CN107610797B - Nuclear fuel assembly pull rod system and process - Google Patents

Nuclear fuel assembly pull rod system and process Download PDF

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Publication number
CN107610797B
CN107610797B CN201710806637.3A CN201710806637A CN107610797B CN 107610797 B CN107610797 B CN 107610797B CN 201710806637 A CN201710806637 A CN 201710806637A CN 107610797 B CN107610797 B CN 107610797B
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rod
pull rod
pulling
pull
platform
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CN107610797A (en
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钱烽
王革
唐荣联
汪华平
王烛光
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CMCU Engineering Co Ltd
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CMCU Engineering Co Ltd
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    • 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

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Abstract

The invention relates to a nuclear fuel assembly rod pulling system and a process, wherein the system comprises a rod pulling pre-assembly box platform, a framework clamping platform and a rod pulling host, wherein the framework clamping platform is arranged between the rod pulling pre-assembly box platform and the rod pulling host, and the device is provided with a moving mechanism and a lifting mechanism on the rod pulling pre-assembly box platform and the rod pulling host, so that the automation degree in the whole process is improved. The process controls each cylinder through a PLC program, so that the control of each pull rod is realized, the pull rod can be more flexibly carried out, and the quality and the efficiency of the process are improved.

Description

Nuclear fuel assembly pull rod system and process
Technical Field
The invention belongs to the field of nuclear energy, and relates to a nuclear fuel assembly pull rod system and a process.
Background
The nuclear power is taken as a low-carbon energy source, is an important component of clean energy, the thirteen-five planning in China greatly develops nuclear energy, 6-8 nuclear power stations are expected to be newly built every year, and the nuclear power operation in China and the installation in the construction machine reach 8800 kilowatts. The nuclear fuel assembly is a core component of a nuclear power unit core, and the quality reliability of the nuclear fuel assembly is directly related to the safety and service life of a nuclear power plant.
The nuclear fuel assembly, as shown in fig. 1a and 1b, comprises an upper tube seat component 401, an upper end portion lattice 402, a mixing lattice 403, fuel rods 404, instrumentation tubes 405, a lower end portion lattice 406, guide tubes 407 and a lower tube seat component 408, wherein the length of the nuclear fuel assembly is about 4m, the cross section of the lattice is 214mm by 214mm, the diameter of the fuel rods is about 9.5mm, the length of the fuel rods is about 3972mm, a 17 x 17 layer arrangement structure is formed on the cross section, fig. 1b is a sectional view, the framework is composed of 11 lattices and a plurality of guide tubes, the previous process is to pull the fuel rods with the length of about 4m layer by layer through the 11 lattices in the framework, and finally, the fuel rods pass through all the lattices, but the number of the fuel rods pulled in each layer is different due to the fact that 24 guide tubes exist in the 17 x 17 lattice, and the selection of the pull rods is needed. Typically using a cylinder.
Because the diameter of the pull rod is very small, the arrangement space is narrow, if 17 cylinders are arranged correspondingly, the arrangement is not easy, so that the selection of a single pull rod cannot be realized by the early pull rod process, but when a fault occurs in the pull rod process, a certain fuel rod is pulled off, the single pull rod operation cannot be carried out on the missed fuel rod, and the accident treatment is very complicated.
The manufacturing process of the nuclear fuel assembly is complex, the requirements on safety and reliability are high, the assembly process of the assembly pulling rod of the fuel rod and the framework is very difficult, the working procedure period is long, the productivity and the quality of the assembly are greatly influenced, and the assembly pulling rod is always an important control procedure for the production of the nuclear fuel assembly. At present, the assembly pulling rod assembly procedure of the fuel rod and the framework is completed by adopting pulling rod special equipment, and as the early nuclear power technology in China is comparatively backward, the industrial automation degree is low, the existing pulling rod system in China is quite different from that in foreign countries, the quality, the precision and the efficiency of the pulling rod are comparatively poor, and the pulling rod also needs to depend on foreign import devices in a plurality of important links.
Disclosure of Invention
In view of the above, the invention aims to provide a nuclear fuel assembly pulling rod system and a process, which effectively improve the precision and quality of assembly pulling rods, enhance the reliability of the pulling rod process, improve the degree of automation and reduce the labor intensity of workers.
In order to achieve the above purpose, the present invention provides the following technical solutions:
the utility model provides a nuclear fuel assembly rod system, includes rod pre-boxing platform, skeleton clamping platform, rod host computer, the skeleton clamping platform sets up between rod pre-boxing platform and rod host computer, all be provided with moving mechanism on rod pre-boxing platform and the rod host computer, rod pre-boxing platform includes pre-boxing removal actuating mechanism and pre-boxing elevating system, the skeleton clamping platform includes grid clamping frame, the rod host computer includes rod main workstation, pull rod select pole and positioning mechanism, rod elevating servo actuating mechanism, rod main servo system.
Further, the pull rod selecting rod and positioning mechanism comprises a slide carriage, a selecting rod cylinder, a selecting rod pull plate, a rotating shaft and a pull rod, wherein the selecting rod pull plate is connected with the slide carriage through the rotating shaft, a pull claw and a pull rod bayonet are arranged on the pull rod, each selecting rod pull plate is respectively and independently connected with the corresponding selecting rod cylinder and is embedded into the pull rod bayonet, and the slide carriage is connected with the pull rod through a pull rod hanging structure.
Further, the two rows of the rod selecting cylinders are arranged in a staggered mode.
Further, the pull rod hanging structure comprises a hanging groove arranged on the slide carriage, the pull rod connecting pull rod hanging seat is arranged in the hanging groove, and a guide groove is arranged below the pull rod.
Further, a force sensor is arranged between the selector rod pulling plate and the slide carriage.
Further, the force sensor is an S-shaped force sensor.
Further, the framework clamping platform further comprises a turnover driving mechanism, the turnover driving mechanism comprises a turnover oil cylinder and a turnover main beam, the turnover main beam is hinged with the framework clamping platform through a main hinge, the diagonal bracing of the turnover oil cylinder is arranged, and the front hinge support point of the turnover oil cylinder is arranged in the middle of the turnover main beam.
Further, the preassembly box moving driving mechanism comprises a roller way.
A nuclear fuel assembly pulling rod process comprises the following steps,
a. welding and combining the grids and the guide pipes in advance to form a framework assembly, placing the framework on a framework clamping platform to be in position, clamping the grids on the framework, and adjusting, positioning and locking;
b. conveying the preassembled boxes with the preassembled fuel rods to a rod-pulling preassembling box platform through a roller way, and positioning, clamping and locking;
c. then starting a program, and moving the pull rod pre-boxing platform and the pull rod host towards the middle framework clamping platform;
d. the lifting servo driving mechanism of the pulling rod is controlled by a program to drive the workbench of the pulling rod host to lift to an accurate position, and the workbench is centered and positioned with one layer of 17 layers of through holes on the grid;
e. setting a rod selecting subprogram on a rod pulling host, and presetting a PLC program to independently control each cylinder according to different assembly specifications, selecting a pull rod, and simultaneously positioning and locking the pull rod which is not selected by utilizing the subsequent rod selecting cylinder;
f. starting a rod pulling program, servo-driving a slide carriage, pushing a pull rod by the slide carriage to advance towards the direction of the pre-packaged box through a grid, and grabbing a fuel rod through a pull claw arranged at the end part of the pull rod after the pull rod reaches a preset position;
g. starting the rod pulling program again, driving the slide carriage reversely, hanging the pull rod by the slide carriage, pulling the fuel rods out of the pre-assembled box, and sequentially passing through all grids on the framework to reach the preset position to finish rod pulling;
h. the main rod pulling workbench of the rod pulling host machine is subjected to height adjustment through a rod pulling lifting servo driving mechanism, and moves to the other layer, and the rod pulling steps are repeated until all fuel rods are pulled into 17 layers of holes of the grid;
i. starting a reset button, returning the preassembled box platform and the pull rod host to the original positions, and performing auxiliary operation;
j. the program control enables the framework clamping and overturning platform to rotate from a horizontal state to an upright state, and the nuclear fuel assembly completed by pulling the rods is lifted and separated, so that one working cycle is completed.
Further, in the process of pulling the rods, the total pulling force of each pull rod is continuously detected and output, and when the total pulling force exceeds a preset warning value, the control system alarms and immediately stops.
The invention has the beneficial effects that:
1. according to the automatic pulling rod pre-boxing platform, the moving mechanism and the lifting mechanism are arranged on the pulling rod pre-boxing platform and the pulling rod main machine respectively, so that the degree of automation in the whole technological process is improved, and the quality and the efficiency of the process are improved.
2. And each cylinder is controlled through a PLC program, so that the control of each pull rod is realized, the pull rod can be more flexibly carried out, when a fault occurs in the pull rod process, a certain fuel rod is pulled out, and after other fuel rods are pulled in place, the pulled out fuel rods are independently selected for pulling, so that the accident handling time is greatly reduced, and more flexible pull rod operation can be realized.
3. The utility model provides a pull rod suspended structure installs on the pull rod through the screw, when the pull rod push head promotes the pull rod and advances or retreats, the pull rod remains throughout and hangs in the suspension groove of carriage apron, just so make pull rod and carriage apron remain relatively fixed, show the rigidity that has improved the pull rod, the push head of selecting the pole pull plate is to the bending that the pull rod caused after the pull rod is pushed down the effect, the support direction requirement of the guide way of nylon board below having reduced the pull rod to the pull rod, consequently the nylon board need not make the whole machined part of pull rod total length, only need the segmentation processing be good can, the manufacturing degree of difficulty of direction nylon board has greatly reduced. The service life of the device is prolonged. Thereby better ensuring the quality of the pull rod of the nuclear fuel assembly.
4. The total tension of each pull rod is continuously detected, so that a factory can accurately master the stress condition of each layer of grillwork of the nuclear fuel assembly in the process of pulling rods, direct support is provided for improving the nuclear fuel assembly from data, and the control system can alarm and stop immediately when the total tension exceeds a preset warning value.
5. According to the overturning driving mechanism, the oil cylinder arrangement mode is set to be the inclined strut, the front hinge support point is adjusted to the middle of the main beam, the angle is adjusted to a reasonable range, the thrust included angle of the oil cylinder is increased in the vertical state of the overturning platform, the lateral component force of the bearing is greatly reduced, the stability of the assembly is improved, and the depth of a pit is reduced.
Drawings
In order to make the objects, technical solutions and advantageous effects of the present invention more clear, the present invention provides the following drawings for description:
FIG. 1a is a schematic structural view of a nuclear fuel assembly;
FIG. 1b is a cross-sectional view of a nuclear fuel assembly;
FIG. 2 is a schematic diagram of the structure of the present invention;
FIG. 3 is a schematic diagram of a pull rod selector and positioning mechanism;
FIG. 4 is a schematic diagram of a pull rod hanging structure;
fig. 5a is a schematic structural diagram of the framework clamping platform according to the present embodiment;
FIG. 5b is a schematic structural view of a prior art skeletal clamping platform;
FIG. 6 is a graph of drag force received by a pull rod during a pull rod pulling process;
FIG. 7 is a force diagram of a tumble drive mechanism bearing and cylinder;
fig. 8 is a schematic structural view of the front hinge structure of the present embodiment.
Detailed Description
Preferred embodiments of the present invention will be described in detail below with reference to the accompanying drawings.
The invention discloses a nuclear fuel assembly rod pulling system, which is shown in fig. 2, and comprises a rod pre-boxing platform 1, a framework clamping platform 2 and a rod pulling host machine 3, wherein the framework clamping platform 2 is arranged between the rod pre-boxing platform 1 and the rod pulling host machine 3, the rod pre-boxing platform 1 and the rod pulling host machine 3 are both provided with moving mechanisms, the moving mechanisms of the rod pre-boxing platform 1 comprise linear guide rails 101, the rod pulling host machine 3 is provided with a moving device 321, the rod pre-boxing platform 1 comprises a pre-boxing moving driving mechanism and a pre-boxing lifting mechanism 102, and the pre-boxing moving driving mechanism comprises a roller way 103. The framework clamping platform 2 comprises a framework clamping framework 201, the pull rod host 3 comprises a pull rod main workbench 301, a pull rod selecting rod and positioning mechanism 302, a pull rod lifting servo driving mechanism 303 and a pull rod main servo system 304, and the pull rod selecting rod and positioning mechanism 302 can select and position any pull rod 309.
In this embodiment, a lifting main beam 108 is arranged on the pre-loading box platform 1, a plurality of rollers are installed on the lifting main beam 108 to form a conveying workbench of a roller way 103, and then the main beam is driven to lift by a small stroke through the pre-loading box lifting mechanism 102. Guide sleeves 106 are arranged at two ends of the lifting main beam 108, so that stability under lifting and stress states is ensured. Wherein 105 is a base.
When the pre-packaged box 107 is pushed from the trolley to the pull rod pre-packaged box platform 1, the lifting main beam 108 is lifted by 50mm, so that the pre-packaged box 107 can roll on the roller way 103 to advance, the labor intensity of workers is greatly reduced, after the pre-packaged box 107 is pushed in place, the lifting main beam 108 is controlled to descend through a program, at the moment, the pre-packaged box falls on 6 reference flat plates 104, and the workers can immediately perform positioning operation, so that the abrasion of the reference flat plates 104 is obviously reduced. Which contributes to the precision maintenance of the device. And meanwhile, the automatic intelligent production transformation of the subsequent pre-packaged boxes 107 is also convenient.
Fig. 3 is a schematic structural diagram of a pull rod selecting rod and positioning mechanism 302, the pull rod selecting rod and positioning mechanism 302 includes a slide carriage 305, a selecting rod cylinder 306, a selecting rod pulling plate 307, a rotating shaft 308, and a pull rod 309, the selecting rod pulling plate 307 is connected with the slide carriage 305 through the rotating shaft 308, a pull claw 310 and a pull rod bayonet 311 are arranged on the pull rod 309, a pulling plate pushing head 312 is arranged on the selecting rod pulling plate 307, each selecting rod pulling plate 307 is respectively and independently connected with the corresponding selecting rod cylinder 306, the selecting rod cylinders 306 are arranged in two rows, and the two rows of selecting rod cylinders 306 are connected with the set selecting rod pulling plate 307 after being arranged in a dislocation manner. Wherein 322 is a base, and adopts the cylinder dislocation arrangement, divide into two rows according to front 8 back 9, then select pole cylinder 306 and select pole arm-tie 307 to carry out dislocation connection, 17 select pole arm-tie 307 all are connected with slide carriage 305 through same pivot 308, select pole arm-tie 307 can be around pivot 308 certain angle of swing under the drive of select pole cylinder 306 for select pole arm-tie 307's arm-tie push head 312 embeds in pull rod bayonet socket 311, thereby promotes or pulls pull rod 309 and remove. And each cylinder is controlled through a PLC program, so that the control of each pull rod is realized.
The slide carriage 305 is connected with a pull rod 309 through a pull rod hanging structure 313. The pull rod hanging structure 313 comprises a hanging groove 314 arranged on the slide carriage 305, the pull rod 309 is connected with a pull rod hanging seat 315 and is arranged in the hanging groove 314, and a guide groove 317 is arranged below the pull rod 309. The guide groove 317 of this embodiment is formed for the nylon guide plate 316. Wherein 318 is the pull rod outer sleeve. In the prior art, since the fuel rod is long, the pull rod 309 is correspondingly long, about 4.8m, 8mm in diameter and poor in rigidity, and the nylon guide plate 316 is arranged below the pull rod to serve as the guide groove 317, but the whole guide groove is difficult to process, and meanwhile, the pull rod 309 has a pressure effect on the guide groove 317 under the push-pull action of the pull plate push head 312, so that the stress is unstable in the pulling process of the fuel rod, the nylon plate is fast in deformation failure, and the quality of the pull rod is affected. In this embodiment, the hanging groove 314 is provided on the slide carriage 305, then the bayonet seat of the pull rod 309 is designed as a pull rod hanging structure 313 as shown in fig. 4, the pull rod hanging structure 313 is mounted on the pull rod 309 through screws, when the pull rod pushing head 312 pushes the pull rod to advance or retreat, the pull rod 309 is always kept hanging in the hanging groove 314 of the slide carriage 305, so that the rigidity of the pull rod 309 and the slide carriage 305 is kept relatively fixed, the rigidity of the pull rod 309 is remarkably improved, the bending caused to the pull rod 309 after the pull rod 309 is pushed down by the pull rod pushing head 312 is reduced, and the requirement of the nylon guide plate 316 below the pull rod 309 on the support and guide of the pull rod 309 is reduced, therefore, the nylon guide plate 316 does not need to be made into an integral workpiece of the whole length of the pull rod, only needs to be processed in a segmented manner, and the manufacturing difficulty of the nylon guide plate 316 is greatly reduced. The service life of the device is prolonged. Thereby better ensuring the quality of the pull rod of the nuclear fuel assembly.
A force sensor 319 is arranged between the selector rod pulling plate 307 and the slide carriage 305. The force sensor 319 adopts an S-shaped force sensor, can effectively convert the tensile force into tiny deformation data, then converts the tiny deformation data into an electric signal through a strain gauge, transmits the electric signal to a transmitter through a signal output port, and enters a control system after being amplified by the transmitter.
The force sensor is connected with the mounting seat 320 through the fixing screw, then the force sensor is mounted on the slide carriage 305 through the mounting seat 320, the force sensor moves along with the slide carriage 305 in the process of pulling the rod, when the rod 309 grabs the fuel rod and pulls the fuel rod backwards and passes through a layer of grillwork, the rod 309 is subjected to the action of the grillwork friction resistance, the rod pushing head 312 is used for bearing the pulling force, the sensor cannot be directly arranged here due to the very narrow space and the reasons of maintenance, and the like, so that the pulling force is transmitted to the upper part of the slide carriage 305 by using the mechanism principle that the rod pulling plate 307 rotates around the rotating shaft 308, the supporting nails are arranged on the rod pulling plate 307, the force sensor is indirectly measured by the action of the supporting nails, and the rolling bearing with small friction force is adopted at the rotating shaft 308 due to the same force arm, meanwhile, the supporting nails are arranged as ball heads, and manufacturing errors are eliminated, so that the error between the force and the actual force is small, and the Shan Bangli detection of the nuclear fuel assembly is realized.
As shown in fig. 6, when the pulling claw 310 of the rod pulling machine pulls the fuel rod through the one-layer lattice of the component skeleton, the pulling rod gradually receives the resistance force of F1 to F11 from the first-layer lattice due to the friction force F of the spring clamping, and sequentially accumulates. Because the whole process is stable, the theoretical resistance is equal to the pulling force, the pulling force displayed by the detection device arranged at the tail end of each pull rod is from 50N to 90N … … to 450N, and the force sensor of the detection system can dynamically output continuous values, so that the total pulling force of each pull rod can be continuously detected. When the total tension exceeds a preset warning value, the control system alarms and stops immediately.
Besides detecting and outputting the total pulling force of each pull rod, the detection system can also detect the resistance of each layer of grillwork passing through the pull rod process through a system operation program, thereby controlling the pull rod process deeper into one layer. The resistance of each layer of grillwork to the pull rod can be accurately known, so that the grillwork quality and pull rod equipment are monitored, improvement comments can be further provided for welding of grillwork, welding assembly of a framework and pull rod production line equipment, and the improvement comments have practical significance for improving the overall quality of the nuclear fuel assembly. Specifically, as shown in fig. 6, when the tension detected when the tension rod passes through the first layer of the grids is 50N, and when the resistance through the second layer of the grids is 90N, for example, the resistance through the second layer of the grids is 90N-50 n=40n, and so on, when the total tension value after passing through each layer of the grids is detected, the resistance through each layer of the grids can be calculated. When the resistance of a certain layer of the grid exceeds a warning value preset by a program, such as 50N, the system alarms, and the rod pulling process is stopped, so that the grid and the components are protected.
The force detection can accurately detect the pulling force of each pull rod, the pulling force is sent into a control system through a transmitter, a stress distribution diagram of each layer of grillwork is further made through software analysis, and data is transmitted to related process systems and related departments of a factory through a network system, so that the factory can accurately grasp the stress condition of each layer of grillwork of the nuclear fuel assembly in the pulling rod process, and direct support is provided for improving the nuclear fuel assembly from the data. Provides basis for the intelligent production of the nuclear fuel assembly in the future.
Fig. 5b is a schematic structural diagram of a prior art framework clamping platform. The existing rod pulling machine adopts a mode of a multi-stage oil cylinder or a deep pit single-stage oil cylinder, when the oil cylinder is turned to an upright state, the angle between the axis of a push rod of the oil cylinder and a turning frame is smaller, so that a bearing at a main hinge of the turning is subjected to a large lateral component force, fatigue abrasion of the bearing is aggravated, the precision of the bearing is affected, meanwhile, due to the large lateral force, the stability of a turning platform in the upright state is poor, the actual use condition is that the shaking phenomenon exists under the upright state, and the shaking phenomenon is not allowed for the production process of a key nuclear fuel assembly in the nuclear power field.
In this embodiment, fig. 5a is a schematic structural diagram of the framework clamping platform of this embodiment; the framework clamping platform 2 further comprises a turnover driving mechanism, the turnover driving mechanism comprises a turnover oil cylinder 202 and a turnover main beam 203, the turnover main beam 203 is hinged with the turnover main beam 203 of the framework clamping platform 2 through a main hinge 204, the turnover oil cylinder 202 is arranged in a diagonal manner, and a front hinge supporting point 205 of the turnover oil cylinder 202 is arranged in the middle of the turnover main beam 203. This patent improves current upset actuating mechanism, should put the bracing with hydro-cylinder arrangement mode, and preceding hinge fulcrum adjusts to the girder centre, adopts the front hinge structure in front hinge fulcrum 205 department as shown in fig. 8, just so to the more reasonable scope of angle adjustment for under the vertical state of upset platform, hydro-cylinder thrust contained angle increases, has reduced the side direction component of bearing greatly, has improved the stability of subassembly. And the depth of the pit is reduced. Wherein 206 the guide plate mechanism, 207 is the upper and lower tube seat device; fig. 7 is a force diagram of the bearing and the oil cylinder of the overturning driving mechanism in this embodiment, and through practical calculation data simulation, it can be seen that the bearing stress is very gentle.
A nuclear fuel assembly pulling rod process comprises the following steps,
a. welding and combining the grids and the guide pipes in advance to form a framework assembly, placing the framework on the framework clamping platform 2 to be in position, clamping the grids on the framework, and adjusting, positioning and locking;
b. conveying the preassembled boxes 107 with the preassembled fuel rods to a pull rod preassembling box platform 1 through a roller way 103, and positioning, clamping and locking;
c. then starting a program, and moving the pull rod pre-assembled box platform 1 and the pull rod host 3 towards the middle framework clamping platform 2;
d. the pulling rod host workbench 301 is driven to lift to an accurate position by a program control pulling rod lifting servo driving mechanism 303, and is centered and positioned with one layer of 17 layers of through holes on the grid;
e. setting a rod selecting subprogram on a rod pulling host, and according to different component specifications, presetting a PLC program to independently control each rod selecting cylinder 306, selecting a pull rod 309, and simultaneously utilizing the subsequent rod selecting cylinder 306 to position and lock the pull rod 309 which is not selected;
f. starting a rod pulling program, servo-driving a slide carriage 305, pushing a pull rod 309 by the slide carriage 305 to advance towards the direction of the pre-assembled box 107 through the grid, and grabbing a fuel rod through a pull claw 310 arranged at the end part of the pull rod 309 after reaching a preset position;
g. starting the rod pulling program again, driving the slide carriage 305 reversely, hanging the pull rod 309 on the slide carriage 305, pulling the fuel rods out of the pre-packaged box 107, and sequentially passing through all grids on the framework to reach the preset position to finish rod pulling;
h. the main rod pulling workbench 301 of the rod pulling host 3 is subjected to height adjustment through a rod pulling lifting servo driving mechanism 303, moves to the other layer, and repeats the rod pulling step until all fuel rods are pulled into 17 layers of holes of the grid;
i. starting a reset button, returning the preassembled box platform 1 and the pull rod host 3 to the original positions, and performing auxiliary operation;
j. the program control makes the framework clamping platform 2 rotate from a horizontal state to an upright state, and lifts the nuclear fuel assembly which is completed by pulling the rods away, so that one working cycle is completed.
In the process of pulling the rods, the total pulling force of each pull rod 309 is continuously detected and output, and when the total pulling force exceeds a preset warning value, the control system alarms and immediately stops.
In the production process of the nuclear fuel assembly, when a rod pulling fault occurs or the nuclear fuel assembly is required to be maintained, the fuel rod is required to be pulled out of the whole assembly, the special domestic rod pulling machine at present can only be pulled out of the assembly by adopting one manual rod, the labor intensity is high, more importantly, the manual pulling is high, secondary damage is easily caused to the fuel rod and the grid, and therefore the quality and the reliability of the nuclear fuel assembly are affected. The common special rod pulling machine is provided with 17 long pull rods, the length of a working section is about 5.6m, during normal operation, the long pull rods are pulled for a distance of about 4.8m, the fuel rods can be pulled out of the pre-assembled box and pass through 11 layers of grids to reach the preset position in front of the lower tube seat, rod pulling operation is completed, when the fuel rods are required to be pulled out for component maintenance or fault treatment, the long pull rods are used for grabbing the fuel rods from rod dropping positions and pulling the fuel rods to the position in front of the lower tube seat, the travel of a main rod pulling plate 305 of the tension rod is limited, at the moment, the slide plate 305 is retracted, the long pull rods pushed by the slide plate 305 can not be pulled out of the grids any more, at the moment, the long pull rods are pulled out, the short pull rods are replaced, the short pull rod structure is identical to the long pull rods, the length of the working section is shortened to about 500mm, the slide plate 305 drives the short pull rods to be restarted to the working position, the fuel rods are grabbed, and the fuel rods are completely pulled out of the component grids by the same working travel stroke. The short rod pull rod process method can also be used in the equipment debugging and overhaul process, and is convenient to test and debug, and the test rod is pulled through the lattice by the short rod pull rod process so as to determine the centering precision errors of the center of the pre-packaged fuel rod, the center of the lattice and the center of the pull rod main machine pull rod.
The pull rod main workbench 301 is provided with a pull rod selecting rod and positioning mechanism 302 for pulling 17 layers of fuel rods layer by layer through the grids to complete assembly, and before each layer of pull rods, the workbench is required to be lifted by a certain height according to the requirements of the number of layers of the pull rods, so that the coaxiality error of the center of the pull rod on the workbench and the center of the corresponding through hole of the grids and the center of the preassembled fuel rod is ensured to be within an allowable range, and in the process of pulling the rods, the scraping between the fuel rods and 11 grids can be reduced as much as possible, the surface quality of the fuel rods is ensured, and the stress distortion of the grids is reduced. Therefore, the lifting precision of the main pull rod workbench is very important for the whole pull rod quality, as shown in fig. 2, in the embodiment, the four screw rod lifters are driven by the pull rod lifting servo driving mechanism 303 to lift by a servo motor, and as the screw rod lifters adopt trapezoidal screw rods with self-locking characteristics, the transmission clearance is larger, the synchronicity of the four screw rod lifters is not completely consistent, and meanwhile, the main pull rod workbench can repeatedly lift in 17 layers according to the process requirement, so that the positioning precision requirement of +/-0.05 mm is met, and the difficulty is very high.
In this embodiment, the lifting numerical control system is designed to a greater degree, firstly, a reference origin is set in the lifting process in a program, the reference origin is 20mm lower than the center height of the lowest layer of fuel rods, the main rod pulling workbench 301 is required to return to the reference origin and realign each time of lifting, in the process of recovering the reference origin again, the gap error in the trapezoid screw direction is eliminated, meanwhile, the synchronism error of four spiral screws is greatly reduced, and after the reference calibration, the fuel rods are lifted to the fuel rod layer required by the process again, and the rod pulling operation of the next layer is performed.
Meanwhile, in the transmission ratio setting, a smaller transmission ratio is arranged on the motor and the middle transmission element, so that the transmission ratio of the screw rod lifter is increased, and in the transmission process, the gap errors of a series of transmission components at the front end are greatly reduced after passing through the screw rod lifter, so that the influence on the final lifting height is reduced.
Finally, it is noted that the above-mentioned preferred embodiments are only intended to illustrate rather than limit the invention, and that, although the invention has been described in detail by means of the above-mentioned preferred embodiments, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the scope of the invention as defined by the appended claims.

Claims (9)

1. A nuclear fuel assembly pull rod system, characterized by: the device comprises a pull rod pre-boxing platform, a framework clamping platform and a pull rod host, wherein the framework clamping platform is arranged between the pull rod pre-boxing platform and the pull rod host, the pull rod pre-boxing platform and the pull rod host are both provided with moving mechanisms, the pull rod pre-boxing platform comprises a pre-boxing moving driving mechanism and a pre-boxing lifting mechanism, the framework clamping platform comprises a framework clamping frame, and the pull rod host comprises a pull rod main workbench, a pull rod selecting and positioning mechanism, a pull rod lifting servo driving mechanism and a pull rod main servo system;
the pull rod selecting and positioning mechanism comprises a slide carriage, a selecting rod cylinder, a selecting rod pull plate, a rotating shaft and a pull rod, wherein the selecting rod pull plate is connected with the slide carriage through the rotating shaft, a pull claw and a pull rod bayonet are arranged on the pull rod, each selecting rod pull plate is respectively and independently connected with the corresponding selecting rod cylinder and is embedded into the pull rod bayonet, and the slide carriage is connected with the pull rod through a pull rod hanging structure.
2. A nuclear fuel assembly tie rod system as defined in claim 1 wherein: the two rows of the rod selecting cylinders are arranged in a staggered mode.
3. A nuclear fuel assembly tie rod system as defined in claim 1 wherein: the pull rod hanging structure comprises a hanging groove arranged on the slide carriage, the pull rod connecting pull rod hanging seat is arranged in the hanging groove, and a guide groove is arranged below the pull rod.
4. A nuclear fuel assembly tie rod system as defined in claim 1 wherein: and a force sensor is arranged between the rod selecting pull plate and the slide carriage.
5. A nuclear fuel assembly tie rod system as defined in claim 4 wherein: the force sensor is an S-shaped force sensor.
6. A nuclear fuel assembly tie rod system as defined in claim 1 wherein: the framework clamping platform further comprises a turnover driving mechanism, the turnover driving mechanism comprises a turnover oil cylinder and a turnover main beam, the turnover main beam is hinged with the framework clamping platform through a main hinge, the turnover oil cylinder is arranged in a diagonal manner, and a front hinge support point of the turnover oil cylinder is arranged in the middle of the turnover main beam.
7. A nuclear fuel assembly tie rod system as defined in claim 1 wherein: the preassembling box moving driving mechanism comprises a roller way.
8. A nuclear fuel assembly pulling process based on the nuclear fuel assembly pulling system of claim 7, wherein: comprises the steps of,
a. welding and combining the grids and the guide pipes in advance to form a framework assembly, placing the framework on a framework clamping platform to be in position, clamping the grids on the framework, and adjusting, positioning and locking;
b. conveying the preassembled boxes with the preassembled fuel rods to a rod-pulling preassembling box platform through a roller way, and positioning, clamping and locking;
c. then starting a program, and moving the pull rod pre-boxing platform and the pull rod host towards the middle framework clamping platform;
d. the lifting servo driving mechanism of the pulling rod is controlled by a program to drive the workbench of the pulling rod host to lift to an accurate position, and the workbench is centered and positioned with one layer of 17 layers of through holes on the grid;
e. setting a rod selecting subprogram on a rod pulling host, and presetting a PLC program to independently control each cylinder according to different assembly specifications, selecting a pull rod, and simultaneously positioning and locking the pull rod which is not selected by utilizing the subsequent rod selecting cylinder;
f. starting a rod pulling program, servo-driving a slide carriage, pushing a pull rod by the slide carriage to advance towards the direction of the pre-packaged box through a grid, and grabbing a fuel rod through a pull claw arranged at the end part of the pull rod after the pull rod reaches a preset position;
g. starting the rod pulling program again, driving the slide carriage reversely, hanging the pull rod by the slide carriage, pulling the fuel rods out of the pre-assembled box, and sequentially passing through all grids on the framework to reach the preset position to finish rod pulling;
h. the main rod pulling workbench of the rod pulling host machine is subjected to height adjustment through a rod pulling lifting servo driving mechanism, and moves to the other layer, and the rod pulling steps are repeated until all fuel rods are pulled into 17 layers of holes of the grid;
i. starting a reset button, returning the preassembled box platform and the pull rod host to the original positions, and performing auxiliary operation;
j. the program control enables the framework clamping and overturning platform to rotate from a horizontal state to an upright state, and the nuclear fuel assembly completed by pulling the rods is lifted and separated, so that one working cycle is completed.
9. The nuclear fuel assembly pulling process of claim 8, wherein: in the process of pulling the rods, the total pulling force of each pull rod is continuously detected and output, and when the total pulling force exceeds a preset warning value, the control system alarms and immediately stops.
CN201710806637.3A 2017-09-08 2017-09-08 Nuclear fuel assembly pull rod system and process Active CN107610797B (en)

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Citations (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4175318A (en) * 1976-05-22 1979-11-27 Doryokuro Kakunenryo Kaihatsu Kigyodan Apparatus of assembling fuel rod bundle
JPS61116692A (en) * 1985-08-20 1986-06-04 三菱原子燃料株式会社 Pull-in device for cylindrical body
JPS62165192A (en) * 1986-01-16 1987-07-21 三菱原子燃料株式会社 Fuel aggregate assembling device
JPS63241496A (en) * 1987-03-30 1988-10-06 三菱原子燃料株式会社 Fuel aggregate assembling device
JPH05142388A (en) * 1991-11-08 1993-06-08 Mitsubishi Nuclear Fuel Co Ltd Assembling device for fuel assembly
US5251243A (en) * 1992-08-21 1993-10-05 Westinghouse Electric Corp. Automatic fuel assembly loader
CN1078064A (en) * 1992-04-28 1993-11-03 弗兰克巴尔日燃料制造公司 Be used for installing the method and apparatus of fuel rod at the nuclear fuel combined frame
FR2709202A1 (en) * 1993-08-20 1995-02-24 Fbfc Fuel assembly loading facility.
JP2001099986A (en) * 1999-10-01 2001-04-13 Nuclear Fuel Ind Ltd Fuel assembly assembling device for light water reactor
US6577698B1 (en) * 1998-12-22 2003-06-10 Societe Franco-Belge De Fabrication De Combusstible Fbfc Installation for loading fuel rods into a nuclear fuel assembly
CN205959624U (en) * 2016-08-30 2017-02-15 四川华都核设备制造有限公司 Pull -rod machine pull rod controlling means
CN205984291U (en) * 2016-08-30 2017-02-22 四川华都核设备制造有限公司 Pull -rod machine pull rod controlling means with pull rod selects pole function
CN206021919U (en) * 2016-08-30 2017-03-15 四川华都核设备制造有限公司 A kind of fuel assembly assembling mechanism with defencive function
CN206075840U (en) * 2016-08-30 2017-04-05 四川华都核设备制造有限公司 A kind of rod drawer
CN106935282A (en) * 2015-12-31 2017-07-07 中核建中核燃料元件有限公司 A kind of water lubrication device that pull-rod is assembled for fuel rod
CN207182919U (en) * 2017-09-08 2018-04-03 中机中联工程有限公司 A kind of nuclear fuel assembly pull-rod system

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6895067B2 (en) * 2002-04-30 2005-05-17 Framatome Anp, Inc. Smooth collet for pulling fuel rods

Patent Citations (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4175318A (en) * 1976-05-22 1979-11-27 Doryokuro Kakunenryo Kaihatsu Kigyodan Apparatus of assembling fuel rod bundle
JPS61116692A (en) * 1985-08-20 1986-06-04 三菱原子燃料株式会社 Pull-in device for cylindrical body
JPS62165192A (en) * 1986-01-16 1987-07-21 三菱原子燃料株式会社 Fuel aggregate assembling device
JPS63241496A (en) * 1987-03-30 1988-10-06 三菱原子燃料株式会社 Fuel aggregate assembling device
JPH05142388A (en) * 1991-11-08 1993-06-08 Mitsubishi Nuclear Fuel Co Ltd Assembling device for fuel assembly
CN1078064A (en) * 1992-04-28 1993-11-03 弗兰克巴尔日燃料制造公司 Be used for installing the method and apparatus of fuel rod at the nuclear fuel combined frame
US5251243A (en) * 1992-08-21 1993-10-05 Westinghouse Electric Corp. Automatic fuel assembly loader
FR2709202A1 (en) * 1993-08-20 1995-02-24 Fbfc Fuel assembly loading facility.
US6577698B1 (en) * 1998-12-22 2003-06-10 Societe Franco-Belge De Fabrication De Combusstible Fbfc Installation for loading fuel rods into a nuclear fuel assembly
JP2001099986A (en) * 1999-10-01 2001-04-13 Nuclear Fuel Ind Ltd Fuel assembly assembling device for light water reactor
CN106935282A (en) * 2015-12-31 2017-07-07 中核建中核燃料元件有限公司 A kind of water lubrication device that pull-rod is assembled for fuel rod
CN205959624U (en) * 2016-08-30 2017-02-15 四川华都核设备制造有限公司 Pull -rod machine pull rod controlling means
CN205984291U (en) * 2016-08-30 2017-02-22 四川华都核设备制造有限公司 Pull -rod machine pull rod controlling means with pull rod selects pole function
CN206021919U (en) * 2016-08-30 2017-03-15 四川华都核设备制造有限公司 A kind of fuel assembly assembling mechanism with defencive function
CN206075840U (en) * 2016-08-30 2017-04-05 四川华都核设备制造有限公司 A kind of rod drawer
CN207182919U (en) * 2017-09-08 2018-04-03 中机中联工程有限公司 A kind of nuclear fuel assembly pull-rod system

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
核电站用燃烧棒组件组装——拉棒机控制系统的研制;刘东波 等;《低压电器》(第1期);第26-29页 *

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