WO2024061068A1 - 一种反应堆装换料系统及方法 - Google Patents

一种反应堆装换料系统及方法 Download PDF

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Publication number
WO2024061068A1
WO2024061068A1 PCT/CN2023/118445 CN2023118445W WO2024061068A1 WO 2024061068 A1 WO2024061068 A1 WO 2024061068A1 CN 2023118445 W CN2023118445 W CN 2023118445W WO 2024061068 A1 WO2024061068 A1 WO 2024061068A1
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WO
WIPO (PCT)
Prior art keywords
reactor
pressure vessel
refueling
lifting
bolt operating
Prior art date
Application number
PCT/CN2023/118445
Other languages
English (en)
French (fr)
Inventor
李雷
朱自强
刘润发
毛飞
朱雪锋
唐伟华
林绍萱
邵长磊
翁晨阳
刘建文
任文俊
刘永骏
吴为
黄尚青
李梦芝
Original Assignee
上海核工程研究设计院股份有限公司
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
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Application filed by 上海核工程研究设计院股份有限公司 filed Critical 上海核工程研究设计院股份有限公司
Publication of WO2024061068A1 publication Critical patent/WO2024061068A1/zh

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/205—Interchanging of fuel elements in the core, i.e. fuel shuffling
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • 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

Definitions

  • the invention relates to the technical field of nuclear power maintenance, and in particular to a reactor loading and refueling system and method.
  • the reactor loading and refueling system is a system that systematically solves the problem of opening the reactor cover and replacing the core fuel assembly.
  • the pressurized water stacking and refueling system adopts the method of opening the cover from above, that is, using a factory crane and special tools to remove the reactor top penetration piece and the reactor pressure vessel top cover in sequence from the top of the reactor. Then the control rod driving mechanism, upper internal components and internal measurement grid are lifted out in sequence, and then individual fuel assemblies are replaced in the reactor.
  • the disassembly and assembly of various penetration parts on the top of the reactor is a time-consuming part of the refueling path of a nuclear power plant.
  • core instrument penetration parts have been adopted.
  • the upper part penetrates the reactor pressure vessel, and the disassembly and assembly of the reactor pressure vessel from the upper part, including the numerous and complicated structures such as the core inspection penetration parts and core measurement instrument components, makes the disassembly and assembly process more difficult;
  • the purpose of the present invention is to provide a reactor loading and refueling system and method to overcome the long critical path caused by the refueling method of sequentially opening the lid from above used in the existing refueling technology. It solves the problem, simplifies the disassembly and assembly process and difficulty of the reactor top penetration, and provides an implementable implementation method for opening the cover and refueling of compact reactors such as integrated reactors.
  • a first aspect of the present invention provides a reactor loading and refueling system, which performs loading and refueling operations on a reactor pressure vessel with a downwardly opened cover, including: a bolt operating device, which is used to interface with the flange surface of the pressure vessel and connect the The bolts of the upper structure and lower structure of the pressure vessel are pre-tightened and disassembled, and can carry the disassembled lower structure of the pressure vessel; the lifting device is used to lift the lower structure or lower structure of the pressure vessel in the vertical direction.
  • the unloaded bolt operating device is lifted and lowered, and its lifting stroke can meet the complete separation of the lower structure and the upper structure of the pressure vessel; the attitude adjustment device is used to adjust the bolt operating device to realize the flange surface of the bolt operating device and the pressure vessel. Achieve precise docking; transfer device, which is used to transfer the bolt operating device, lifting device and attitude adjustment device loaded with the lower structure of the pressure vessel or unloaded between the reactor cavity position and the transfer position, wherein the bolt operation device
  • the device, lifting device, attitude adjustment device and transfer device are located underwater in the reactor core pool.
  • the attitude adjustment device is set on the top of the lifting device.
  • the bolt operating device is connected to the attitude adjustment device.
  • the lifting device is fixedly connected to the transfer device. The device can drive the lifting device, the attitude adjustment device and the bolt operating device installed on the lifting device to move in the horizontal direction.
  • the reactor loading and refueling system of the present invention also includes a guide device, which includes a plurality of pairs of mechanical guide pairs located on the bolt operating device and the pressure vessel respectively, which can provide guidance for the lifting device during the lifting process.
  • a guide device which includes a plurality of pairs of mechanical guide pairs located on the bolt operating device and the pressure vessel respectively, which can provide guidance for the lifting device during the lifting process.
  • the reactor loading and refueling system of the present invention also includes a lifting platform, which is arranged at a transfer position outside the reactor cavity to lift and lower the transfer device moved to the transfer position in the vertical direction.
  • the reactor loading and refueling system of the present invention also includes a refueling stand, which is arranged underwater in the spent pool area and above the lifting platform, and can carry and store the lower structure of the unloaded pressure vessel; and a refueling machine, which performs the replacement operation of the core fuel assembly on the refueling stand.
  • a refueling stand which is arranged underwater in the spent pool area and above the lifting platform, and can carry and store the lower structure of the unloaded pressure vessel; and a refueling machine, which performs the replacement operation of the core fuel assembly on the refueling stand.
  • the reactor loading and refueling system of the present invention also includes a spreader, which can lift the lower structure of the pressure vessel stored on the refueling platform; and a bridge crane, which is connected to the spreader and integrates the spreader and the lower structure. Make the transfer.
  • a spreader which can lift the lower structure of the pressure vessel stored on the refueling platform
  • a bridge crane which is connected to the spreader and integrates the spreader and the lower structure. Make the transfer.
  • a track is provided at the bottom of the core pool.
  • the track is located between the bottom of the pressure vessel and the lifting platform, and the transfer device can move horizontally on the track.
  • the attitude adjustment device consists of a coaxially arranged rotary platform and a translation platform.
  • the rotary platform is fixedly installed on the top of the lifting device.
  • the translation platform is located above the rotary platform and is connected to the rotary platform through a universal ball bearing and screw guide mechanism. Connection, the translation platform is a circular ring structure, and the bolt operating device is fixedly installed on the translation platform.
  • the slewing platform consists of a lower slew unit and an upper slew unit driven by a hydraulic cylinder. Both the upper slew unit and the lower slew unit are annular structures. The lower slew unit and the upper slew unit are coaxially arranged and connected through bearings.
  • the universal ball bearing and the screw guide mechanism are both fixedly installed on the upper rotary unit.
  • the screw guide mechanism is divided into an X-axis mechanism and a Y-axis mechanism.
  • the X-axis mechanism is fixedly installed on the upper rotary unit, and the Y-axis mechanism slides It is set on the X-axis mechanism, and the translation platform is slidably set on the Y-axis mechanism.
  • a second aspect of the present invention provides a reactor loading and refueling method, which utilizes the reactor loading and refueling system as described above to perform a loading and refueling operation on a reactor pressure vessel with a downwardly opened lid, which includes the following steps:
  • the attitude adjustment device adjusts the position, horizontality and radial azimuth of the bolt operating device to achieve docking with the flange surface of the reactor pressure vessel;
  • the bolt operating device, lifting device and attitude adjustment device loaded with the lower structure of the pressure vessel or unloaded are transferred between the reactor cavity position and the transfer position through the transfer device.
  • the present invention adopts a reactor loading and refueling system with a downward opening cover. After the reactor cover is opened and transferred, the core fuel assembly replacement operation can be performed in a tight sequence. Compared with the existing pressurized water reactor refueling technology, the reactor refueling system can be started sequentially from above. The series of operations of the cover are separated from the critical path of refueling. Even if the upper parts of the reactor need to be further disassembled for in-service inspections, etc., they can be carried out simultaneously with the subsequent core fuel assembly replacement operations, shortening the overhaul path and improving power plant operation and maintenance.
  • the refueling method of opening the cover downward can overcome the complex disassembly and assembly problems of the reactor top penetration parts, which is beneficial to third-generation pressurized water reactors and compact small reactors where it is difficult to disassemble and install the top penetration parts. reactor.
  • the invention adopts a refueling method with the cover opened downward. After the lower structure of the reactor pressure vessel is transferred as a whole, open refueling can be performed above the core, which greatly reduces the difficulty of the replacement operation of the core fuel assembly and is beneficial to the internal operation of the reactor.
  • Compact reactors such as integrated reactors are compact and narrow in space, making it difficult to refuel in traditional ways.
  • Figure 1 is a schematic diagram of the first state of refueling (the transfer device moves to the reactor cavity position) of a pressurized water reactor according to one or more embodiments of the present invention
  • Figure 2 is a schematic diagram of the second state (the lifting device is lifted into place) of refueling the pressurized water reactor according to one or more embodiments of the present invention
  • FIG. 3 is a schematic diagram of a pressurized water reactor in a third state of refueling (the posture adjustment device is adjusted in place to achieve flange docking) according to one or more embodiments of the present invention
  • Figure 4 is a schematic diagram of the fourth state (the bolt operating device realizes the disassembly of the flange surface) of the pressurized water reactor according to one or more embodiments of the present invention for refueling;
  • Figure 5 is a schematic diagram of the fifth state (the lifting device is lowered) of refueling the pressurized water reactor according to one or more embodiments of the present invention
  • Figure 6 is a schematic diagram of the sixth state (the transfer device operates to the transfer position) of refueling the pressurized water reactor according to one or more embodiments of the present invention
  • Figure 7 is a schematic diagram of the seventh state of refueling of the pressurized water reactor according to one or more embodiments of the present invention (the lower structure of the reactor pressure vessel is hoisted to the refueling platform);
  • Figure 8 is a schematic diagram of the eighth state (core refueling) of the pressurized water reactor according to one or more embodiments of the present invention.
  • Figure 9 is a schematic diagram of the ninth state of refueling of the pressurized water reactor (reactor pressure vessel substructure reassembly) according to one or more embodiments of the present invention.
  • FIG. 10 is a schematic diagram of a pressurized water reactor in a tenth state of refueling (the transfer vehicle is lifted to the operating platform by the lifting platform) according to one or more embodiments of the present invention
  • FIG. 11 is a schematic diagram of the front view of the posture adjustment device according to one or more embodiments of the present invention.
  • FIG. 12 is a view taken along line A-A in FIG. 11 .
  • the existing method of refueling in the reactor after opening the cover sequentially from above has a long critical path for refueling, disassembling and assembling the core inspection penetration parts and core measurement instrument components from the upper part, etc. are numerous and complex, and the disassembly and assembly process is more complex. Difficult problem, in order to solve the above technical problems, the present invention proposes a reactor loading and refueling system and method.
  • Figure 1 is a schematic diagram of the first state of refueling (the transfer device moves to the reactor cavity position) of a pressurized water reactor according to one or more embodiments of the present invention.
  • the reactor loading and refueling system 100 of this embodiment performs loading and refueling operations on the reactor pressure vessel 8 with the cover downwards opened, and includes a bolt operating device 1, a lifting device 2, an attitude adjustment device 3 and a transfer device. Device 4.
  • the reactor pressure vessel 8 with the cover downwards is a pressure vessel with a refueling flange and internal components, that is, it is divided into a vessel shell and internal components (in order to explain the gist of the present invention in detail, in Figure 1 and other drawings (Internal components unrelated to the present invention are not shown), in which the container shell is divided into an upper shell and a lower shell.
  • the container part located above the refueling flange is the upper shell, which can be connected through its own structure.
  • the upper shell and the control rod inside The driving mechanism, upper internal components, and internal measurement grid (not shown) together form an integrated upper structure 81.
  • the container part located below the refueling flange is the lower shell, which can carry the core basket 9 and the reactor core.
  • the cores together form the lower structure 82 , and the upper structure 81 and the lower structure 82 are connected by bolts 83 .
  • the core basket 9 is a basket structure with an integral frame that contains the core. It is used to achieve overall hoisting of the core and refueling outside the reactor. Its structure can accommodate all fuel assemblies in the core and perform integral hoisting.
  • the bolt operating device 1 is used to dock with the flange surface 84 of the pressure vessel 8 , perform pre-tightening and disassembly operations on the bolts 83 connecting the upper structure 81 and the lower structure 82 of the pressure vessel 8 , and can carry the disassembled pressure vessel 8 of substructure 82.
  • the bolt operating device 1 includes a pallet 101 and several independent automatic bolt disassembly and assembly mechanisms and several independent automatic bolt pretensioning mechanisms.
  • the pallet 101 is fixed on the attitude adjustment device 3 through a bracket and can be connected to the flange of the reactor pressure vessel 8
  • the lower edge of the surface 84 is butted and carries the weight of the substructure 82 of the reactor pressure vessel 8 during the lifting process.
  • the automatic bolt disassembly/assembly mechanism and the automatic bolt pre-tensioning mechanism can be used to realize automatic disassembly/installation of the bolts.
  • the automatic bolt pre-tensioning mechanism can adaptively mesh with the bolt 83 and complete the pre-tightening, elongation measurement and nut rotation of the bolt 83; the automatic bolt disassembly and assembly mechanism includes several multi-degree-of-freedom automatic manipulators, related instruments and Sensors, etc., can automatically remove or install bolts and nuts and place them in temporary storage structures.
  • the lifting device 2 is a lifting device with several stages of hydraulic cylinder lifting structures.
  • the lifting device 2 is used to lift the lower structure 82 of the pressure vessel 8 or the unloaded bolt operating device 1 in the vertical direction. Its lifting stroke can satisfy the complete disengagement or docking of the lower structure 82 and the upper structure 81 of the pressure vessel 8 .
  • the attitude adjustment device 3 is used to adjust the bolt operating device 1 so as to achieve precise docking between the bolt operating device 1 and the flange surface 84 of the pressure vessel 8 .
  • the attitude adjustment device 3 is fixedly installed on the top of the lifting device 2 and has multiple degrees of freedom in position, horizontality and radial azimuth. It is used to adjust the attitude at the end of the lifting stage and realize the connection between the bolt operating device 1 and the reactor pressure vessel. Precise docking of the lower edge of flange surface 84 of 8.
  • the transfer device 4 is used to transfer the substructure 82 carrying the pressure vessel 8 or the unloaded bolt operating device 1, lifting device 2 and attitude adjustment device 3 between the reactor cavity position and the transfer position.
  • the transfer device 4 is located underwater in the core pool and below the reactor pressure vessel 8.
  • the transfer device 4 is a transfer vehicle that can achieve horizontal movement.
  • the transfer device 4 is a transfer vehicle that runs horizontally on the track 41.
  • the trolley structure, the track 41 is set at the bottom of the reactor core pool, the track 41 is located below the reactor pressure vessel 8, the trolley is driven by a wire rope or hydraulic method, and carries the lower part of the reactor pressure vessel 8 between the transfer position and the reactor cavity position.
  • the structure 82 or the unloaded bolt operating device 1 is transferred.
  • the bolt operating device 1, the lifting device 2, the attitude adjustment device 3 and the transfer device 4 are located underwater in the reactor core pool.
  • the attitude adjustment device 3 is arranged on the top of the lifting device 2.
  • the bolt operating device 1 is connected to the attitude adjustment device 3.
  • the lifting device 2 is fixedly connected to the transfer device 4.
  • the transfer device 4 can drive the lifting device 2 and the attitude adjustment device 3 and the bolt operating device 1 installed on the lifting device 2 to move in the horizontal direction.
  • the water level in the refueling pool is maintained at the refueling water level, the drive cables, pipelines, etc. of the bolt operating device 1, the transfer device 4, the lifting device 2 and the attitude adjustment device 3 are connected, and the lifting device 2 and the bolt operating device 1 are transferred from the transfer position to the reactor cavity position directly below the reactor through the transfer device 4.
  • Figure 2 is a schematic diagram of the second state (the lifting device is lifted into place) of refueling the pressurized water reactor according to one or more embodiments of the present invention.
  • the reactor refueling system 100 of the present invention also includes a guide device 5, It includes a plurality of pairs of mechanical guide pairs located on the bolt operating device 1 and the pressure vessel 8 respectively, which can provide guidance for the lifting device 2 during the lifting process.
  • the guide device 5 includes a guide seat 51 with a guide groove fixed on the pallet 101, and a guide shaft 52 fixed on the corresponding position of the lower end of the upper reactor pressure vessel 8 of the refueling flange.
  • the guide shaft 52 can be inserted.
  • the guide seat 51 see Figure 3
  • it is used to provide a centering guide for the pallet 101 during the opening and closing process of the reactor pressure vessel 8, so as to ensure the centering accuracy of the upper and lower parts of the reactor pressure vessel 8 during the opening and closing process.
  • the lifting device 2 lifts the bolt operating device 1 , approaches the reactor pressure vessel flange surface 84 from below, and enters the guide stroke of the guide device 5 .
  • the guide shaft 52 at the lower end of the pressure vessel 8 has not yet cooperated with the guide seat 51 on the tray 101 .
  • Figure 3 is a schematic diagram of the third state of refueling of the pressurized water reactor according to one or more embodiments of the present invention (the attitude adjustment device is adjusted in place to achieve flange docking).
  • the position, horizontality and radial azimuth angle of the bolt operating device 1 are adjusted by the attitude adjustment device 3 to adjust the terminal attitude to achieve docking with the flange surface 84 of the reactor pressure vessel.
  • the guide shaft 52 at the lower end of the pressure vessel 8 cooperates with the guide seat 51 on the tray 101 to form a guide.
  • Figure 4 is a schematic diagram of the fourth state (the bolt operating device 1 realizes the disassembly of the flange surface) of the pressurized water reactor according to one or more embodiments of the present invention during refueling.
  • the bolt operating device 1 disassembles and recovers the reactor pressure vessel flange nuts and bolts 83. In this state, the disassembly of all bolts 83 has been completed.
  • Figure 5 is a schematic diagram of the fifth state (the lifting device 2 is lowered) of refueling the pressurized water reactor according to one or more embodiments of the present invention.
  • the lifting device 2 drives the bolt operating device 1 to lower, and at the same time drives the lower structure 82 of the reactor pressure vessel 8 including the core hoist 9 to lower accordingly until it is lifted.
  • the device 2 is in a fully retracted state. In this state, the transfer device 4 is ready to transfer the lower structure 82 to the transfer position.
  • Figure 6 is a schematic diagram of the sixth state of refueling (the transfer device 4 moves to the transfer position) of the pressurized water reactor according to one or more embodiments of the present invention.
  • the transfer device 4 transfers the lifting device 2 from the reactor cavity position to a transfer position located outside the reactor cavity.
  • a lifting platform 6 is provided below the transfer position to lift the transfer device 4 moved to the transfer position in the vertical direction.
  • the lifting platform 6 is a platform lift that operates vertically underwater and can carry the lower structure 82 of the reactor pressure vessel or the unloaded transfer device 4 for lifting.
  • the transfer device 4 has transferred the lower structure 82 to the lifting platform 6 at the transfer position. At this time, the lifting platform 6 can perform lifting operations.
  • Figure 7 is a schematic diagram of the seventh state of refueling of the pressurized water reactor according to one or more embodiments of the present invention (the reactor pressure vessel substructure 82 is hoisted to the refueling platform 7).
  • the reactor loading and refueling system 100 of the present invention also includes a refueling platform 7, which is arranged underwater in the waste tank area and above the lifting platform 6, and can carry and store the unloaded pressure vessel 8 of substructure 82.
  • the refueling platform 7 is close to the lifting platform 6.
  • the refueling platform 7 is a platform structure located underwater in the waste tank area for supporting and storing the unloaded reactor pressure vessel substructure, and allows the refueling machine 10 (See Figure 8) The core fuel assembly replacement operation is performed at this position.
  • the refueling platform 7 is a special storage rack structure with a support ring and a guide pin.
  • the reactor loading and refueling system 100 also includes a hoist 11 capable of lifting the lower structure 82 of the pressure vessel 8 stored on the refueling platform 7 .
  • the reactor loading and refueling system 100 also includes a bridge crane 12, which is connected to the spreader 11 and transfers the spreader 11 and the substructure 82 as a whole.
  • the spreader 11 has the ability to hoist the lower structure 82 of the reactor pressure vessel.
  • the bridge crane 12 is set up in the refueling operation hall in the spent tank area. It is a heavy-duty double-girder bridge crane with high positioning accuracy and is used in the reactor. During the refueling period, the reactor pressure vessel substructure 82 is hoisted by the hoist 11.
  • the lifting platform 6 carries the transfer device 4 and lifts it to a height that can be lifted by the hoist 11 and ensures that the fuel assembly therein has a sufficient shielding water layer.
  • the lower structure of the reactor pressure vessel including the core hoist 9 is lifted onto the refueling platform 7 by the bridge crane 12 and the hoist 11.
  • Figure 8 is a schematic diagram of the eighth state (core refueling) of the pressurized water reactor according to one or more embodiments of the present invention.
  • the reactor loading and refueling system 100 also includes a refueling machine 10 , which performs the replacement operation of the core fuel assembly on the refueling platform 7 .
  • the refueling machine 10 is a bridge crane capable of operating fuel assemblies and inserts outside the reactor and in the spent pool area.
  • the refueling machine 10 is equipped with a telescopic sleeve, fuel assemblies and special operating grippers for inserts.
  • Figure 9 is a schematic diagram of the ninth state of refueling of the pressurized water reactor according to one or more embodiments of the present invention (reactor pressure vessel substructure reassembly).
  • the reactor pressure vessel lower structure 82 including the core hoisting 9 on the refueling platform 7 is hoisted to the pallet 101 through the bridge crane 2 and the spreader 11, and is lifted and lowered.
  • the platform 6 drives the transfer device 4 to descend.
  • the transfer device 4 transfers the lifting device 2 from the lifting platform 6 at the transfer position to the reactor cavity position.
  • the lifting device 2 lifts the bolt operating device and approaches the reactor pressure vessel flange from below. face and enter the guide
  • the guide stroke of position 5 is used to adjust the position, level and radial azimuth of the bolt operating device 1 through the attitude adjustment device 3 to achieve docking with the flange surface 84 of the reactor pressure vessel.
  • the bolt operating device 1 adjusts the reactor pressure
  • the vessel flange nuts and bolts 83 are installed, thereby reinstalling the reactor pressure vessel substructure 82 .
  • Figure 10 is a schematic diagram of the tenth state of refueling of the pressurized water reactor according to one or more embodiments of the present invention (the transfer trolley is lifted to the operating platform through the lifting platform).
  • the transfer device 4 is moved back to the lifting platform 6 at the transfer position, and is lifted to the operating platform above the water surface by the lifting platform 6 , and can be moved out of the nuclear power plant for storage and maintenance.
  • the lower structure 82 of the reactor pressure vessel can be refueled in an open manner above the core after being transferred as a whole, which greatly reduces the difficulty of the core fuel assembly replacement operation and is particularly beneficial to the reactor.
  • Compact reactors such as integrated reactors have compact and narrow internal spaces and are difficult to refuel in traditional ways.
  • the reactor core fuel assembly can be replaced in a tight sequence after the reactor cover is opened and transferred.
  • the cover can be opened sequentially from above in a series of The operation is separated from the critical path of refueling.
  • the refueling method of opening the cover downward can overcome the complex problem of disassembly and assembly of the reactor top penetration, which is especially beneficial to reactors such as third-generation pressurized water reactors and compact small reactors where it is difficult to disassemble and install the top penetration.
  • Figure 11 is a schematic front structural view of the attitude adjustment device 3 according to one or more embodiments of the present invention.
  • the posture adjustment device 3 is composed of a rotating platform and a translation platform 35.
  • the rotating platform is fixedly arranged on the top of the lifting device 3, and the translation platform 35 is located at the top of the rotating platform.
  • the translation platform 35 is connected to the rotary platform through a universal ball bearing 34 and a screw guide mechanism 36 .
  • the translation platform 35 has a circular ring structure, and the bolt operating device 1 is fixedly installed on the translation platform 35 .
  • the rotary platform 37 is composed of a lower rotary unit 31 and an upper rotary unit 32 driven by a hydraulic cylinder 33. Both the upper rotary unit 32 and the lower rotary unit 31 are annular structures. The lower rotary unit 31 and the upper rotary unit 32 are coaxially arranged and pass through Bearings (such as plane bearings, etc.) are connected.
  • the side of the upper rotary unit 32 of the lower rotary unit 31 has an outward protrusion.
  • the protrusions of the lower rotary unit 31 and the upper rotary unit 32 on the same side are connected through a hydraulic cylinder 33.
  • the hydraulic cylinder 33 is a two-way hydraulic cylinder.
  • the hydraulic cylinder 33 is hingedly connected to the protrusions at both ends thereof, so that the upper rotary unit 32 is driven to rotate by the expansion and contraction of the hydraulic cylinder 33 .
  • FIG. 12 is a view taken along line A-A in FIG. 11 .
  • the universal ball bearing 34 and the screw guide mechanism 36 are both fixedly installed on the upper rotary unit.
  • the screw guide mechanism 36 is divided into an X-axis mechanism 361 and a Y-axis mechanism 362.
  • the X-axis mechanism 361 is fixedly installed on the upper rotary unit.
  • the Y-axis mechanism 362 is slidably disposed on the X-axis mechanism 361, and the translation platform 35 is slidably disposed on the Y-axis mechanism.
  • a number of universal ball bearings 34 are evenly fixed on the upper surface of the upper rotary unit 32.
  • the vertical load of the translation platform 35 and above is supported by the universal ball bearings 34.
  • the upper rotary unit 32 is also fixed with a screw guide rail mechanism. 36.
  • the screw guide mechanism 36 is divided into two layers: the X-axis mechanism 361 and the Y-axis mechanism 362.
  • the X-axis mechanism is fixedly arranged on the upper rotary unit 32, and the Y-axis mechanism 362 is slidingly arranged on the X-axis mechanism 361, and the two are set perpendicular to each other, the Y-axis
  • the mechanism 362 is driven by the screw on the X-axis mechanism 361.
  • the Y-axis mechanism 362 is slidably provided with a base.
  • the base is driven by the screw on the Y-axis mechanism 362.
  • the translation platform 35 is fixed on the base, and the tray 101 is fixed. Set on the translation platform 35.
  • the translation platform 35 is a circular ring structure, and the translation platform 35 and the rotary platform 37 are coaxially arranged.
  • the coaxial arrangement serves as an installation reference, which can effectively ensure the accuracy of subsequent posture adjustment.
  • screw guide rail mechanism 36 can be provided with one or more. The specific number can be selected according to actual needs, and there are no excessive restrictions here.
  • the posture adjustment device 3 has the ability to adjust multiple degrees of freedom such as position, horizontality and radial azimuth, and is used for slight posture adjustment at the end of the lifting stage, so as to achieve precise docking between the tray 101 and the lower edge of the reactor pressure vessel flange surface.
  • a second aspect of the present invention provides a reactor loading and refueling method, which uses the reactor loading and refueling system 100 as described above to perform a loading and refueling operation on the reactor pressure vessel 8 with the cover downwards opened, which includes the following steps:
  • the attitude adjustment device 3 performs attitude adjustment on the position, horizontality and radial azimuth of the bolt operating device 1 to achieve docking with the reactor pressure vessel flange surface 84;
  • the lifting device 2 is used to drive the bolt operating device 1 carrying the lower structure 82 of the pressure vessel 8 down;
  • the substructure 82 carrying the pressure vessel 8 or the unloaded bolt operating device 1, lifting device 2 and attitude adjustment device 3 are moved to and transferred to the reactor cavity position through the transfer device 4. Transfer between positions 4.
  • the transfer device 4 transfers the lower structure 82 to the lifting platform 6 at the transfer position.
  • the lifting platform 6 carries the transfer device 4 and lifts it to a height where the spreader 11 can hoist it and ensures that the fuel assembly therein has a sufficient shielding water layer.
  • the lower structure of the reactor pressure vessel including the core hoisting device 9 is hoisted to the refueling platform 7 through the bridge crane 12 and the hoisting device 11 .
  • the refueling machine 10 performs the replacement operation of the core fuel assembly on the refueling platform 7 .
  • the reactor pressure vessel substructure 82 including the core hoisting 9 on the refueling platform 7 is hoisted to the pallet 101 through the bridge crane 2 and the spreader 11.
  • the lifting platform 6 drives the transfer device 4 Descending, the transfer device 4 transfers the lifting device 2 from the lifting platform 6 at the transfer position to the reactor cavity position.
  • the lifting device 2 lifts the bolt operating device, approaches the flange surface of the reactor pressure vessel from below, and enters the guide device With a guide stroke of 5, the position, horizontality and radial azimuth of the bolt operating device 1 are adjusted through the attitude adjustment device 3 to achieve docking with the flange surface 84 of the reactor pressure vessel.
  • the bolt operating device 1 adjusts the orientation of the reactor pressure vessel.
  • the flange nuts and bolts 83 are installed to reassemble the reactor pressure vessel substructure 82 .

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Abstract

一种反应堆装换料系统(100)及方法，对向下开盖的反应堆压力容器(8)进行装换料操作，包括：螺栓操作装置(1)、举升装置(2)、姿态调整装置(3)和转运装置(4)，其中，螺栓操作装置(1)、举升装置(2)、姿态调整装置(3)和转运装置(4)位于反应堆堆芯水池水下，姿态调整装置(3)设置在举升装置(2)顶部，螺栓操作装置(1)与姿态调整装置(3)连接，举升装置(2)固定连接在转运装置(4)上，转运装置(4)能够带动举升装置(2)以及安装在举升装置(2)上的姿态调整装置(3)和螺栓操作装置(1)在水平方向上移动。该反应堆装换料系统(100)及方法，解决了现有核反应堆换料技术路径长、拆装难度大的问题，缩短了路径、降低了拆装难度。

Description

一种反应堆装换料系统及方法
相关申请的交叉引用
本申请要求享有于2022年09月19日提交的名称为“一种向下开盖的反应堆装换料系统及方法”的中国专利申请202211138104.X的优先权，该申请的全部内容通过引用并入本文中。
技术领域
本发明涉及核电检修技术领域，特别是涉及一种反应堆装换料系统及方法。
背景技术
反应堆装换料系统是系统性解决反应堆开盖和堆芯燃料组件更换的系统。现有技术中，压水堆装换料系统均是采用从上方开盖的方式，也即使用厂房吊车及专用工器具，从反应堆上方依次移除反应堆堆顶贯穿件、反应堆压力容器顶盖，再依次吊出控制棒驱动机构、上部堆内构件和堆内测量格架，然后在反应堆内依次进行单个燃料组件的更换操作。
发明人发现，现有的换料技术，存在的不足主要有：
第一方面，由于采用从上方依次开盖后进行堆内换料的方式，先后进行的反应堆部件拆解和换料的各步骤不能并行开展，换料关键路径较长；
第二方面，反应堆顶部具有的各种贯穿件结构拆装是核电厂换料路径中耗时较长的部分，特别是自压水反应堆发展到第三代以来，采用了堆芯仪表贯穿件从上方贯穿反应堆压力容器的方式，从上部拆装堆内核测贯穿件和堆芯测量仪表组件等数量众多结构复杂，拆装工艺更加困难；
第三方面，对于得到了较大发展的一体化堆等紧凑型反应堆，由于高 度紧凑的全内置布局，安全壳和反应堆压力容器都有复杂的堆顶贯穿件，反应堆内部有紧凑的内置控制棒驱动机构和换热组件，不仅从上方开盖操作的难度进一步增加，也严重制约了从上方将装卸料机的伸缩式套筒深入堆内进行燃料组件操作的可实施性。
发明内容
针对现有技术存在的不足，本发明的目的是提供一种反应堆装换料系统及方法，克服现有换料技术所采用的从上方依次开盖的换料方式所带来的关键路径较长问题，简化反应堆顶贯穿件的拆装工艺和难度，并对一体化堆等紧凑型反应堆的开盖换料提供了可实施的实现方式。
本发明第一方面提供一种反应堆装换料系统，对向下开盖的反应堆压力容器进行装换料操作，包括：螺栓操作装置，其用于和压力容器的法兰面对接，对连接压力容器上部结构和下部结构的螺栓进行预紧和拆装操作，并能够承载拆卸下的压力容器的下部结构；举升装置，其用于在竖直方向上，对载有压力容器下部结构或空载的螺栓操作装置升降，其升降行程可以满足压力容器下部结构和上部结构的完全脱离；姿态调整装置，其用于对螺栓操作装置进行调整，从而实现螺栓操作装置和压力容器的法兰面实现精准对接；转运装置，其用于将载有压力容器下部结构或空载的螺栓操作装置、举升装置及姿态调整装置在反应堆的堆腔位置和转运位置之间的转运，其中，螺栓操作装置、举升装置、姿态调整装置和转运装置位于反应堆堆芯水池水下，姿态调整装置设置在举升装置顶部，螺栓操作装置与姿态调整装置连接，举升装置固定连接在转运装置上，转运装置能够带动举升装置以及安装在举升装置上的姿态调整装置和螺栓操作装置在水平方向上移动。
优选地，本发明的反应堆装换料系统还包括导向装置，其包括多个对分别位于螺栓操作装置和压力容器上的机械导向副，可以在举升过程中为举升装置提供导向。
优选地，本发明的反应堆装换料系统还包括升降平台，其设置在反应堆堆腔外部的转运位置，对移动到转运位置的转运装置在竖直方向上进行升降。
优选地，本发明的反应堆装换料系统还包括换料台架，其设置在乏池区域水下，并设置在升降平台上方，能够承载并存放已卸载的压力容器的下部结构；换料机，其在所述换料台架上进行堆芯燃料组件的更换操作。
优选地，本发明的反应堆装换料系统还包括吊具，其能够将换料台架上存放的压力容器的下部结构吊起；桥式起重机，其连接吊具，将吊具和下部结构整体进行转移。
优选地，堆芯水池的池底设有轨道，轨道位于压力容器下方与升降平台之间，转运装置能够在轨道上水平运动。
优选地，姿态调整装置由同轴设置的回转平台和平移平台组成，回转平台固定设置在举升装置的顶部，平移平台位于回转平台的上方且通过万向球轴承和丝杠导轨机构与回转平台连接，平移平台为圆环结构，螺栓操作装置固定设置在平移平台上。
优选地，回转平台由通过液压缸驱动的下回转单元和上回转单元组成，上回转单元与下回转单元均为圆环结构，下回转单元与上回转单元同轴设置且通过轴承连接。
优选地，万向球轴承和丝杠导轨机构均固定设置在上回转单元上，丝杠导轨机构分为X轴机构和Y轴机构，X轴机构固定设置在上回转单元上，Y轴机构滑动设置在X轴机构上，平移平台滑动设置在Y轴机构上。
本发明第二方面提供一种反应堆装换料方法，利用如上所述的反应堆装换料系统对向下开盖的反应堆压力容器进行装换料操作，包括以下步骤：
将转运装置移动到位于反应堆正下方的堆腔位置；
利用举升装置将螺栓操作装置举升，使螺栓操作装置从下方靠近压力容器法兰面；
姿态调整装置对螺栓操作装置的位置、水平度和径向方位角进行姿态调整，实现和反应堆压力容器法兰面的对接；
利用螺栓操作装置对连接压力容器上部结构和下部结构的螺栓进行拆解、回收；
利用举升装置带动承载压力容器下部结构的螺栓操作装置下降；
通过转运装置将载有压力容器下部结构或空载的螺栓操作装置、举升装置及姿态调整装置在反应堆的堆腔位置和转运位置之间进行转运。
本发明通过采用向下开盖的反应堆装换料系统，反应堆开盖并转运后可以紧序进行堆芯燃料组件的替换操作，相较于现有压水堆换料技术可以将从上方依次开盖的一系列操作从换料关键路径脱离，即便因在役检查等需要对反应堆上部部件进一步拆解，也可以和后续进行的堆芯燃料组件更换操作同步进行，缩短大修路径，提升电厂运维经济性；同时，向下开盖的换料方式，可以克服复杂的反应堆顶贯穿件的拆装问题，有益于第三代压水堆和紧凑型小堆等难于实施堆顶贯穿件拆装的反应堆。
本发明采用了向下开盖的换料方式，反应堆压力容器下部结构整体转运后可在堆芯上方进行敞开式换料，极大的降低了堆芯燃料组件更换操作的难度，有益于堆内空间紧凑狭窄、难以采用传统方式进行换料的一体化堆等紧凑型反应堆。
应当理解的是，以上的一般描述和后文的细节描述仅是示例性的，并不能限制本申请。
附图说明
为了更清楚地说明本申请实施例的技术方案，下面将对本申请实施例中所需使用的附图作简单地介绍。
图1是本发明根据一个或多个实施方式的压水反应堆进行换料的第一状态(转运装置运行到堆腔位置)示意图；
图2是本发明根据一个或多个实施方式的压水反应堆进行换料的第二状态(举升装置举升到位)示意图；
图3是本发明根据一个或多个实施方式的压水反应堆进行换料的第三状态(姿态调整装置调整到位，实现法兰对接)示意图；
图4是本发明根据一个或多个实施方式的压水反应堆进行换料的第四状态(螺栓操作装置实现法兰面拆解)示意图；
图5是本发明根据一个或多个实施方式的压水反应堆进行换料的第五状态(举升装置下降)示意图；
图6是本发明根据一个或多个实施方式的压水反应堆进行换料的第六状态(转运装置运行到转运位置)示意图；
图7是本发明根据一个或多个实施方式的压水反应堆进行换料的第七状态(反应堆压力容器下部结构吊装到换料台架)示意图；
图8是本发明根据一个或多个实施方式的压水反应堆进行换料的第八状态(堆芯换料)示意图；
图9是本发明根据一个或多个实施方式的压水反应堆进行换料的第九状态(反应堆压力容器下部结构回装)示意图；
图10是本发明根据一个或多个实施方式的压水反应堆进行换料的第十状态(转运小车通过升降平台起升到操作平台)示意图；
图11是本发明根据一个或多个实施方式的姿态调整装置的主视结构示意图；
图12是图11的A-A向视图。
附图标记：
100-反应堆装换料系统；
1-螺栓操作装置；
101-托盘；
2-举升装置；
3-姿态调整装置；
31-下回转单元；
32-上回转单元；
33-液压缸；
34-万向球轴承；
35-平移平台；
36-丝杠导轨机构；
361-X轴机构；
362-Y轴机构；
37-回转平台；
4-转运装置；
41-轨道；
5-导向装置；
51-导向座；
52-导向轴；
6-升降平台；
7-换料台架；
8-压力容器；
81-上部结构；
82-下部结构；
83-螺栓；
84-法兰面；
9-堆芯吊篮；
10-换料机；
11-吊具；
12-桥式起重机。
具体实施方式
为了更好的理解本申请的技术方案，下面结合附图对本申请实施例进行详细描述。
现有的从上方依次开盖后进行堆内换料的方式存在着换料关键路径较长、从上部拆装堆内核测贯穿件和堆芯测量仪表组件等数量众多结构复杂，拆装工艺更加困难的问题，为了解决如上的技术问题，本发明提出了一种反应堆装换料系统及方法。
图1是本发明根据一个或多个实施方式的压水反应堆进行换料的第一状态(转运装置运行到堆腔位置)示意图。
如图1所示，本实施例的反应堆装换料系统100，对向下开盖的反应堆压力容器8进行装换料操作，包括螺栓操作装置1、举升装置2、姿态调整装置3和转运装置4。
向下开盖的反应堆压力容器8为一个具有换料法兰以及内部构件的压力容器，即，分为容器外壳及其内部的构件(为了详细说明本发明的要点，在图1及其他附图中未显示与本发明无关的内部构件)，其中，容器外壳分为上壳和下壳，位于换料法兰上方的容器部分为上壳，可通过自身结构连接，上壳与其内部的控制棒驱动机构、上部堆内构件、堆内测量格架(未图示)共同构成一体化上部结构81，位于换料法兰下方的容器部分为下壳，下壳可以承载堆芯吊篮9和堆芯，共同构成下部结构82，上部结构81和下部结构82通过螺栓83连接。
堆芯吊篮9为一个具有整体框架的包含堆芯的吊篮结构体，用于实现堆芯整体吊装和堆外换料，其结构可以容纳堆芯所有燃料组件并进行整体吊装。
螺栓操作装置1用于和压力容器8的法兰面84对接，对连接压力容器8的上部结构81和下部结构82的螺栓83进行预紧和拆装操作，并能够承载拆卸下的压力容器8的下部结构82。
螺栓操作装置1包括托盘101和若干个独立的自动螺栓拆装机构和若干个独立的自动螺栓预紧机构，托盘101通过支架固定设置在姿态调整装置3上，可以与反应堆压力容器8的法兰面84下缘对接，并在举升过程中承载反应堆压力容器8的下部结构82的重量。当托盘101与反应堆压力容器法兰面84下缘精准对接后，可通过自动螺栓拆装机构和自动螺栓预紧机构，实现螺栓的自动拆卸/安装。
自动螺栓预紧机构可自适应与螺栓83啮合，并完成螺栓83的预紧、伸长量测量以及螺母的旋动；自动螺栓拆装机构包括数个多自由度自动机械臂、相关的仪表以及传感器等，可以自动拆除或安装螺栓、螺母，并将其放置在临时存放结构中。
可以理解的是，自动螺栓预紧机构、自动螺栓拆装机构均为现有技术手段，具体的这里不做过多的赘述。
举升装置2为一个具有若干级液压缸顶升结构的顶升装置，举升装置2用于在竖直方向上，对承载有压力容器8下部结构82或空载的螺栓操作装置1升降，其升降行程可以满足压力容器8的下部结构82和上部结构81的完全脱离或对接。
姿态调整装置3用于对螺栓操作装置1进行调整，从而实现螺栓操作装置1和压力容器8的法兰面84实现精准对接。
姿态调整装置3固定设置在举升装置2的顶部，具有位置、水平度和径向方位角多个自由度的执行，用于举升阶段末端姿态的调整，实现螺栓操作装置1与反应堆压力容器8的法兰面84下缘的精准对接。
转运装置4用于将载有压力容器8的下部结构82或空载的螺栓操作装置1、举升装置2及姿态调整装置3在反应堆的堆腔位置和转运位置之间的转运。
转运装置4位于堆芯水池水下且处于反应堆压力容器8的下方，转运装置4为一个可以实现水平运动的转运载具，具体的，本实施例中转运装置4为一个在轨道41上水平运行的小车结构，轨道41设置在堆芯水池的池底，轨道41位于反应堆压力容器8下方，小车采用钢丝绳或液压方式驱动，在转运位置和堆腔位置之间对载有反应堆压力容器8的下部结构82或空载的螺栓操作装置1进行转运。
螺栓操作装置1、举升装置2、姿态调整装置3和转运装置4位于反应堆堆芯水池水下，姿态调整装置3设置在举升装置2顶部，螺栓操作装置1与姿态调整装置3连接，举升装置2固定连接在转运装置4上，转运装置4能够带动举升装置2以及安装在举升装置2上的姿态调整装置3和螺栓操作装置1在水平方向上移动。
如图1所示，实施换料的开始阶段，换料水池水位保持在换料水位，将螺栓操作装置1、转运装置4、举升装置2及姿态调整装置3的驱动电缆、管路等连接完成，并通过转运装置4将举升装置2及螺栓操作装置1从转运位置转运到位于反应堆正下方的堆腔位置。
图2为本发明根据一个或多个实施方式的压水反应堆进行换料的第二状态(举升装置举升到位)示意图。
如图2所示，本发明的反应堆装换料系统100还包括导向装置5， 其包括多个对分别位于螺栓操作装置1和压力容器8上的机械导向副，可以在举升过程中为举升装置2提供导向。
具体地，导向装置5包括固定在托盘101上带有导向槽的导向座51，和固定在换料法兰的上部反应堆压力容器8的下端对应位置上的导向轴52，导向轴52可插装在导向座51内(见图3)，以用于在反应堆压力容器8开合盖过程中为托盘101提供对中导向，以保证反应堆压力容器8上下部分在开合盖过程中的对中精度。
如图2所示，举升装置2将螺栓操作装置1举升，从下方接近反应堆压力容器法兰面84，并进入导向装置5的导向行程。此时，压力容器8的下端的导向轴52尚未与托盘101上的导向座51进行配合。
图3是本发明根据一个或多个实施方式的压水反应堆进行换料的第三状态(姿态调整装置调整到位，实现法兰对接)示意图。
如图3所示，通过姿态调整装置3对螺栓操作装置1的位置、水平度和径向方位角进行末端姿态调整，实现和反应堆压力容器法兰面84的对接。此时，压力容器8的下端的导向轴52与托盘101上的导向座51进行配合，形成导向。
图4是本发明根据一个或多个实施方式的压水反应堆进行换料的第四状态(螺栓操作装置1实现法兰面拆解)示意图。
如图4所示，螺栓操作装置1对反应堆压力容器法兰螺母及螺栓83进行拆解和回收。该状态下，已完成全部螺栓83的拆解。
图5是本发明根据一个或多个实施方式的压水反应堆进行换料的第五状态(举升装置2下降)示意图。
如图5所示，举升装置2带动螺栓操作装置1下降，同时带动堆芯吊装9在内的反应堆压力容器8的下部结构82随之下降，直至举升 装置2处于完全收回状态，在此状态下，转运装置4即可准备对下部结构82进行转运位置的转移操作。
图6是本发明根据一个或多个实施方式的压水反应堆进行换料的第六状态(转运装置4运行到转运位置)示意图。
如图6所示，转运装置4将举升装置2从堆腔位置转运到位于反应堆堆腔外部的转运位置。在转运位置下方设有升降平台6，对移动到转运位置的转运装置4在竖直方向上进行升降。升降平台6为一个在水下竖直方向上进行升降运行的平台式升降机，可以承载有反应堆压力容器下部结构82或空载的转运装置4进行升降。在图6中的状态下，转运装置4已将下部结构82转移到转运位置的升降平台6上，此时，升降平台6可以进行升降操作。
图7是本发明根据一个或多个实施方式的压水反应堆进行换料的第七状态(反应堆压力容器下部结构82吊装到换料台架7)示意图。
如图7所示，本发明的反应堆装换料系统100还包括换料台架7，其设置在乏池区域水下，并设置在升降平台6上方，能够承载并存放已卸载的压力容器8的下部结构82。
换料台架7靠近于升降平台6，换料台架7为一个位于乏池区域水下的用于托载并存放已卸载的反应堆压力容器下部结构的台架结构，并允许换料机10(见图8)在此位置进行堆芯燃料组件更换操作，本实施例中换料台架7为一个带有支撑环和导向销的专用存放架结构。
反应堆装换料系统100还包括吊具11，其能够将换料台架7上存放的压力容器8的下部结构82吊起。
反应堆装换料系统100还包括桥式起重机12，其连接吊具11，将吊具11和下部结构82整体进行转移。
吊具11具有吊装反应堆压力容器下部结构82的能力，桥式起重机12设置在乏池区域处的换料操作大厅内，为一个具有高定位精度的重载双梁桥式起重机，用于在反应堆装换料期间通过吊具11对反应堆压力容器下部结构82进行吊装。
如图7所示，升降平台6承载转运装置4并起升，升至吊具11可以吊装的高度并保证其中的燃料组件具有足够的屏蔽水层，通过桥式起重机12及吊具11将包括了堆芯吊装9在内的反应堆压力容器下部结构吊装到换料台架7上。
图8是本发明根据一个或多个实施方式的压水反应堆进行换料的第八状态(堆芯换料)示意图。
如图8所示，反应堆装换料系统100还包括换料机10，其在换料台架7上进行堆芯燃料组件的更换操作。
换料机10为一个具有在堆外和乏池区域进行燃料组件、内插件操作能力的桥式起重机，换料机10带有伸缩套筒、燃料组件及内插件专用操作抓具。
可以理解的是，换料机10、吊具11以及桥式起重机12均为现有结构，具体的结构形式这里不再过多的赘述。
图9是本发明根据一个或多个实施方式的压水反应堆进行换料的第九状态(反应堆压力容器下部结构回装)示意图。
如图9所示，堆芯更换完成后，通过桥式起重机2及吊具11将换料台架7上包括了堆芯吊装9在内的反应堆压力容器下部结构82吊装到托盘101上，升降平台6带动转运装置4下降，转运装置4将举升装置2从位于转运位置的升降平台6上转运到堆腔位置，举升装置2将螺栓操作装置举升，从下方接近反应堆压力容器法兰面，并进入导向装 置5的导向行程，通过姿态调整装置3对螺栓操作装置1的位置、水平度和径向方位角进行末端姿态调整，实现和反应堆压力容器法兰面84的对接，螺栓操作装置1对反应堆压力容器法兰螺母及螺栓83进行安装，从而将反应堆压力容器下部结构82回装。
图10是本发明根据一个或多个实施方式的压水反应堆进行换料的第十状态(转运小车通过升降平台起升到操作平台)示意图。
如图10所示，将转运装置4重新移动回转运位置的升降平台6上，并通过升降平台6将其抬升到水面以上的操作平台上，并可将其移出核电厂进行贮存和维护。
由于采用了向下开盖的换料方式，反应堆压力容器下部结构82整体转运后可在堆芯上方进行敞开式换料，极大的降低了堆芯燃料组件更换操作的难度，特别有益于堆内空间紧凑狭窄、难以采用传统方式进行换料的一体化堆等紧凑型反应堆。
通过采用向下开盖的换料方式，反应堆开盖并转运后可以紧序进行堆芯燃料组件的替换操作，相较于现有压水堆换料技术可以将从上方依次开盖的一系列操作从换料关键路径脱离，即便因在役检查等需要对反应堆上部部件进一步拆解，也可以和后续进行的堆芯燃料组件更换操作同步进行，缩短大修路径，提升电厂运维经济性；同时，向下开盖的换料方式，可以克服复杂的反应堆顶贯穿件的拆装问题，特别有益于第三代压水堆和紧凑型小堆等难于实施堆顶贯穿件拆装的反应堆。
图11是本发明根据一个或多个实施方式的姿态调整装置3的主视结构示意图。
如图11所示，姿态调整装置3由回转平台和平移平台35组成，回转平台固定设置在举升装置3的顶部，平移平台35位于回转平台的 上方，平移平台35通过万向球轴承34和丝杠导轨机构36与回转平台连接。
平移平台35为圆环结构，螺栓操作装置1固定设置在平移平台35上。
回转平台37由通过液压缸33驱动的下回转单元31和上回转单元32组成，上回转单元32与下回转单元31均为圆环结构，下回转单元31与上回转单元32同轴设置且通过轴承(例如平面轴承等)连接。
下回转单元31的上回转单元32的侧部具有向外的凸起，下回转单元31和上回转单元32位于同侧的凸起之间通过液压缸33连接，液压缸33为双向液压缸，液压缸33与其两端的凸起铰接，从而通过液压缸33的伸缩带动上回转单元32转动。
可以理解的是，液压缸33至少设有一个，当液压缸33设有两个时，两个液压缸33应相对设置在回转平台37的两侧，通过做相反的伸缩运动带动回转平台37转动，以提高回转平台37的转动能力。
图12是图11的A-A向视图。
如图12所示，万向球轴承34和丝杠导轨机构36均固定设置在上回转单元上，丝杠导轨机构36分为X轴机构361和Y轴机构362，X轴机构361固定设置在上回转单元32上，Y轴机构滑362动设置在X轴机构361上，平移平台35滑动设置在Y轴机构上。
上回转单元32的上表面均匀固定设有若干万向球轴承34，平移平台35及其以上部分竖直方向载荷由万向球轴承34支撑，上回转单元32上还固定设有丝杠导轨机构36，丝杠导轨机构36分为X轴机构361和Y轴机构362两层，其中，X轴机构固定设置在上回转单元32上，Y轴机构362滑动设置在X轴机构361上，且二者相互垂直设置，Y轴 机构362通过X轴机构361上的丝杠带动，Y轴机构362上滑动设有基座，基座通过Y轴机构362上的丝杠带动，平移平台35固定设置在基座上，托盘101固定设置在平移平台35上。
平移平台35为圆环结构，平移平台35与回转平台37同轴设置，同轴设置作为安装基准，可有效保证后续姿态调整的准确性。
可以理解的是，丝杠导轨机构36可以设置一个，也可以设置多个，具体设置的数量可根据实际需求进行选择，这里不做过多的限制。
姿态调整装置3具有位置、水平度和径向方位角等多个自由度调节的能力，用于举升阶段末端的姿态小幅调整，从而实现托盘101与反应堆压力容器法兰面下缘的精准对接。
本发明第二方面提供一种反应堆装换料方法，利用如上所述的反应堆装换料系统100对向下开盖的反应堆压力容器8进行装换料操作，包括以下步骤：
将转运装置4移动到位于反应堆正下方的堆腔位置。
利用举升装置2将螺栓操作装置1举升，使螺栓操作装置1从下方靠近压力容器法兰面84；
姿态调整装置3对螺栓操作装置1的位置、水平度和径向方位角进行姿态调整，实现和反应堆压力容器法兰面84的对接；
利用螺栓操作装置1对连接压力容器8的上部结构81和下部结构82的螺栓83进行拆解、回收；
利用举升装置2带动承载压力容器8的下部结构82的螺栓操作装置1下降；
通过转运装置4将载有压力容器8的下部结构82或空载的螺栓操作装置1、举升装置2及姿态调整装置3在反应堆的堆腔位置和转运 位置4之间进行转运。
转运装置4将下部结构82转移到转运位置的升降平台6上，升降平台6承载转运装置4并起升，升至吊具11可以吊装的高度并保证其中的燃料组件具有足够的屏蔽水层，通过桥式起重机12及吊具11将包括了堆芯吊装9在内的反应堆压力容器下部结构吊装到换料台架7上。换料机10，其在换料台架7上进行堆芯燃料组件的更换操作。
堆芯更换完成后，通过桥式起重机2及吊具11将换料台架7上包括了堆芯吊装9在内的反应堆压力容器下部结构82吊装到托盘101上，升降平台6带动转运装置4下降，转运装置4将举升装置2从位于转运位置的升降平台6上转运到堆腔位置，举升装置2将螺栓操作装置举升，从下方接近反应堆压力容器法兰面，并进入导向装置5的导向行程，通过姿态调整装置3对螺栓操作装置1的位置、水平度和径向方位角进行末端姿态调整，实现和反应堆压力容器法兰面84的对接，螺栓操作装置1对反应堆压力容器法兰螺母及螺栓83进行安装，从而将反应堆压力容器下部结构82回装。
将转运装置4重新移动回转运位置的升降平台6上，并通过升降平台6将其抬升到水面以上的操作平台上，并可将其移出核电厂进行贮存和维护。
以上所述仅为本申请的优选实施例而已，并不用于限制本申请，对于本领域的技术人员来说，本申请可以有各种更改和变化。凡在本申请的精神和原则之内，所作的任何修改、等同替换、改进等，均应包含在本申请的保护范围之内。

Claims (10)

  1. 一种反应堆装换料系统，对向下开盖的反应堆压力容器进行装换料操作，其特征在于，包括：
    螺栓操作装置，其用于和所述压力容器的法兰面对接，对连接所述压力容器上部结构和下部结构的螺栓进行预紧和拆装操作，并能够承载拆卸下的压力容器的下部结构；
    举升装置，其用于在竖直方向上，对载有所述压力容器下部结构或空载的所述螺栓操作装置升降，其升降行程可以满足所述压力容器下部结构和上部结构的完全脱离；
    姿态调整装置，其用于对所述螺栓操作装置进行调整，从而实现所述螺栓操作装置和所述压力容器的法兰面实现精准对接；
    转运装置，其用于将载有所述压力容器下部结构或空载的螺栓操作装置、举升装置及姿态调整装置在所述反应堆的堆腔位置和转运位置之间的转运，
    其中，所述螺栓操作装置、所述举升装置、所述姿态调整装置和所述转运装置位于反应堆堆芯水池水下，所述姿态调整装置设置在所述举升装置顶部，所述螺栓操作装置与所述姿态调整装置连接，所述举升装置固定连接在所述转运装置上，所述转运装置能够带动所述举升装置以及安装在所述举升装置上的姿态调整装置和所述螺栓操作装置在水平方向上移动。
  2. 根据权利要求1所述的反应堆装换料系统，其特征在于，还包括导向装置，其包括多个对分别位于所述螺栓操作装置和所述压力容器上的机械导向副，可以在举升过程中为所述举升装置提供导向。
  3. 根据权利要求1所述的反应堆装换料系统，其特征在于，还包括升降平台，其设置在所述反应堆堆腔外部的转运位置，对移动到转运位置的所述转运装置在竖直方向上进行升降。
  4. 根据权利要求3所述的反应堆装换料系统，其特征在于，还包括换料台架，其设置在乏池区域水下，并设置在所述升降平台上方，能够承载并存放已卸载的所述压力容器的下部结构；换料机，其在所述换料台架上进行堆芯燃料组件的更换操作。
  5. 根据权利要求4所述的反应堆装换料系统，其特征在于，还包括吊具，其能够将所述换料台架上存放的所述压力容器的下部结构吊起；桥式起重机，其连接所述吊具，将所述吊具和所述下部结构整体进行转移。
  6. 根据权利要求3所述的反应堆装换料系统，其特征在于，所述堆芯水池的池底设有轨道，所述轨道位于所述压力容器下方与所述升降平台之间，所述转运装置能够在所述轨道上水平运动。
  7. 根据权利要求1所述的反应堆装换料系统，其特征在于，所述姿态调整装置由同轴设置的回转平台和平移平台组成，所述回转平台固定设置在所述举升装置的顶部，所述平移平台位于所述回转平台的上方且通过万向球轴承和丝杠导轨机构与回转平台连接，所述平移平台为圆环结构，所述螺栓操作装置固定设置在所述平移平台上。
  8. 根据权利要求7所述的反应堆装换料系统，其特征在于，所述回转 平台由通过液压缸驱动的下回转单元和上回转单元组成，所述上回转单元与所述下回转单元均为圆环结构，所述下回转单元与所述上回转单元同轴设置且通过轴承连接。
  9. 根据权利要求8所述的反应堆装换料系统，其特征在于，所述万向球轴承和所述丝杠导轨机构均固定设置在所述上回转单元上，所述丝杠导轨机构分为X轴机构和Y轴机构，所述X轴机构固定设置在上回转单元上，所述Y轴机构滑动设置在所述X轴机构上，所述平移平台滑动设置在Y轴机构上。
  10. 一种反应堆装换料方法，利用如权利要求1所述的反应堆装换料系统对向下开盖的反应堆压力容器进行装换料操作，其特征在于，包括以下步骤：
    将所述转运装置移动到位于反应堆正下方的堆腔位置；
    利用所述举升装置将所述螺栓操作装置举升，使所述螺栓操作装置从下方靠近所述压力容器法兰面；
    姿态调整装置对所述螺栓操作装置的位置、水平度和径向方位角进行姿态调整，实现和反应堆压力容器法兰面的对接；
    利用所述螺栓操作装置对连接所述压力容器上部结构和下部结构的螺栓进行拆解、回收；
    利用举升装置带动承载所述压力容器下部结构的所述螺栓操作装置下降；
    通过所述转运装置将载有所述压力容器下部结构或空载的螺栓操作装置、举升装置及姿态调整装置在所述反应堆的堆腔位置和转运位置之间进行转运。
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