CN117871274A - Full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device - Google Patents
Full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device Download PDFInfo
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- CN117871274A CN117871274A CN202311735121.6A CN202311735121A CN117871274A CN 117871274 A CN117871274 A CN 117871274A CN 202311735121 A CN202311735121 A CN 202311735121A CN 117871274 A CN117871274 A CN 117871274A
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- Prior art keywords
- sample
- sealing
- cladding tube
- internal pressure
- test
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- 238000005253 cladding Methods 0.000 title claims abstract description 107
- 238000012360 testing method Methods 0.000 title claims abstract description 72
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 22
- 238000007789 sealing Methods 0.000 claims abstract description 64
- 238000005520 cutting process Methods 0.000 claims abstract description 25
- 238000003698 laser cutting Methods 0.000 claims description 10
- 239000002699 waste material Substances 0.000 claims description 6
- 238000004064 recycling Methods 0.000 claims description 3
- 238000012546 transfer Methods 0.000 abstract description 9
- 238000000034 method Methods 0.000 abstract description 8
- 238000002360 preparation method Methods 0.000 abstract description 8
- 210000001503 joint Anatomy 0.000 abstract description 3
- 239000000523 sample Substances 0.000 description 132
- 239000007789 gas Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 238000005086 pumping Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 239000013068 control sample Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 230000036316 preload Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
Classifications
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to a full-automatic after-irradiation nuclear fuel cladding internal pressure mechanical test device, which comprises a hot chamber, wherein the hot chamber is internally provided with: a furnace body; a cutting module for cutting out a cladding tube sample of a set length; the assembly module is used for inserting the core rod into the cladding tube sample, and locking two sealing fittings at two ends of the cladding tube sample to form a sealing sample piece; the sample assembling and disassembling module is used for installing the sealing sample piece into the furnace body for test or disassembling and recovering the sealing sample piece in the furnace body; and a manipulator for gripping, transferring, and manipulating the cladding tube sample, the sealing fitting, the sealing sample. The test device can realize operations such as fixed-length preparation, transfer, high-temperature high-pressure sealing assembly, butt joint assembly with a test furnace body and the like of a cladding tube sample before a test, and automatic sample disassembly operation after the test, thereby overcoming technical limitations and problems of scattered operation process, excessive manual intervention, low test efficiency, high operation threshold of test personnel and high risk of human misoperation of the current main stream device.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device.
Background
The nuclear fuel cladding is required to evaluate the material performance by an internal pressure mechanical test due to the operation characteristics of bearing internal and external pressures. The internal pressure mechanical test of the cladding relates to test operations such as sample preparation of fixed-length test, high-temperature high-pressure sealing assembly, sample assembly and sample disassembly of the sample in a test furnace body.
Because the irradiated nuclear fuel cladding has radioactivity and cannot be manually and accurately operated, the matured mechanical test device is matched with a hot chamber manipulator and a mechanical assembly platform to carry out the internal pressure mechanical test of the irradiated nuclear fuel cladding, the device has the advantages of multiple manual intervention and scattered operation in the test process, high requirement on the manipulator operation skill of a test operator, low test operation efficiency and high risk of manual introduction misoperation.
Disclosure of Invention
The invention aims to solve the technical problem of providing a full-automatic after-irradiation nuclear fuel cladding internal pressure mechanical test device aiming at the defects in the prior art.
The technical scheme adopted for solving the technical problems is as follows: the device for testing the internal pressure mechanics of the nuclear fuel cladding after full-automatic irradiation comprises a hot chamber, wherein the hot chamber is internally provided with: a furnace body;
a cutting module for cutting out a cladding tube sample of a set length;
the assembly module is used for inserting a core rod into the cladding tube sample, and locking two sealing fittings at two ends of the cladding tube sample to form a sealing sample piece;
the sample assembling and disassembling module is used for installing the sealing sample into the furnace body for test or disassembling and recovering the sealing sample in the furnace body; and
and the manipulator is used for grabbing, transferring and operating the cladding tube sample, the sealing fitting and the sealing sample.
In some embodiments, the cutting module comprises a laser cutting head, a sample stage that grips one end of the sample before cutting the cladding tube sample and allows the cladding tube sample to rotate along its own axis.
In some embodiments, the sample manipulation stage comprises two chucks and a rotating head rotatably provided on the chucks, respectively, the chucks being moved closer to or away from each other to allow the rotating head to clamp and unclamp the cladding tube sample, and to allow the rotating head and the cladding tube sample to rotate synchronously after clamping the cladding tube sample.
In some embodiments, the cutting module further comprises a collection box that collects waste material resulting from the cutting.
In some embodiments, the assembly module includes a slidably disposed bracket, a sleeve positioned over the cladding tube sample, and a first clamping jaw disposed on the bracket for clamping and locking or removing the sealing fitting to or from the cladding tube sample.
In some embodiments, the assembly module further comprises a base, and a first guide rail for sliding the bracket is arranged on the base.
In some embodiments, the bracket is provided with a second guide rail for the first clamping jaw to move up and down, and a limiting structure for limiting the movement range of the first clamping jaw.
In some embodiments, the seal assembly includes a guide end cap and an input end cap mounted at each end of a mandrel;
the assembling and disassembling sample module comprises a guide rod in the furnace body, a fixed port and a second clamping jaw arranged outside the furnace body, wherein a sealing sample piece of the guide end cover is arranged on the guide rod, radially fixed to the sealing sample piece and axially guided;
the input end cover of the sealing sample piece is fixedly installed on the fixed port so as to be connected with a pressure source through the fixed port, and the second clamping jaw clamps the guide end cover so as to enable the manipulator to disassemble and assemble the input end cover and the fixed port.
In some embodiments, the input end cap of the seal sample is secured to the stationary port by a fastener fastening arrangement,
in some embodiments, the manipulator comprises a manipulator arm and a mechanical clamp arranged on the manipulator arm, wherein the mechanical clamp comprises a third clamping jaw used for clamping one end of a cladding tube sample and driving the cladding tube sample to rotate along an axis, a fourth clamping jaw used for clamping a sealing accessory, a fifth clamping jaw used for clamping the cladding tube sample, and a wrench used for rotating disassembly.
The full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device has the following beneficial effects: the automatic process of the test device can realize the operations of fixed-length preparation, transfer, high-temperature and high-pressure sealing assembly, butt joint assembly with a test furnace body and the like of a cladding tube sample before the test, and the automatic sample disassembling operation after the test overcomes the technical limitations and problems of scattered operation process, excessive manual intervention, low test efficiency, high operation threshold of test personnel and high risk of human misoperation of the current main stream device.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic diagram of a full-automatic post-irradiation nuclear fuel containment internal pressure mechanical test device in an embodiment of the invention;
FIG. 2 is a schematic view of the structure of the heating chamber in FIG. 1;
FIG. 3 is a schematic diagram of an assembled structure of a seal sample to be tested;
FIG. 4 is an exploded view of the seal sample of FIG. 3;
FIG. 5 is a schematic view of the cutting module of FIG. 2;
FIG. 6 is a schematic view of the assembly module of FIG. 2;
FIG. 7 is a schematic view of the cartridge of FIG. 2;
FIG. 8 is a schematic view of the manipulator of FIG. 2;
fig. 9 is a schematic view of the mechanical clamp of fig. 8.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings.
As shown in fig. 1 to 4, the full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device in a preferred embodiment of the present invention comprises a main control room 1 and a hot room 2, wherein the main control room 1 comprises a computer main control system, an electrical control system, an internal pressure control system, a temperature control system, a cooling circulation system and an industrial robot control system, and can be used for controlling the environment and the work of parts in the hot room 2, and a furnace body 21, a cutting module 22, an assembling module 23, a sample assembling and disassembling module 24 and a manipulator 25 are arranged in the hot room 2.
The furnace body 21 is in a high-temperature vacuum environment, a temperature and vacuum environment is provided for carrying out an internal pressure mechanical test of the cladding, and a strain measurement module is configured for measuring the strain quantity of the sealing sample piece 3 in the test process.
The internal pressure control system uses inert gas or liquid with stable property as medium to form a pressure source to apply pressure in the sealing sample piece 3, and provides pressure input for the internal pressure test of the cladding of the sealing sample piece 3 in the furnace body 21, wherein the pressure can be stable or alternate in a certain frequency or be lifted at a certain speed.
The temperature control system provides uniform and stable temperature for the sealing sample piece 3 through a closed-loop control system consisting of a temperature control meter, a thermocouple and a heating body. The vacuum pumping system 4 provides a vacuum-like environment for the furnace body 21 by using a vacuum pumping system consisting of a rotary vane type mechanical pump and a diffusion pump or a molecular pump, and prevents high-temperature oxidation. The cooling water circulation system consists of an air-cooled chiller or a water-cooled chiller, a plurality of groups of water outlet pipes and water return pipes, and is used for circularly cooling the cavity of the furnace body 21 and the vacuum system.
The electric control system consists of a logic controller PLC, a control card or other devices with logic control functions, a relay, a contactor and a switch, and is used for supplying power to other systems and performing electric logic control. The computer main control system consists of an industrial control computer, a signal communication card and upper computer software, and is responsible for controlling the temperature, the pressure and the movements of the industrial manipulator 25 and the clamp of the manipulator 25, and collecting and recording test data such as temperature, pressure, outer diameter, vacuum degree and the like.
In some embodiments, the cutting module 22 is used for cutting a cladding tube sample 31 with a set length, the assembling module 23 is used for inserting a core rod 32 into the cladding tube sample 31 and locking two sealing fittings at two ends of the core rod 32 to form a sealing sample piece 3, and the assembling and disassembling module 24 is used for installing the sealing sample piece 3 into the furnace body 21 for testing or removing and recycling the sealing sample piece 3 in the furnace body 21; the manipulator 25 is used for gripping, transferring and handling the cladding tube sample 31, the sealing fitting, the sealing sample 3. The sealing fitting comprises a guide end cap 33 and an input end cap 34 mounted at both ends of the cladding tube sample 31, respectively, and high pressure gas is input from the input end cap 34 inward to pressurize the sealing sample 3 at a set pressure.
In some embodiments, as shown in connection with fig. 5, the cutting module 22 includes a laser cutting head 221, a sample station 222, and a waste collection cartridge 223, the sample station 222 holding one end of the sample of the cladding tube sample 31 prior to cutting and allowing the cladding tube sample 31 to rotate along its own axis.
Specifically, in the present embodiment, the sample operating station 222 includes two chucks 2221, and a plurality of rotating heads 2222 respectively rotatably provided on the two chucks 2221, the two chucks 2221 may be moved away from or close to each other under the control of the electrical control system, the two chucks 2221 are moved close to allow the rotating heads 2222 to clamp the cladding tube sample 31, the two chucks 2221 are moved away from allow the rotating heads 2222 to unclamp the cladding tube sample 31, and simultaneously, after clamping the cladding tube sample 31, the rotating heads 2222 and the cladding tube sample 31 are allowed to rotate synchronously when the cladding tube sample 31 is driven to rotate about its own axis. Of course, after the two chucks 2221 are close to the rotating head 2222 to clamp the cladding tube sample 31, the sample operating platform 222 integrally rotates to drive the cladding tube sample 31 to rotate around its own axis.
As the sample is rotated, the laser cutting head 221 is operated to cut the sample to obtain a cladding tube sample 31 of a set length. The waste generated during the cutting process falls to the waste collection box 223 for recycling.
As shown in connection with fig. 6, the assembly module 23 comprises a base 231, a bracket 232 slidably arranged on the base 231, a sleeve 233 positioned for the cladding tube sample 31, and a first clamping jaw 234 arranged on the bracket 232 for clamping and locking or removing the sealing fitting to or from the cladding tube sample 31, in particular, a first guide rail 235 for sliding the bracket 232 is arranged on the base 231, so that the position of the bracket 232 can be adjusted according to the position of the cladding tube sample 31, allowing the first clamping jaw 234 to install or remove the sealing fitting. In this embodiment, after the first clamping jaw 234 clamps the sealing fitting, the cladding tube sample 31 in the sleeve 233 is rotated to effect the disassembly of the sealing fitting.
Further, the bracket 232 is provided with a second guide rail 236 for the first clamping jaw 234 to move up and down, and a limit structure 237 for limiting the moving range of the first clamping jaw 234, so that the first clamping jaw 234 can move up and down in addition to moving in the horizontal direction, thereby meeting the installation requirement of the sealing accessory.
Referring to fig. 7, the assembling and disassembling module 24 includes a guide rod 241, a fixed port 242, and a second clamping jaw 243 disposed outside the furnace body 21, wherein the guide end cover 33 is mounted on the guide rod 241 to radially fix the seal sample 3 and axially guide the seal sample 3, so that the input end cover 34 is mounted and fixed on the fixed port 242 to be connected with an air source through the fixed port 242, and the second clamping jaw 243 clamps the guide end cover 33 to enable the manipulator 25 to assemble and disassemble the input end cover 34 and the fixed port 242.
Further, the input end cover 34 and the fixed port 242 are in threaded fit, and the manipulator 25 is used for fastening or loosening the input end cover 34 and the fixed port 242 in a threaded manner, so that the sample loading and unloading of the sealing sample piece 3 are completed. The input end cover 34 of the sealed sample piece 3 is connected with an air source through the fixed port 242 after sample loading, so that the pressure is conveniently injected into the sealed sample piece 3 for testing. Typically, the input end cap 34 is secured to the fixed port 242 by a fastener fastening arrangement, which also allows the input end cap 34 to be directly threadedly coupled to the fixed port 242.
As shown in connection with fig. 8 and 9, in some embodiments, the manipulator 25 comprises a manipulator 251 and a mechanical clamp 252 arranged on the manipulator 251, the mechanical clamp 252 comprises a third clamping jaw 2521 for clamping one end of the cladding tube sample 31 and driving the cladding tube sample 31 to rotate along an axis, a fourth clamping jaw 2522 for clamping a sealing fitting, a fifth clamping jaw 2523 for clamping the cladding tube sample 31, and a wrench 2524 for rotating and dismounting, in this embodiment, the third clamping jaw 2521 and the fourth clamping jaw 2522 are arranged on the same side of the mechanical clamp 252, the fourth clamping jaw 2522 is arranged on the side adjacent to the side on which the third clamping jaw 2521 is arranged, and on the opposite side of the side on which the manipulator 251 is connected to the mechanical clamp 252, and the wrench 2524 is arranged on the side adjacent to the side on which the manipulator 251 is connected to the mechanical clamp 252, in other embodiments, the clamping jaws 252 may be distributed on different sides of the mechanical clamp 252 in other manners.
When cutting a sample, the rotating head 2222 of the sample operation platform 222 is clamped at one end of the sample, the third clamping jaw 2521 is clamped at the other end of the sample, and the third clamping jaw 2521 drives the sample to rotate, so that the laser cutting head 221 cuts the sample to obtain the cladding tube sample 31 with a set length. The fifth jaw 2523 may clamp the cut resulting cladding tube sample 31, and the fourth jaw 2522 clamps sealing fittings mounted to both ends of the cladding tube sample 31.
Specifically, in the preparation of the test, the cladding tube sample, the seal fitting, and the core rod 32 to be subjected to the test are transferred to the material preparation table 5 at a specified position. The manipulator 25 completes debugging programming according to the design of the space motion track and is in the zeroing standby position.
After the start of the test, the cladding tube sample 31 is first cut to length. The specific implementation steps are as follows: the arm 251 of the control robot 25 is moved over the material rig, and the clamp body on the arm 251 is turned so that the third jaw 2521 provided thereon corresponds to the cladding tube sample to be tested. Subsequently, the third jaw 2521 is controlled to clamp one end of the cladding tube sample to be tested, and the mechanical arm 251 clamping the cladding tube sample to be tested is moved to correspond to the sample station 222 of the cutting module 22. The two chucks 2221 on the control sample station 222 are spaced apart from each other, and the other end of the cladding tube sample is extended into the two chucks 2221 by the third jaw 2521 until the cladding tube sample is to be cut corresponding to the laser cutting head 221, and the two chucks 2221 are controlled to be close to each other to clamp one end of the cladding tube sample. Subsequently, the laser cutting head 221 is activated and the third jaw 2521 rotates the cladding tube sample along its axis, thereby completing the laser cutting of one end of the cladding tube sample to obtain the exact fixed length cladding tube sample 31 required for the test. When the length after cutting one end is longer than the required cladding tube sample 31, the laser cutting head 221 may be rotated to cut after clamping the two ends again, or the cladding tube sample may be turned over to cut the other end by the laser cutting head 221 after clamping the two ends again.
After the fixed-length cutting of the cladding tube sample 31 is completed to obtain the cladding tube sample 31, the assembly of the sealing sample 3 needs to be completed for the cladding tube sample 31. The implementation steps are as follows: the third jaw 2521 of the arm 251 of the robot 25 transfers the cut cladding tube sample 31 into the sleeve 233 of the assembly module 23. The robot 25 transfers the guided end cap 33 assembly from the preparation platform to the first jaw 234 of the assembly module 23, replacing the fourth jaw 2522. The assembly module 23 is activated and the first clamping jaw 234 pre-loads and secures the leading end cap 33 in abutment with the cladding tube sample 31. The manipulator 25 rotates the guide end cap 33 by exchanging the torque wrench 2524, and the guide end cap 33 is fastened in threaded connection with the cladding tube sample 31. The first clamping jaw 234 of the assembly module 23 is released and the manipulator 25 is then replaced with the fifth clamping jaw 2523 to clamp and vertically invert the cladding tube sample 31 so that the guide end cap 33 fits into the sleeve 233 for securing. The control robot 25 again continues to grip the core rod 32 from the preparation table with the fifth jaw 2523 and transfers it into the cladding tube sample 31. The control manipulator 25 transfers the core rod 32 to the first clamping jaw 234 by replacing the fourth clamping jaw 2522, starts the automatic assembly module 23, enables the first clamping jaw 234 to move along the vertical second guide rail 236 and adjust to a proper position, locks the first clamping jaw 234, and enables the first clamping jaw 234 to butt-fit and fix the input end cover 34 with the cladding tube sample 31. The control manipulator 25 changes the wrench 2524, and controls the wrench 2524 to work to rotate the input end cover 34, so that the input end cover 34 is fastened with the cladding tube sample 31 in a threaded connection mode, and the cladding tube sample 31 is assembled in a sealing mode to form the sealing sample 3.
After the sealing sample piece 3 is assembled, the manipulator 25 is matched with the sample assembling and disassembling module 24 to assemble the sealing sample piece 3 in the test furnace body 21 before the test is completed. The sample loading implementation steps of the sealing sample piece 3 are as follows: the manipulator 25 is controlled to operate, the manipulator 25 transfers the sealing sample piece 3 from the assembling module 23 to the assembling and disassembling module 24 in the test furnace body 21 by replacing the fifth clamping jaw 2523, meanwhile, during transferring, the control input end cover 34 is connected with the fixing port 242 of the assembling and disassembling module 24, and the guide end cover 33 is fixed with the guide rod 241 of the assembling and disassembling module 24. After the sealing sample piece 3 is placed in place, the sample assembling and disassembling module 24 is started, the fourth clamping jaw 2522 clamps the guide end cover 33, and the manipulator 25 uses the wrench 2524 to replace the wrench 2524 to connect and screw the input end cover 34 with the fixed port 242, so that sample assembling is completed.
After loading is completed, the test may be started and a process record made. The specific test implementation steps are as follows: after the sample loading in the test furnace body 21 is completed, the test furnace body 21 is closed. The rest test steps are completed in the main control room 1, a cooling water circulation system and a vacuumizing system are started in sequence, when the vacuum degree reaches a specified value, the temperature control system is restarted, when the temperature and the vacuum degree meet the conditions, the internal pressure control system is restarted, and the gas of the control gas source enters the fixed port 242 to apply stable or alternating frequency or lifting pressure at a certain speed to the inside of the sealed sample piece 3. And the computer main control system collects and records test data such as time, temperature, pressure, outer diameter, vacuum degree and the like in real time until the test is finished.
After the test is finished, the manipulator 25 is matched with the sample assembling and disassembling module 24 to complete sample disassembling of the sealed sample piece 3 in the test furnace body 21. Specifically, the control manipulator 25 uses the torque wrench 2524 to loosen the threaded connection between the input end cover 34 and the fixed port 242, and then the control manipulator 25 uses the fifth clamping jaw 2523 to transfer the tested sample piece from the test furnace body 21 to the waste recovery box, so as to complete the whole test operation.
The invention can realize the operations of fixed-length preparation, transfer, high-temperature high-pressure sealing assembly, butt joint assembly with a test furnace body 21 and the like of a cladding tube sample after irradiation of one-key type before test, and the like, and overcomes the technical limitations and problems of scattered operation process, excessive manual intervention, low test efficiency, high operation threshold of test personnel and high risk of human misoperation of the current main stream device.
It will be appreciated that the above technical features may be used in any combination without limitation.
The foregoing description is only illustrative of the present invention and is not intended to limit the scope of the invention, and all equivalent structures or equivalent processes or direct or indirect application in other related technical fields are included in the scope of the present invention.
Claims (10)
1. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device is characterized by comprising a hot chamber (2), wherein the hot chamber (2) is internally provided with: a furnace body (21);
a cutting module (22) for cutting out a cladding tube sample (31) of a set length;
-an assembly module (23) for inserting a mandrel (32) into a cladding tube sample (31) and locking two sealing fittings to both ends of said cladding tube sample (31) forming a sealing sample (3);
the sample assembling and disassembling module (24) is used for installing the sealing sample piece (3) into the furnace body (21) for test or removing and recycling the sealing sample piece (3) in the furnace body (21); and
and the manipulator (25) is used for grabbing, transferring and operating the cladding tube sample (31), the sealing fitting and the sealing sample piece (3).
2. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device according to claim 1, wherein the cutting module (22) comprises a laser cutting head (221) and a sample operating table (222), and the sample operating table (222) clamps one end of a sample before cutting the cladding tube sample (31) and enables the cladding tube sample (31) to rotate along the self axis.
3. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device according to claim 2, wherein the sample handling station (222) comprises two chucks (2221) and rotating heads (2222) rotatably arranged on the two chucks (2221), respectively, the chucks (2221) are close to or far away from each other to allow the rotating heads (2222) to clamp and unclamp cladding tube samples (31), and after clamping the cladding tube samples (31), the rotating heads (2222) and the cladding tube samples (31) can synchronously rotate.
4. The full-automatic post-irradiation nuclear fuel containment internal pressure mechanical test device of claim 2, wherein the cutting module (22) further comprises a collection box (223) that collects waste generated by cutting.
5. The fully automated post-irradiation nuclear fuel cladding internal pressure mechanical test device according to claim 1, wherein the assembly module (23) comprises a slidably arranged bracket (232), a sleeve (233) positioning the cladding tube sample (31), and a first clamping jaw (234) arranged on the bracket (232) for clamping and locking the sealing fitting onto the cladding tube sample (31) or removing the sealing fitting from the cladding tube sample (31).
6. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device according to claim 5, wherein the assembly module (23) further comprises a base (231), and a first guide rail (235) for sliding the bracket (232) is arranged on the base (231).
7. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device according to claim 5, wherein the bracket (232) is provided with a second guide rail (236) for the first clamping jaw (234) to move up and down, and a limiting structure (237) for limiting the movement range of the first clamping jaw (234).
8. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device according to any one of claims 1 to 7, wherein the sealing fitting comprises a guide end cover (33) and an input end cover (34) respectively mounted at both ends of a mandrel (32);
the sample assembling and disassembling module (24) comprises a guide rod (241) in the furnace body (21), a fixed port (242) and a second clamping jaw (243) arranged outside the furnace body (21), wherein a guide end cover (33) is used for sealing a sample piece (3) and is mounted on the guide rod (241), radially fixing the sealing sample piece (3) and axially guiding the sealing sample piece;
the input end cover (34) of the sealing sample piece (3) is fixedly installed on the fixed port (242) so as to be connected with a pressure source through the fixed port (242), and the second clamping jaw (243) clamps the guide end cover (33) so as to enable the manipulator (25) to be detached from the input end cover (34) and the fixed port (242).
9. The fully automated post-irradiation nuclear fuel cladding internal pressure mechanical test device according to claim 8, wherein an input end cap (34) of the sealing sample (3) is secured to the securing port (242) by a locking fastener fastening mount.
10. The full-automatic post-irradiation nuclear fuel cladding internal pressure mechanical test device according to any one of claims 1-7, wherein the manipulator (25) comprises a manipulator (251) and a mechanical clamp (252) provided on the manipulator (251), the mechanical clamp (252) comprising a third jaw (2521) for clamping one end of a cladding tube sample (31) and rotating the cladding tube sample (31) along an axis, a fourth jaw (2522) for clamping a sealing fitting, a fifth jaw (2523) for clamping the cladding tube sample (31), and a wrench (2524) for rotating the disassembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311735121.6A CN117871274A (en) | 2023-12-15 | 2023-12-15 | Full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311735121.6A CN117871274A (en) | 2023-12-15 | 2023-12-15 | Full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117871274A true CN117871274A (en) | 2024-04-12 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311735121.6A Pending CN117871274A (en) | 2023-12-15 | 2023-12-15 | Full-automatic irradiation post-nuclear fuel cladding internal pressure mechanical test device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117871274A (en) |
-
2023
- 2023-12-15 CN CN202311735121.6A patent/CN117871274A/en active Pending
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