CN219180205U - Gripping apparatus for replacing reactor pressure vessel detector - Google Patents
Gripping apparatus for replacing reactor pressure vessel detector Download PDFInfo
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- CN219180205U CN219180205U CN202223373958.4U CN202223373958U CN219180205U CN 219180205 U CN219180205 U CN 219180205U CN 202223373958 U CN202223373958 U CN 202223373958U CN 219180205 U CN219180205 U CN 219180205U
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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
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Abstract
The utility model belongs to the technical field of pressurized water reactor nuclear power plant refueling and overhaul, and particularly relates to a detector gripping apparatus for replacing a reactor pressure vessel, which comprises the following components: the device comprises a lifting ring, a bracket, a cylinder driving mechanism, a core bar connecting piece, a moment transmission sleeve, a spring, a main supporting mechanism, a core bar, a locking mechanism and a plurality of sleeve connecting rods; the top of the bracket is in threaded connection with a hanging ring, and an air cylinder driving mechanism is arranged in the bracket; the bottom of the bracket is connected with the top of the torque transmission sleeve through a plurality of sleeve connecting rods; the torque transmission sleeve is internally provided with a main supporting mechanism, the outer surface of the main supporting mechanism is sleeved with a spring, the main supporting mechanism is internally provided with a core rod, the top end of the core rod is arranged at the top end of the main supporting mechanism through a core rod connecting piece, and the outer wall of the bottom of the main supporting mechanism is hinged with a locking mechanism. The utility model solves the technical problem of jamming of the gripping apparatus in the process of uncovering the reactor core pressure vessel in the process of reloading and overhaul of the existing nuclear power unit.
Description
Technical Field
The utility model belongs to the technical field of pressurized water reactor nuclear power plant refueling and overhaul, and particularly relates to a gripper for replacing a reactor pressure vessel detector.
Background
The three-generation nuclear power technology in China has changed the bottom insertion type finger sleeve of the reactor pressure vessel into a reactor top integrated detector assembly, and the total number of the finger sleeve is 24, so that the safety of a reactor core measurement system is improved. The reactor core measuring system introduces a neutron-temperature detector assembly from the top of the reactor core pressure vessel, and the detector assembly is required to be replaced every refueling period according to design requirements. The original equipment is from detector module demolishs instrument that takes, has the phenomenon of gripping apparatus jam in the detector module change process in the reloading cycle, easily causes the influence to reloading overhaul period, also causes the influence to operating personnel's professional irradiation under high radioactive environment dosage simultaneously.
Therefore, an improved gripping apparatus for replacing a reactor pressure vessel detector and a replacing method thereof are needed to be designed, and the technical problem of gripping apparatus jam in the process of overhauling the cover opening of the reactor core pressure vessel in the process of refueling of a nuclear power unit in the prior art is solved.
Disclosure of Invention
The utility model provides a gripping apparatus for replacing a reactor pressure vessel detector, which is used for solving the technical problem of gripping of the gripping apparatus in the process of uncovering a reactor core pressure vessel in the process of refueling and overhaul of an existing nuclear power unit.
The technical scheme of the utility model is as follows:
a probe gripper for replacing a reactor pressure vessel, comprising: the device comprises a lifting ring, a bracket, a cylinder driving mechanism, a core bar connecting piece, a moment transmission sleeve, a spring, a main supporting mechanism, a core bar, a locking mechanism and a plurality of sleeve connecting rods; the top of the bracket is in threaded connection with a hanging ring, and an air cylinder driving mechanism is arranged in the bracket; the bottom of the bracket is connected with the top of the torque transmission sleeve through a plurality of sleeve connecting rods; the torque transmission sleeve is internally provided with a main supporting mechanism, the outer surface of the main supporting mechanism is sleeved with a spring, the main supporting mechanism is internally provided with a core rod, the top end of the core rod is arranged at the top end of the main supporting mechanism through a core rod connecting piece, and the outer wall of the bottom of the main supporting mechanism is hinged with a locking mechanism.
The center of the bottom of the bracket is provided with a cylinder driving mechanism movement through hole, and the cylinder driving mechanism moves up and down in the bracket through the cylinder driving mechanism movement through hole.
A plurality of sleeve connecting rod threaded holes are further formed in the periphery of the moving through hole of the bottom cylinder driving mechanism of the bracket and are used for penetrating and fixing the sleeve connecting rods; one end of each sleeve connecting rod penetrates into the sleeve connecting rod threaded hole and is in threaded connection with the bottom of the bracket, and the other end of the sleeve connecting rod is fixedly connected with the main supporting mechanism inside the torque transmission sleeve.
The main supporting mechanism is of a hollow cylinder structure as a whole, the moment transmission sleeve moves up and down along the outer wall of the main supporting mechanism through an air cylinder driving mechanism, and a groove is formed in the bottom of the outer wall of the main supporting mechanism.
The locking mechanism comprises four hook claws, one ends of the four hook claws are uniformly fixed on the outer wall of the bottom of the main supporting mechanism, and when the torque transmission sleeve moves downwards along the outer wall of the main supporting mechanism, the hook claws on the locking mechanism are folded to be meshed with the detector assembly;
when the torque transmission sleeve moves upwards along the outer wall of the main supporting mechanism, the spring downwards enters the groove, the hook claw on the locking mechanism is loosened, and the detector assembly is in a loosened state.
The utility model has the beneficial effects that:
the utility model relates to a gripping apparatus for replacing a reactor pressure vessel detector, which mainly comprises a cylinder driving part, a torque transmission sleeve, a main supporting mechanism and a locking mechanism, wherein the torque transmission sleeve is arranged outside the main supporting mechanism and can move up and down under the action of the cylinder driving part, and then the locking mechanism is driven to mutually convert between an engaged state and a released state. The device has a simpler structure, improves the reliability, reduces the jamming phenomenon of the gripping apparatus in the process of uncovering the pressure vessel of the reactor core during the refueling and overhaul of the nuclear power unit, reduces the occupational irradiation of environmental dose to operators in the operation process, and improves the replacement efficiency of the detector assembly; the device can be widely applied to nuclear power stations with detectors arranged at the tops of reactor core pressure vessels such as VVER/ACP1000 and the like, and is used for leading neutron-temperature detector assemblies out of the reactor from the top cover of the pressure vessel.
Drawings
Fig. 1 is a schematic view of a structure of a detector gripper for replacing a reactor pressure vessel according to the present utility model.
Wherein: 1-lifting ring, 2-support, 3-cylinder driving mechanism, 4-core bar connecting piece, 5-moment transmission sleeve, 6-spring, 7-main supporting mechanism, 8-core bar, 9-locking mechanism and 10-sleeve connecting rod
Detailed Description
The present utility model will be described in detail with reference to the drawings and examples for replacing a reactor pressure vessel probe gripper and a replacement method thereof.
A probe gripper for replacing a reactor pressure vessel, comprising: the device comprises a lifting ring 1, a bracket 2, a cylinder driving mechanism 3, a core bar connecting piece 4, a moment transmission sleeve 5, a spring 6, a main supporting mechanism 7, a core bar 8, a locking mechanism 9 and a plurality of sleeve connecting rods 10; the top of the bracket 2 is in threaded connection with a hanging ring 1, and an air cylinder driving mechanism 3 is arranged in the bracket 2; the bottom of the bracket 2 is connected with the top of the torque transmission sleeve 5 through a plurality of sleeve connecting rods 10; the torque transmission sleeve 5 is internally provided with a main supporting mechanism 7, the outer surface of the main supporting mechanism 7 is sleeved with a spring 6, the inside of the main supporting mechanism 7 is provided with a core rod 8, the top end of the core rod 8 is arranged at the top end of the inside of the main supporting mechanism 7 through a core rod connecting piece 4, and the outer wall of the bottom of the main supporting mechanism 7 is hinged with a locking mechanism 9.
The center of the bottom of the bracket 2 is provided with a cylinder driving mechanism movement through hole, and the cylinder driving mechanism 3 moves up and down in the bracket 2 through the cylinder driving mechanism movement through hole.
A plurality of sleeve connecting rod threaded holes are further formed in the periphery of the motion through hole of the bottom cylinder driving mechanism of the bracket 2 and used for penetrating and fixing the sleeve connecting rods 10; one end of each sleeve connecting rod 10 penetrates into the sleeve connecting rod threaded hole and is in threaded connection with the bottom of the bracket 2, and the other end of each sleeve connecting rod 10 is fixedly connected with the main supporting mechanism 7 in the torque transmission sleeve 5.
The whole main supporting mechanism 7 is of a hollow cylinder structure, and the torque transmission sleeve 5 moves up and down along the outer wall of the main supporting mechanism 7 through the cylinder driving mechanism 3; the bottom of the outer wall of the main supporting mechanism 7 is provided with a groove.
The locking mechanism 9 comprises four hook claws, one ends of the four hook claws are uniformly fixed on the outer wall of the bottom of the main supporting mechanism 7, and when the air cylinder driving part is used for feeding air, the moment transmission sleeve 5 is meshed with the detector assembly when the moment transmission sleeve moves downwards along the outer wall of the main supporting mechanism 7;
when the cylinder drives the part to enter air downwards, the moment transmission sleeve 5 moves upwards along the outer wall of the main supporting mechanism 7, the spring 6 enters the groove downwards, the hook claw on the locking mechanism 9 is loosened, and the detector assembly is in a loosened state.
Examples:
the cylinder driving mechanism 3 is arranged above the main supporting mechanism 7; the cylinder driving mechanism 3 is connected with an air source and adopts a double-air-inlet cylinder structure. The cylinder driving mechanism 3 is connected with a torque transmission sleeve 5, the torque transmission sleeve 5 moves along the outer wall of the main supporting mechanism under the action of air source power, and the locking mechanism can realize the mutual conversion between the 'meshed' state and the 'released' state along with the movement of the torque transmission sleeve. By the grabbing method, the detector assembly can be quickly and accurately stretched into the torque transmission sleeve 5 and locked and fixed, the multi-layer sleeve is adopted to grab the detector assembly by combining the grabbing heads of the spring locking mechanism, the structure is simple and compact, and the detector assembly is operated in a small space. Under the cooperation of the full-automatic steel wire rope winding system and the air pipe winding system, the long-distance operation gripping device grips, lifts and transports the detector assembly in a high-emissivity water environment, so that the number of operators is reduced, the irradiation dose borne by the operators is reduced, the replacement efficiency of the detector assembly is improved, and the economical efficiency of a reactor is improved.
The embodiments of the present utility model have been described in detail, but the present utility model is not limited to the above examples, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present utility model.
Claims (5)
1. A probe gripper for replacing a reactor pressure vessel, comprising: the device comprises a lifting ring (1), a bracket (2), an air cylinder driving mechanism (3), a core rod connecting piece (4), a moment transmission sleeve (5), a spring (6), a main supporting mechanism (7), a core rod (8), a locking mechanism (9) and a plurality of sleeve connecting rods (10); the top of the bracket (2) is in threaded connection with a hanging ring (1), and an air cylinder driving mechanism (3) is arranged in the bracket (2); the bottom of the bracket (2) is connected with the top of the torque transmission sleeve (5) through a plurality of sleeve connecting rods (10); the torque transmission sleeve (5) is internally provided with a main supporting mechanism (7), the outer surface of the main supporting mechanism (7) is annularly sleeved with a spring (6), a core rod (8) is arranged inside the main supporting mechanism (7), the top end of the core rod (8) is arranged at the top end inside the main supporting mechanism (7) through a core rod connecting piece (4), and the outer wall of the bottom of the main supporting mechanism (7) is hinged with a locking mechanism (9).
2. A gripper for replacing a reactor pressure vessel probe according to claim 1, wherein: the center of the bottom of the bracket (2) is provided with a cylinder driving mechanism movement through hole, and the cylinder driving mechanism (3) moves up and down in the bracket (2) through the cylinder driving mechanism movement through hole.
3. A gripper for replacing a reactor pressure vessel probe according to claim 2, wherein: a plurality of sleeve connecting rod threaded holes are further formed in the periphery of the motion through hole of the bottom cylinder driving mechanism of the bracket (2) and used for penetrating and fixing the sleeve connecting rods (10); one end of each sleeve connecting rod (10) penetrates into a sleeve connecting rod threaded hole and is in threaded connection with the bottom of the support (2), and the other end of each sleeve connecting rod (10) is fixedly connected with the main supporting mechanism (7) in the torque transmission sleeve (5).
4. A reactor pressure vessel probe gripper for replacement according to claim 3, wherein: the whole main supporting mechanism (7) is of a hollow cylinder structure, and the torque transmission sleeve (5) moves up and down along the outer wall of the main supporting mechanism (7) through the cylinder driving mechanism (3); the bottom of the outer wall of the main supporting mechanism (7) is provided with a groove.
5. A gripper for replacing a reactor pressure vessel probe according to claim 4, wherein: the locking mechanism (9) comprises four hook claws, one ends of the four hook claws are uniformly fixed on the outer wall of the bottom of the main supporting mechanism (7), and when the torque transmission sleeve (5) moves downwards along the outer wall of the main supporting mechanism (7), the hook claws on the locking mechanism (9) are folded to be meshed with the detector assembly;
when the torque transmission sleeve (5) moves upwards along the outer wall of the main supporting mechanism (7), the spring (6) downwards enters the groove, the hook claw on the locking mechanism (9) is loosened, and the detector assembly is in a loosened state.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202223373958.4U CN219180205U (en) | 2022-12-15 | 2022-12-15 | Gripping apparatus for replacing reactor pressure vessel detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202223373958.4U CN219180205U (en) | 2022-12-15 | 2022-12-15 | Gripping apparatus for replacing reactor pressure vessel detector |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN219180205U true CN219180205U (en) | 2023-06-13 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202223373958.4U Active CN219180205U (en) | 2022-12-15 | 2022-12-15 | Gripping apparatus for replacing reactor pressure vessel detector |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN219180205U (en) |
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2022
- 2022-12-15 CN CN202223373958.4U patent/CN219180205U/en active Active
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