force is monitored in real time through the tension meter 4.2 in the pulling process. And stopping extracting after the clamp is lifted to a specified height, wherein the process can be judged by a motor encoder 2.3. The long bar clamp lifting is limited by the guide opening, and certain perpendicularity is ensured, so that the extracted IITA component is extracted vertically upwards, as shown in figure 15.

Clamping rollers: and starting the clamping roller hydraulic cylinder under the condition that the clamp is not loosened, and pushing the clamping roller 5.4 and the driving roller 5.8 to clamp the extracted IITA component. After clamping, the clamp is opened and lifted upwards, and the IITA component is completely released from the clamp, as shown in figure 16;

and (5) bending the IITA component: the winding extraction phase is entered after the clamp releases the target IITA component. And starting the bending hydraulic cylinder, and pushing the bending roller 5.2 forward to push the IITA component to bend towards the inlet direction of the temporary storage barrel 6. By adjusting the operating stroke of the bending cylinder, the size of the final IITA assembly winding radius can be adjusted, as shown in fig. 17.

And (6) winding and extracting: the driving motor 2.1 is started to drive the driving roller 5.8 to rotate, and friction force is generated on the surface of the clamped IITA component due to the clamping force action of the driving roller and the clamping roller, and the friction force provides extraction force for extracting the IITA component. At this point the IITA assembly continues to be withdrawn from the reactor and follows a fixed radius forming a circle due to the action of the bending rollers. The size of the temporary storage cylinder is matched with the circumference, so that the IITA component can be wound on the temporary storage cylinder. In addition, a guide plate 6.1 is designed on the temporary storage cylinder 6, the driving roller continuously rotates, and the IITA component which is subsequently drawn out forms a spiral shape with a fixed screw pitch under the action of the guide plate. After the target IITA component is completely withdrawn from the reactor, the withdrawal process is complete, as shown in FIGS. 18, 19 and 20;

and (7) spit-back shearing: the extracted IITA components need to be sealed, but because of the high radioactivity, the volume occupied by the components in the sealing process is reduced as much as possible. The equipment of this application realizes shearing with shearing tool 9 and collecting vessel 10 cooperation and seals up the deposit. After extraction is finished, the equipment moves to the position above the shearing tool 9 along with the hoisting equipment on the nuclear fuel refueling machine, a collecting barrel 10 is arranged below the shearing tool 9, and the tail part of the extracted IITA component is aligned with the shearing tool 9. The drive roller 5.8 is activated and rotated in the reverse direction to eject the IITA module as shown in figure 21. The re-discharged IITA components gradually enter the shearing tool, the shearing tool utilizes a hydraulic cylinder to drive a blade to cut the IITA components into small sections, the small sections fall into a collecting barrel 10, and the collecting barrel can be independently packaged.

As a further improvement, in order to ensure that the cutting length of each section is the same, the back-spitting and shearing actions can be linked. The unit length of each section is controlled to be spit back through a driving motor encoder, and meanwhile, a proximity switch is arranged on the shearing tool to detect the position of the shearing tool. After a cutter opening signal fed back by the proximity switch is received, the motor rotates to drive the roller to start to spit the IITA component back to the unit length, the encoder feeds back to the position signal after the spit back is finished, and the signal drives the cutting tool to start cutting. And continuously repeating the actions until the cutting action with the preset cycle number is finished through automatic control of the electric control background, and at the moment, the IITA component backs back to the appointed position.

As a further improvement, the returned meter is fed into the shear tool, a certain distance is reserved between the shear tool and the extraction device, the returned meter is not vertical, and is difficult to align with the inlet of the shear tool, and alignment is needed to ensure that the returned meter is aligned with the shear tool. The method comprises the following steps:

straightening the end of an IITA component electric connector: the driving roller is started and rotates reversely, the IITA component is spit back, the end of the IITA component electric connector returns to the extracting device, at the moment, the bending roller influences the end of the IITA component electric connector and cannot return to the original position, the clamp vertically falls down and cannot grab, in order to achieve re-grabbing of the IITA component by the clamp, the bending roller needs to be retracted, the straightening roller is started, the end of the IITA component electric connector is pushed back, and the end of the electric connector pushed back can enter a clamp grabbing range, as shown in fig. 22. Then the clamp is opened and falls down to complete the re-grasping.

Clamp shearing: after the clamp re-grabs the IITA component, the straightening roller and the clamping roller are retracted, the winch is started to enable the clamp and the grabbed IITA component to descend together, the rest IITA components are sent into the shearing tool, and the shearing tool is matched with the clamp to shear the IITA component into small sections. As shown in fig. 23. The falling process of the clamp can be linked with the shearing action, the falling unit length of the clamp is controlled by a winch coder, and the falling and shearing circulation process is realized by the signal matching of the clamp and a shearing tool proximity switch. And after the IITA component is conveyed into the tool and only the end head of the electric connector at the upper end is left, the clamp is loosened, the end head of the electric connector directly falls into the collecting barrel, and the treatment process of the single IITA component is finished.

The above-mentioned embodiments are merely illustrative of the preferred embodiments of the present invention, and do not limit the scope of the present invention, and various modifications and improvements of the technical solution of the present invention by those skilled in the art should fall within the protection scope defined by the claims of the present invention without departing from the spirit of the present invention.

Claims (10)

1. The extraction equipment for the nuclear detection instrument assembly of the reactor core is characterized by comprising a clamp, a hydraulic medium driving system of the clamp, a winch, an extraction device, a temporary storage barrel, a supporting frame and a connecting frame;

the supporting frame is vertically arranged, the top of the supporting frame is fixedly provided with a connecting frame, the top of the connecting frame is provided with a lifting appliance, the side part of the connecting frame is provided with a sliding connection assembly, and the sliding connection assembly is in sliding connection with a fence of the nuclear fuel refueling machine; a winch and a driving motor are arranged in the connecting frame, a rope of the winch is fixedly connected with the clamp, and the clamp is driven to open or close by a water medium hydraulic driving system;

a winch rope guide frame, a winch coder and a tension meter are arranged in the supporting frame, and a rope of the winch passes through the coder and the tension meter and is lifted and lowered along the length direction of the supporting frame;

the bottom of the supporting frame is fixedly provided with an extraction device, the extraction device comprises an extraction shell, a clamping roller, a driving roller, a bending roller and a straightening roller, and the hydraulic cylinder group is arranged in the extraction shell; the upper end and the lower end of the extraction shell are oppositely provided with guide openings, the driving roller and the clamping roller are oppositely arranged at the bottom of the extraction shell, a channel for an IITA component to pass through is reserved between the driving roller and the clamping roller, and the bending roller is arranged above the extraction shell; the straightening roller is arranged between the bending roller and the clamping roller;

the output end of the driving motor is connected with a rotating shaft of the driving roller through a transmission shaft assembly to drive the driving roller to rotate forwards and backwards, and a motor encoder is further arranged on the driving motor; the hydraulic cylinder group comprises a plurality of hydraulic cylinders which respectively drive the clamping roller, the bending roller and the straightening roller to be close to or far away from the IITA component in the horizontal direction;

the temporary storage barrel is arranged on one side of the extraction shell, and the diameter of the temporary storage barrel is matched with the bending angle of the bending roller.

2. The extraction apparatus of the nuclear reactor core instrumentation assembly according to claim 1, wherein the sliding connection assembly is a connection bracket provided at a side of the connection frame, the connection bracket is provided with fixed rollers, a distance between the fixed rollers is adjustable, a fence of the nuclear fuel refueling machine is placed between the fixed rollers, the distance between the fixed rollers is adjusted, and the connection frame is connected to the fence and is movable along the fence.

3. The reactor core nuclear instrumentation assembly draw-off equipment of claim 1 wherein a rope guide is further disposed within the support frame, the hoist rope being disposed within the rope guide.

4. The reactor core nuclear instrumentation assembly extraction apparatus of claim 1 wherein the clamps are long rod clamps.

5. The reactor core nuclear instrumentation assembly extraction plant of claim 1 wherein a guide plate is provided on the staging drum, the guide plate being disposed below the initial position of IITA assembly winding.

6. The reactor core nuclear instrumentation assembly extraction apparatus of claim 1 wherein the output of the drive motor is mounted with a torque limiter.

7. The extraction equipment for the nuclear detection instrument assembly of the reactor core according to claim 1, further comprising hydraulic pump stations, wherein the hydraulic cylinder groups are respectively connected to the hydraulic pump stations; and the water medium hydraulic driving system of the clamp is integrated in the hydraulic pump station.

8. The reactor core nuclear instrumentation assembly draw-off equipment of claim 1 further comprising an electrical control cabinet and a hand-held console, each of the electrical control components being integrated within the electrical control cabinet, the hand-held console including an input module and a display module.

9. A method of extracting a nuclear instrumentation component from a reactor core, comprising the steps of:

step (1), descending a clamp: moving the extraction apparatus of claim 1 over the target instrumentation assembly using the lifting device, the clamp lowering through the extraction device to directly over the IITA assembly;

step (2), the clamp grabs the target IITA component: after the clamp is aligned with the position of the electric connector end of the target IITA component, the clamp is opened, descended and then closed to finish the grabbing action;

and (3) lifting the clamp: starting a winch to lift the clamp, vertically and upwardly withdrawing the target IITA component, and stopping withdrawing after the clamp is lifted to a specified height;

clamping rollers: starting a clamping roller hydraulic cylinder under the condition that the clamp is not loosened, pushing the clamping roller and the driving roller to clamp the extracted IITA component, and opening the clamp and lifting the clamp upwards to the IITA component to be completely separated from the clamp;

and (5) bending the IITA component: starting a bending hydraulic cylinder, pushing a bending roller forward, and pushing an IITA component to bend towards the inlet direction of the temporary storage cylinder;

and (6) winding and extracting: starting a driving motor to drive a driving roller to rotate, wherein under the action of the driving roller and a clamping roller, the IITA component is drawn out from the reactor, forms a circumference and is wound on a temporary storage cylinder under the action of a bending roller, and after the target IITA component is completely drawn out from the reactor, the drawing process is finished;

and (7) spit-back shearing: the equipment is moved above a shearing tool by using hoisting equipment, a collecting barrel is arranged below the shearing tool, the tail part of the extracted IITA component is aligned to the shearing tool, a driving roller is started and rotates reversely, the IITA component is spit back, the spit back process is linked with shearing action, the rotation angle of the driving roller is controlled by a driving motor encoder, so that the IITA component is controlled to spit back and fall down by unit length, and the spit back and shearing circulation is realized by matching with a shearing tool proximity switch; the IITA component which is spit back out gradually enters a shearing tool, the shearing tool cuts the IITA component into small sections, the small sections fall into a collecting barrel, and the collecting barrel is packaged independently.

10. The extraction method according to claim 9, wherein the step (7) of spit-back shearing employs the following method:

straightening the end of an IITA component electric connector: starting the driving roller and reversely rotating, spitting the IITA component back, returning the end head of the IITA component electric connector into the extracting device, retreating the bending roller, starting the straightening roller, pushing the end head of the IITA component electric connector back, enabling the end head of the electric connector after being pushed back to enter a clamp grabbing range, and then opening the clamp to fall to complete re-grabbing;

clamp shearing: the straightening roller and the clamping roller are retreated, the winch is started to enable the clamp and the grabbed IITA component to descend together, the IITA component is sent into the shearing tool, the IITA component is sheared into small sections by the shearing tool, the falling process of the clamp is linked with the shearing action, the falling unit length of the clamp is controlled through the encoder of the winch, and the falling and shearing circulation is realized through the cooperation of the encoder of the winch and the proximity switch of the shearing tool; and after the IITA component only remains the end of the upper electric connector, the clamp is released, the end of the electric connector directly falls into the collecting barrel, and the single IITA component is processed.

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