CN116588787A - Hoisting system for internal components - Google Patents

Hoisting system for internal components Download PDF

Info

Publication number
CN116588787A
CN116588787A CN202310549555.0A CN202310549555A CN116588787A CN 116588787 A CN116588787 A CN 116588787A CN 202310549555 A CN202310549555 A CN 202310549555A CN 116588787 A CN116588787 A CN 116588787A
Authority
CN
China
Prior art keywords
scooter
pile
sub
compartment
lifting
Prior art date
Legal status (The legal status 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 status listed.)
Pending
Application number
CN202310549555.0A
Other languages
Chinese (zh)
Inventor
胡伦宝
刘青松
钟金童
路广遥
周建明
倪亮
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, China Nuclear Power Technology Research Institute Co Ltd, CGN Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN202310549555.0A priority Critical patent/CN116588787A/en
Publication of CN116588787A publication Critical patent/CN116588787A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/10Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B61RAILWAYS
    • B61DBODY DETAILS OR KINDS OF RAILWAY VEHICLES
    • B61D15/00Other railway vehicles, e.g. scaffold cars; Adaptations of vehicles for use on railways
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B66HOISTING; LIFTING; HAULING
    • B66CCRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
    • B66C1/00Load-engaging elements or devices attached to lifting or lowering gear of cranes or adapted for connection therewith for transmitting lifting forces to articles or groups of articles
    • B66C1/10Load-engaging elements or devices attached to lifting or lowering gear of cranes or adapted for connection therewith for transmitting lifting forces to articles or groups of articles by mechanical means
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B66HOISTING; LIFTING; HAULING
    • B66CCRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
    • B66C15/00Safety gear
    • B66C15/06Arrangements or use of warning devices
    • B66C15/065Arrangements or use of warning devices electrical
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/19Reactor parts specifically adapted to facilitate handling, e.g. to facilitate charging or discharging of fuel elements
    • HELECTRICITY
    • H05ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05KPRINTED CIRCUITS; CASINGS OR CONSTRUCTIONAL DETAILS OF ELECTRIC APPARATUS; MANUFACTURE OF ASSEMBLAGES OF ELECTRICAL COMPONENTS
    • H05K9/00Screening of apparatus or components against electric or magnetic fields
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Transportation (AREA)
  • Microelectronics & Electronic Packaging (AREA)
  • Load-Engaging Elements For Cranes (AREA)

Abstract

The application relates to a hoisting system for a pile inner member. The in-pile component hoisting system includes: the scooter comprises a scooter body, a plurality of wheels connected with the scooter body and a shielding body arranged on the scooter body, wherein the wheels are configured to drive the scooter to move, the shielding body extends along the thickness direction of the scooter body, two ends of the shielding body are provided with openings, and the openings penetrate through the shielding body and the scooter body to form a containing cavity for containing the upper or lower in-pile components; the lifting device comprises a grabbing head and a lifting part connected with the grabbing head, the grabbing head is used for being connected with the upper internal pile component or the lower internal pile component, the lifting part is used for being connected with an external crane, and the grabbing head is configured to move in the shielding body along the height direction of the shielding body under the driving of the lifting part.

Description

Hoisting system for internal components
Technical Field
The application relates to the technical field of nuclear power, in particular to a hoisting system for a member in a pile.
Background
The internals are located within the reactor pressure vessel and are primarily used to support and compress a reactor fuel assembly, which includes an upper internals and a lower internals. During a reactor refueling or service, the upper and lower internals need to be removed from the reactor pressure vessel, respectively, for refueling and service.
In general, when a nuclear power station located on land performs reactor refueling or overhaul, a special underwater hoisting passage can be used for transferring internal components of the nuclear reactor, and a certain amount of water can isolate radioactive substances, so that the transfer safety can be ensured.
However, miniaturized reactors are typically installed on offshore mobile platforms, limited by reactor bay space and in order to reduce the cost of refueling facility construction, reactor bays are typically not designed with refueling channels. Therefore, a means for safely transferring miniaturized reactor internals is lacking.
Disclosure of Invention
Based on this, it is necessary to propose a hoisting system for internals in a reactor to accomplish the transfer of the internals in a miniaturized reactor with safety of personnel, environment and equipment.
The embodiment of the application provides a hoisting system for an in-pile member, which is used for hoisting the in-pile member of a miniaturized nuclear reactor pressure vessel. The pressure vessel includes an upper cap and a barrel sealingly engaged with the upper cap, the internals including an upper internals and a lower internals, the internals hoist system comprising: the scooter comprises a scooter body, a plurality of wheels connected with the scooter body and a shielding body arranged on the scooter body, wherein the wheels are configured to drive the scooter to move, the shielding body extends along the thickness direction of the scooter body, two ends of the shielding body are provided with openings, and the openings penetrate through the shielding body and the scooter body to form a containing cavity for containing the upper or lower in-pile components; the lifting device comprises a grabbing head and a lifting part connected with the grabbing head, the grabbing head is used for being connected with the upper internal pile component or the lower internal pile component, the lifting part is used for being connected with an external crane, and the grabbing head is configured to move in the shielding body along the height direction of the shielding body under the driving of the lifting part.
In some embodiments, the material of the shield includes lead, iron, stainless steel, and lead boron polyethylene.
In some embodiments, the inner wall of the shielding body is provided with at least one sliding rail extending along the height direction of the shielding body, and the grabbing head is provided with a sliding block matched with the sliding rail.
In some embodiments, the scooter further comprises a driving structure connected with the scooter body and a sealing bottom plate connected with an output end of the driving structure, wherein the sealing bottom plate is configured to move relative to the scooter body under the driving of the driving structure so as to seal or open the opening at the bottom of the shielding body.
In some embodiments, the nuclear reactor includes a reactor placement point including a reactor compartment including a hatch, a first sub-compartment positioned below the hatch, and a second sub-compartment in communication with and positioned below the first sub-compartment, an orthographic projection of the first sub-compartment at the second sub-compartment overlaying the second sub-compartment, the second sub-compartment configured to house at least a portion of the structure of the pressure vessel. The hoisting system for the internal components of the pile further comprises a water jacket, wherein the water jacket is a hollow cylinder with openings at two ends and is used for being in sealing joint with an interface of the first sub-cabin and the second sub-cabin, and under the condition that the water jacket is in sealing joint with the interface, the orthographic projection of the water jacket on the second sub-cabin covers the second sub-cabin.
In some embodiments, the reactor placement point further comprises a storage pool at one side of the reactor compartment, wherein a first storage bin for placing the upper internals and a second storage bin for placing the lower internals are arranged in the storage pool; the reactor placement point is provided with two guide rails extending along a first direction, the storage water tank and the reactor cabin are positioned between the two guide rails, and the first direction is the direction from the reactor cabin to the storage water tank;
the wheels are configured to move on the rail to move the scooter.
In some embodiments, the in-pile component lifting system further comprises a first controller and first, second, and third position sensors disposed on the rail;
the first, second, and third position sensors are each electrically connected to the first controller, the first position sensor configured to emit a first position signal when the opening of the shield is aligned with the hatch, the second position sensor configured to emit a second position signal when the opening of the shield is aligned with the first storage bin, and the third position sensor configured to emit a third position signal when the opening of the shield is aligned with the second storage bin;
the first controller is configured to send an alarm signal when receiving one of the first position signal, the second position signal, and the third position signal.
In some embodiments, the gripper comprises a gripper body and a plurality of connecting rods rotatably connected with the gripper body and extending along the height direction of the shielding body, wherein the upper and lower in-pile members are provided with connecting holes matched with the connecting rods, and the connecting rods are configured to be connected with or separated from the connecting holes through rotation.
In some embodiments, the in-pile component lifting system further comprises an operating platform disposed above the head body;
the operating platform is provided with a second controller electrically connected with the connecting rod, and the second controller is configured to control the connecting rod to rotate.
In some embodiments, the lifting part comprises a lifting ring and a plurality of lifting rods connected with the lifting ring, and the other ends of the lifting rods are connected with the grabbing head body.
The in-pile component hoisting system of the embodiment of the application transfers the miniaturized reactor in-pile components in a hoisting mode. In the first aspect, the transfer requirement of the components in the miniaturized reactor can be met, so that convenience in reactor refueling or overhaul is improved while the construction cost of the miniaturized reactor facility is reduced. In a second aspect, the hoisting system for the in-pile components is further provided with the shielding body, and in the transferring process, the in-pile components are located in the accommodating cavity of the shielding body, so that nuclear radiation of the in-pile components can be reduced to a certain extent, and further, the safety of the in-pile components in transferring is improved.
Drawings
FIG. 1 is a schematic view of a hoist system for an in-pile member positioned above the in-pile member according to an embodiment of the present application;
FIG. 2 is a schematic view of a hoisting system for hoisting an in-pile component into a reactor compartment according to an embodiment of the present application;
FIG. 3 is a schematic view of a structure in which a scooter of the in-pile member lifting system of the embodiment of the present application drives an upper in-pile member to move to a storage pool;
FIG. 4 is a schematic structural view of a lower in-pile member moving to a storage pool driven by a scooter of an in-pile member lifting system according to an embodiment of the present application;
FIG. 5 is a schematic view of a lifting appliance of the in-pile component lifting system according to an embodiment of the present application, in which a lower in-pile component is placed in a storage pool;
fig. 6 is a schematic top view of a reactor placement point according to an embodiment of the present application.
Detailed Description
In order that the above objects, features and advantages of the application will be readily understood, a more particular description of the application will be rendered by reference to the appended drawings. In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present application. The present application may be embodied in many other forms than described herein and similarly modified by those skilled in the art without departing from the spirit of the application, whereby the application is not limited to the specific embodiments disclosed below.
In the description of the present application, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present application and simplifying the description, and do not indicate or imply that the device or element being referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present application.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present application, the meaning of "plurality" means at least two, for example, two, three, etc., unless specifically defined otherwise.
In the present application, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present application can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present application, unless expressly stated or limited otherwise, a first feature "up" or "down" a second feature may be the first and second features in direct contact, or the first and second features in indirect contact via an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
It will be understood that when an element is referred to as being "fixed" or "disposed" on another element, it can be directly on the other element or intervening elements may also be present. When an element is referred to as being "connected" to another element, it can be directly connected to the other element or intervening elements may also be present. The terms "vertical," "horizontal," "upper," "lower," "left," "right," and the like are used herein for illustrative purposes only and are not meant to be the only embodiment.
As shown in fig. 1 to 4, an embodiment of the present application proposes an in-pile component lifting system 100. The in-stack component lifting system 100 is used to lift in-stack components 300 within a miniaturized nuclear reactor pressure vessel 200. The pressure vessel 200 includes an upper cap (not shown) and a barrel 210 sealingly engaged with the upper cap, and the in-stack member 300 includes an upper in-stack member 310 and a lower in-stack member 320.
The in-pile component lifting system 100 includes a scooter 110 and a spreader 120. The scooter 110 includes a scooter body 111, a plurality of wheels 113 coupled to the scooter body, and a shield 112 disposed on the scooter body 111. The wheels 113 are configured to move the scooter 110. The shield 112 extends in the thickness direction of the body 111 of the scooter. The shield 112 has openings 1121 at both ends, and the openings 1121 penetrate the shield 112 and the body 111 of the scooter so as to form a receiving cavity S1 for receiving the upper or lower in-pile member 310 or 320. The spreader 120 includes a head 121 and a hoisting portion 122 connected to the head 121. The gripping head 121 is adapted to be connected to either the upper internals 310 or the lower internals 320 and the lifting portion 122 is adapted to be connected to an external crane. The gripper 121 is configured to move in the height direction of the shield 112 inside the shield 112 by the driving of the hanging portion 122.
In the present application, the pressure vessel 200 includes an upper cover and a cylinder 210. The cylinder 210 refers to the remaining portion of the pressure vessel 200 except for the upper cover. Since the in-stack components 300 are located inside the pressure vessel 200, the upper cover of the pressure vessel 200 needs to be removed first when the in-stack components 300 are lifted. When the upper cover is removed, the in-pile member 300 is exposed.
The internals 300 include an upper internals 310 and a lower internals 320. The upper and lower internals 310, 320 are used to support and compress the fuel assemblies within. If a fuel assembly needs to be refueled or serviced, the upper and lower internals 310, 320 need to be removed first. The in-pile member lifting system 100 of the present application can complete lifting of the upper and lower in-pile members 310 and 320.
The in-pile component lifting system 100 includes a scooter 110 and a spreader 120. The scooter 110 comprises a scooter body 111 and a shielding body 112, wherein the scooter body 111 is used for carrying the shielding body 112. The shield 112 refers to a member that can reduce nuclear radiation. Specifically, the shield 112 extends in the thickness direction of the body 111 of the scooter. The shield 112 has openings at both ends thereof, which penetrate the shield 112 and the body 111 of the scooter so as to form a receiving chamber S1 for receiving the upper or lower in-pile member 310 or 320. The concrete hoisting process comprises the following steps: as shown in fig. 1, after the upper cover of the reactor pressure vessel 200 is removed, the drams 110 are moved to the pressure vessel placement point and stopped so that the openings are aligned with the in-stack members 300. At this point, the shield 112 on the body 111 of the scooter is aligned with the in-pile member 300. Then, the hook of the external crane is connected to the lifting part 122 of the lifting tool 120, so that the crane drives the lifting tool 120 to move until the gripping head 121 of the lifting tool 120 is located in the receiving cavity S1. Next, as shown in fig. 2, the crane drives the gripper 121 downward so that the gripper 121 is connected with the upper in-pile member 310 of the in-pile member 300. Thereafter, the crane driving head 121 is raised in the height direction of the shield 112 inside the shield 112 to drive the upper in-pile member 310 to be completely located in the accommodation chamber S1 of the shield 112. Finally, as shown in fig. 3, the scooter 110 is moved, the spreader 120 and the upper internals 310 are transferred to a preset target point, such as a storage pool 420, and the upper internals 310 are lowered by the crane and the spreader 120. After the placement is completed, the spreader 120 is removed. After the upper internals 310 are transferred away, the lower internals 320 can be transferred to the predetermined target point in the same manner. As shown in fig. 4 and 5, fig. 4 is a schematic view of the scooter 110 driving the hanger 120 and the lower in-pile member 320 to be transferred to a preset target point. Fig. 5 is a schematic view showing a structure in which the hanger places the lower internals 320 in the storage pond 420. In this way, the lifting and transferring of the upper and lower internals 310 and 320 is completed, so that the material change or maintenance work can be smoothly performed. It will be readily appreciated that during the movement of the scooter 110 described above, the external crane and the lifting part 122 remain connected in order to ensure that the gripping head 121 of the lifting appliance 120 and the upper internals 310 are in a stable state within the receiving cavity S1 of the shielding 112.
The in-pile component lifting system 100 of the present application, in the first aspect, can meet the transfer requirement of in-pile components of a miniaturized reactor, thereby being beneficial to improving the convenience of reactor refueling or maintenance while reducing the construction cost of miniaturized reactor facilities. In a second aspect, the in-pile component handling system 100 of the present application is also provided with a shield 112. In the transfer process, the in-pile member 300 is located in the accommodating cavity S1 of the shielding body 112, so that the influence of nuclear radiation of the in-pile member on the site can be reduced to a certain extent, and further safety of operators for performing in-pile member transfer and safety of field devices and environments can be protected.
In some embodiments, the material of the shield 112 includes lead, iron, stainless steel, and lead boron polyethylene. The material has a good nuclear radiation protection effect, so that the safety of personnel during transfer of the components in the pile is improved. However, the material of the shield 112 is not limited to the above-described ones.
In some embodiments, the inner wall of the shield 112 is provided with at least one sliding rail (not shown) extending in the height direction of the shield 112, and the gripping head 121 is provided with a slider (not shown) adapted to the sliding rail. When the crane drives the grabbing head 121 to enter the shielding body 112, the sliding blocks of the grabbing head 121 can be matched with the sliding rails on the inner wall of the shielding body 112. Thus, in the first aspect, the shield 112 is slidably connected to the gripper 121, which is advantageous for improving the reliability of the movement of the gripper 121 inside the shield 112. In the second aspect, the sliding rail can also play a role in guiding and limiting, so that the stability and accuracy of movement can be improved.
Further, the sliding fit of the guide rail and the slider may be varied. For example, one of the guide rails is a convex guide rail, and the sliding block is provided with a groove matched with the convex. Or alternatively, the guide rail is a groove-shaped guide rail, and the sliding block is provided with a protrusion matched with the groove. The application is not limited in this regard.
In some embodiments, as shown in fig. 1 and 2, the scooter 110 further includes a driving structure (not shown) connected to the scooter body 111 and a sealing floor 115 connected to an output end of the driving structure, the sealing floor 115 being configured to move relative to the scooter body 111 under the driving of the driving structure to seal or open an opening 1121 in the bottom of the shielding body 112. In this embodiment, the scooter 110 further includes a sealing floor 115. As shown in fig. 2, when the crane drives the spreader 120 to hoist the in-pile member 300, the sealing floor 115 is in an open state, i.e., the sealing floor 115 is not coupled with the opening at the bottom of the shielding 112, thereby avoiding blocking the movement of the spreader 120 and the in-pile member 300. As shown in fig. 3, after the hanger 120 lifts and moves the in-pile member 300 to the accommodating chamber S1 in the shielding body 112, the sealing floor 115 moves relative to the body 111 of the scooter under the driving of the driving structure, thereby sealing the opening 1121 in the bottom of the shielding body 112. Thus, the protection of nuclear radiation during hoisting is further improved, and the hoisting transfer safety is further improved. In addition, the sealing bottom plate 115 may also serve as a load-bearing bottom plate after the sealing bottom plate 115 seals the opening 1121 in the bottom of the shield 112. In this way, the external crane can ensure that the gripping head 121 of the spreader 120 and the upper or lower in-pile member 310, 320 are in a stable state within the receiving cavity S1 of the shielding 112 without continuing to connect the lifting portion 122 while moving the scooter 110. Further, the driving structure may be a linear driving assembly such as a cylinder driving structure, a hydraulic cylinder driving structure, or a rotary-to-linear motion driving assembly such as a ball screw driving structure, a synchronous belt driving structure, or the like, which is not limited in the present application.
In some embodiments, as shown in fig. 1 and 2, a nuclear reactor includes a reactor placement point 400, the reactor placement point 400 including a reactor compartment 410. The reactor compartment 410 includes a hatch 411, a first sub-compartment 412 located below the hatch 411, and a second sub-compartment 413 in communication with the first sub-compartment 412 and located below the first sub-compartment 412. The front projection of the first sub-tank 412 onto the second sub-tank 413 covers the second sub-tank 413, the second sub-tank 413 being configured to house at least part of the structure of the pressure vessel 200.
The present embodiment proposes a specific structure of the nuclear reactor placement point 400. The nuclear reactor installation point 400 refers to a place and a position where a miniaturized nuclear reactor is installed. For example, the nuclear reactor placement point 400 may be an offshore mobile vessel or the like, to which the present application is not limited. The reactor placement point 400 includes a reactor compartment 410. The reactor compartment 410 is used for housing the pressure vessel 200 and the like. Specifically, the reactor compartment 410 includes a hatch 411, a first sub-compartment 412, and a second sub-compartment 413. The front projection of the first sub-cabin 412 on the second sub-cabin 413 covers the second sub-cabin 413, which means that the second sub-cabin 413 is a small cabin, the first sub-cabin 412 is a large cabin, and the interface of the two sub-cabins is in a step shape. At least a portion of the pressure vessel 200 is located in the second sub-compartment 413, i.e., at least a portion of the pressure vessel 200 is below the step, being the deepest part of the reactor compartment 410. In this way, the pressure vessel 200 is located deep in the nuclear reactor placement point 400, so that the radiation of the nuclear reactor to the outside can be further reduced, and the safety thereof can be improved.
Further, as shown in fig. 1 and 2, the in-pile component lifting system 100 further includes a water jacket 130, the water jacket 130 being a hollow cylinder having openings at both ends, the water jacket 130 being for sealing engagement with an interface of the first sub-compartment 412 and the second sub-compartment 413, the water jacket 130 covering the second sub-compartment 413 in an orthographic projection of the second sub-compartment 413 in a case where the water jacket 130 is in sealing engagement with the interface.
In this embodiment, the in-pile component lifting system 100 further includes a water jacket 130. The water jacket 130 is a hollow cylinder having openings at both ends. Since the interface of the second sub-tank 413 and the first sub-tank 412 is stepped. With the water jacket 130 sealingly engaged with the interface, the orthographic projection of the water jacket 130 at the second sub-compartment 413 covers the second sub-compartment 413. Thus, the water jacket 130 may be fitted over the outside of the second sub-tank 413, and a portion of the pressure vessel 200 penetrating into the second sub-tank 413 may be freely accessed through the water jacket 130. When the upper cover of the pressure vessel 200 is removed and the hoisting of the in-pile member is not started yet, the radioactive substances inside the pressure vessel 200 are exposed, thereby causing damage to the human body. Therefore, before the upper cover of the pressure vessel 200 is removed, the water jacket 130 may be placed on the interface between the second sub-chamber 413 and the first sub-chamber 412, the two sub-chambers may be sealed and combined, and then water may be injected into the water jacket 130 to shield a portion of nuclear radiation. The drams 110 of the in-pile component lifting system 100 are then positioned over the hatches 411 of the reactor compartment 410 for lifting operations. Thus, the hoisting safety is further improved.
Further, as shown in fig. 3 and 6 and referring to fig. 1, the reactor placement point 400 further includes a storage pool 420 at one side of the reactor compartment, and a first storage bin 421 for placing the upper internals 310 and a second storage bin 422 for placing the lower internals 320 are provided in the storage pool 420. The reactor placement point 400 is provided with two guide rails 430 extending in a first direction, which is the direction from the reactor compartment 410 to the storage pool 420, between the two guide rails 430, along with the storage pool 420 and the reactor compartment 410. The wheels 113 are configured to move on the rails 430 to move the scooter 110.
In this embodiment, the reactor placement point 400, for example, an offshore mobile vessel, also includes a storage pool 420. The reactor placement point 400 is provided with two guide rails 430. In this way, the wheels 113 of the scooter 110 may move on the rail 430. The movement of the scooter 110 to the point where the opening 1121 of the shield 112 on the scooter 110 is aligned with the hatch 411 of the reactor compartment 410 may be stopped and then the lifting of the in-pile member 300 may begin. After the upper internals 310 are lifted, the scooter 110 may continue to be driven on the rail 430. When the opening 1121 of the shielding 112 is aligned with the first storage bin 421, the spreader 120 may lower the upper internals 310 from within the receiving cavity S1 of the shielding 112 into the first storage bin 421, completing the storage of the upper internals 310. After the lower internals 320 are lifted, the drams 110 may be driven on the rails 430. When the opening 1121 of the shielding 112 is aligned with the second storage bin 422, the spreader 120 may lower the lower internals 320 from within the receiving cavity S1 of the shielding 112 into the second storage bin 422, completing storage of the lower internals 310. As can be seen from the above, the convenience of transferring the in-stack member 300 is advantageously improved by the guiding action of the guide rail 430.
Further, the in-pile component lifting system 100 further includes a controller (not shown) and a first position sensor (not shown), a second position sensor (not shown), and a third position sensor (not shown) disposed on the guide rail 430. The first position sensor, the second position sensor and the third position sensor are electrically connected with the controller. The first position sensor is configured to emit a first position signal when the opening 1121 of the shield 112 is aligned with the hatch 411, the second position sensor is configured to emit a second position signal when the opening 1121 of the shield 112 is aligned with the first storage compartment 421, and the third position sensor is configured to emit a third position signal when the opening 1121 of the shield 112 is aligned with the second storage compartment 422. The controller is configured to send an alarm signal when receiving one of the first position signal, the second position signal, and the third position signal.
In this embodiment, three position sensors are disposed on the guide rail 430, and by using the three position sensors, the accuracy of aligning the opening 1121 of the shielding 112 with the hatch 411 of the reactor compartment 410, the first storage compartment 421, and the second storage compartment 422 can be improved. In addition, when an external person receives an alarm signal, it indicates that the opening 1121 of the shielding body 112 is aligned with the hatch 411 of the reactor compartment 410, or that the opening 1121 of the shielding body 112 is aligned with the first storage compartment 421, or that the opening 1121 of the shielding body 112 is aligned with the second storage compartment 422, so that the lifting, transferring and storing of the in-pile member 300 can be performed in time, thereby further facilitating the lifting and transferring convenience.
In some embodiments, as shown in fig. 4, the gripper 121 includes a gripper body 1211 and a plurality of connection rods 1212 rotatably connected to the gripper body 1211 and extending in a height direction of the shielding body 112, and each of the upper and lower in-pile members 310 and 320 is provided with connection holes (not shown) adapted to the connection rods, and the connection rods 1212 are configured to be connected to or disconnected from the connection holes by rotation. The present application proposes a way of removably connecting the gripping head 121 with the upper internals 310 or the lower internals 320. That is, the plurality of connecting rods 1212 may rotate relative to the bit body 1211 and then be removably connected to either the upper or lower in-pile members 310, 320 by rotation. The mode is a common mode of lifting the in-pile components by the in-pile component lifting tool of the large nuclear power station, has a simple and reliable structure, and is beneficial to improving the convenience of connecting the grabbing head 121 with the upper in-pile component 310 or the lower in-pile component 320.
Further, as shown in fig. 4, the in-pile component lifting system 100 further includes an operating platform 140 disposed above the head body 1211. The operating platform 140 is provided with a second controller (not shown) electrically connected to the connecting rod 1212, the controller being configured to control the rotation of the connecting rod. The operation platform 140 may be used for personnel to perform related hoisting operations, such as connection of the in-pile member 300 to the gripper 121, connection of the hoisting portion 122 to an external crane, etc., so as to facilitate improvement of functionality of the in-pile member hoisting system 100. In addition, the operation platform 140 is further provided with a second controller, and the second controller intelligently controls the connection of the connecting rod 1212 with the upper in-pile member 310 or the lower in-pile member 320, thereby further facilitating the connection of the in-pile member hoisting system 100 with the in-pile member 300.
Further, the edge of the operation platform 140 is further provided with a guard rail 141, so that the safety of personnel operation is improved.
In some embodiments, as shown in fig. 4, the lifting portion 122 includes a lifting ring 1221 and a plurality of lifting rods 1222 connected to the lifting ring 1221, and the other ends of the plurality of lifting rods 1222 are connected to the head body 1211. The present embodiment illustrates a specific structure of the hanging portion 122. The hoist ring 1221 is connected to an external hoist, and then the head 121 and the in-pile member 300 are hoisted by the hoist rod 1222, which is simple and reliable. Further, the number of the hanger rods 1222 may be reasonably set according to the weight of the hoist, and the plurality of hanger rods 1222 may be uniformly arranged in the circumferential direction of the head body 1211. In this way, the force uniformity of the boom 1222 is advantageously improved.
The technical features of the above-described embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above-described embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples illustrate only a few embodiments of the application, which are described in detail and are not to be construed as limiting the scope of the application. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of protection of the present application is to be determined by the appended claims.

Claims (10)

1. An in-stack component handling system for handling said in-stack components within a miniaturized nuclear reactor pressure vessel, said pressure vessel including an upper cap and a barrel sealingly engaged with said upper cap, said in-stack components including an upper in-stack component and a lower in-stack component, said in-stack component handling system comprising:
the scooter comprises a scooter body, a plurality of wheels connected with the scooter body and a shielding body arranged on the scooter body, wherein the wheels are configured to drive the scooter to move, the shielding body extends along the thickness direction of the scooter body, two ends of the shielding body are provided with openings, and the openings penetrate through the shielding body and the scooter body to form a containing cavity for containing the upper or lower in-pile components; and
the lifting device comprises a grabbing head and a lifting part connected with the grabbing head, wherein the grabbing head is used for being connected with an upper internal pile member or a lower internal pile member, the lifting part is used for being connected with an external crane, and the grabbing head is configured to move in the shielding body along the height direction of the shielding body under the driving of the lifting part.
2. The in-pile component lifting system of claim 1, wherein the material of the shield comprises lead, iron, stainless steel, and lead boron polyethylene.
3. The in-pile component lifting system according to claim 1, characterized in that the inner wall of the shielding body is provided with at least one sliding rail extending in the height direction of the shielding body, and the gripping head is provided with a sliding block adapted to the sliding rail.
4. The in-pile component lifting system of claim 1, further comprising a drive structure coupled to the body of the scooter and a sealing floor coupled to an output end of the drive structure, the sealing floor configured to move relative to the body of the scooter under the drive of the drive structure to seal or open the opening in the bottom of the shield.
5. The in-pile component lifting system of claim 1, wherein the nuclear reactor includes a reactor placement point including a reactor compartment including a hatch, a first sub-compartment positioned below the hatch, and a second sub-compartment in communication with and positioned below the first sub-compartment, an orthographic projection of the first sub-compartment at the second sub-compartment covering the second sub-compartment, the second sub-compartment configured to house at least a portion of a structure of the pressure vessel;
the hoisting system for the internal components of the pile further comprises a water jacket, wherein the water jacket is a hollow cylinder with openings at two ends and is used for being in sealing joint with an interface of the first sub-cabin and the second sub-cabin, and under the condition that the water jacket is in sealing joint with the interface, the orthographic projection of the water jacket on the second sub-cabin covers the second sub-cabin.
6. The internals hoist system of claim 5, wherein the reactor placement point further includes a storage pond located on one side of the reactor compartment, the storage pond having a first storage compartment disposed therein for the upper internals and a second storage compartment disposed therein for the lower internals;
the reactor placement point is provided with two guide rails extending along a first direction, the storage water tank and the reactor cabin are positioned between the two guide rails, and the first direction is the direction from the reactor cabin to the storage water tank;
the wheels are configured to move on the rail to move the scooter.
7. The in-pile component lifting system of claim 6, further comprising a first controller and first, second, and third position sensors disposed on the rail;
the first, second, and third position sensors are each electrically connected to the first controller, the first position sensor configured to emit a first position signal when the opening of the shield is aligned with the hatch, the second position sensor configured to emit a second position signal when the opening of the shield is aligned with the first storage bin, and the third position sensor configured to emit a third position signal when the opening of the shield is aligned with the second storage bin;
the first controller is configured to send an alarm signal when receiving one of the first position signal, the second position signal, and the third position signal.
8. The in-pile member lifting system according to claim 1, wherein the gripper includes a gripper body and a plurality of connection bars rotatably connected to the gripper body and extending in a height direction of the shield body, the upper in-pile member and the lower in-pile member are each provided with a connection hole adapted to the connection bar, and the connection bars are configured to be connected to or disconnected from the connection holes by rotation.
9. The in-pile component handling system of claim 8, further comprising an operating platform disposed above the gripper body;
the operating platform is provided with a second controller electrically connected with the connecting rod, and the second controller is configured to control the connecting rod to rotate.
10. The in-pile component lifting system of claim 9, wherein the lifting portion includes a lifting ring and a plurality of lifting rods connected to the lifting ring, and the other ends of the plurality of lifting rods are connected to the head body.
CN202310549555.0A 2023-05-16 2023-05-16 Hoisting system for internal components Pending CN116588787A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202310549555.0A CN116588787A (en) 2023-05-16 2023-05-16 Hoisting system for internal components

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202310549555.0A CN116588787A (en) 2023-05-16 2023-05-16 Hoisting system for internal components

Publications (1)

Publication Number Publication Date
CN116588787A true CN116588787A (en) 2023-08-15

Family

ID=87593207

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202310549555.0A Pending CN116588787A (en) 2023-05-16 2023-05-16 Hoisting system for internal components

Country Status (1)

Country Link
CN (1) CN116588787A (en)

Similar Documents

Publication Publication Date Title
US3910006A (en) Fuel element handling arrangement and method
US4450134A (en) Method and apparatus for handling nuclear fuel elements
US5661768A (en) Spent nuclear fuel (SNF) dry transfer system
US6793450B2 (en) Below grade cask transfer facility
US4069923A (en) Buoyancy elevator for moving a load in an industrial facility such as a nuclear power plant
KR101531780B1 (en) Elevation-type thruster apparatus
EP2215638A1 (en) Canister transfer system with independent traveling shielded bell
US6920963B2 (en) Apparatus having vertically movable personnel cages for a spreader
CN102693770A (en) Coordinate ground vehicle system of nuclear power plant
KR102220826B1 (en) Method and device for repairing damage to a container wall located under water
US5369676A (en) Reactor refueling mechanism
CN116588787A (en) Hoisting system for internal components
US8908821B2 (en) Core-structure storing method
CN110648774B (en) Vehicle-mounted mobile material changing system and material changing method
CN208802119U (en) A kind of personnel applied to offshore marine structure, which step on, to take a lift
JP2015517648A (en) Nuclear power plant fuel pool
CN111383786B (en) Method for changing material of pool reactor
CN113744906B (en) Dismounting device for intermediate heat exchanger
US20030043953A1 (en) Reactor vessel handling method
CN107195348B (en) A reload system for integration heap
CN114197057B (en) Monocrystalline silicon neutron irradiation device and method
CN100460308C (en) Rubber membrane sealed type air storage cabinet thin shell top multiple-point digital control integrated raising method
US5133466A (en) Wet lift rig
JPH1184052A (en) Method for carrying out in-pile structure of pressurized water reactor
CN214690069U (en) Marker ship for channel survey

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination