CN112299238A - Hoisting tool for nuclear power plant retired upper reactor internals - Google Patents
Hoisting tool for nuclear power plant retired upper reactor internals Download PDFInfo
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- CN112299238A CN112299238A CN202011094402.4A CN202011094402A CN112299238A CN 112299238 A CN112299238 A CN 112299238A CN 202011094402 A CN202011094402 A CN 202011094402A CN 112299238 A CN112299238 A CN 112299238A
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- central support
- power plant
- nuclear power
- support
- hydraulic telescopic
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- 239000000725 suspension Substances 0.000 claims abstract description 43
- 230000005855 radiation Effects 0.000 abstract description 6
- 238000000034 method Methods 0.000 description 9
- 239000000306 component Substances 0.000 description 8
- 238000010586 diagram Methods 0.000 description 6
- 230000000694 effects Effects 0.000 description 4
- 238000012549 training Methods 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 238000013459 approach Methods 0.000 description 1
- 230000002457 bidirectional effect Effects 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002035 prolonged effect Effects 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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Classifications
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B66—HOISTING; LIFTING; HAULING
- B66C—CRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
- B66C1/00—Load-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
- B66C1/10—Load-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
- B66C1/42—Gripping members engaging only the external or internal surfaces of the articles
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B66—HOISTING; LIFTING; HAULING
- B66C—CRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
- B66C15/00—Safety gear
Abstract
The invention discloses a hoisting tool for a nuclear power plant retired upper reactor internals, which comprises: the hydraulic pipeline is arranged in the central support and is connected with the hydraulic pump; the three suspension arms are arranged at intervals of 120 degrees around the central support, one end of each suspension arm is rotatably connected to the central support, and the other end, far away from the central support, of each suspension arm is provided with a grapple; the three hydraulic telescopic cylinders are arranged at intervals of 120 degrees around the central support, one end of each hydraulic telescopic cylinder is rotatably connected to the central support, the other end, far away from the central support, of each hydraulic telescopic cylinder is connected to the corresponding suspension arm, and the hydraulic telescopic cylinders stretch and retract under the driving of the hydraulic pumps to drive the suspension arms to grab and release; and the three balance rods are respectively arranged between two adjacent suspension arms and can slide up and down along the sliding grooves formed in the suspension arms. Compared with the prior art, the hoisting tool for the nuclear power plant retired upper reactor component can control hoisting actions by remotely controlling the hydraulic pump, is simple to operate, and can avoid radiation risks and conventional industrial risks.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a hoisting tool for an upper reactor internals in decommissioning of a nuclear power plant.
Background
The nuclear power plant upper reactor internals are located in the reactor pressure vessel and above the reactor core fuel assemblies and mainly play a role in supporting and fixing the reactor core assemblies, ensuring control rod drive line centering, guiding control rod movement and distributing flow. The upper reactor internals comprises a control rod guide cylinder, an upper support plate, a support column and a reactor core upper plate, wherein the upper support plate is a perforated plate with a skirt type cylinder, and three connecting sliding holes for installing a hoisting and screwing piece are arranged on a flange surface of the upper reactor internals so as to be matched with the reactor internals to dismantle the upper reactor internals as a whole; the reactor core upper plate is a porous circular plate and is connected with the upper supporting plate into a whole through 40 supporting columns; the control rod guide cylinder is divided into an upper part and a lower part which are fixed on the upper support plate by bolts.
During nuclear power plant reactor installation and refueling servicing, internals spreaders are commonly used as specialized tools for lifting the upper and lower internals. The in-pile member lifting appliance in the prior art generally comprises an operation assembly, an operation platform, a lifting assembly, a triangular support frame and a support ring, and the lifting assembly, the triangular support frame and the support ring are fixedly lifted together by matching a lifting appliance meshing pin at the lower end of an upright post of the operation assembly and a lifting screwing piece of the in-pile member. Before formal hoisting, the in-pile member hoisting tool needs an operator to assemble the five types of parts together on a platform of 20m, wherein the total number of the parts is more than 400; when the hoisting task is executed, an operator can only screw the operating assembly into the hoisting and screwing-in piece by turning over the railing from the loading and unloading machine and then turning down the railing to a hoisting tool operating platform which is 10 m away from the reactor pool.
However, the prior art internals spreader has the following disadvantages:
1) the lifting appliance of the in-pile member is complex to operate and needs to be assembled on site, so that the operation working hours are prolonged, and the irradiation risk of field workers is increased;
2) the assembly process of the in-core member lifting appliance is complex, and the nuclear power plant needs to reorganize related personnel for skill training to be familiar with operation before entering the decommissioning stage, so that the comprehensive cost is high;
3) the lifting appliance of the reactor internals has the weight of 4t and the height of 10 meters, is inconvenient to control after being connected with the ring crane, can lift the reactor internals in place only by matching with equipment such as a guide rod and the like, and cannot meet the flexible requirement of lifting the upper supporting plate and the reactor core upper plate to the temporary cutting device;
4) personnel can manually connect/disconnect the lifting appliance and the reactor internals from the operation platform only by turning over the railing from the loading and unloading machine platform for multiple times, so that the conventional industrial risks such as falling are increased;
5) the reactor core lifting appliance can lift equipment only by matching with the lifting screwed piece on the upper supporting plate, and cannot lift the reactor core upper plate which is not assembled with the lifting screwed piece after the reactor core upper plate and the upper supporting plate are disconnected;
6) the large size of the lifting appliance occupies the space in a reactor plant, and brings inconvenience to the deployment of other tools;
7) many fine parts adopted by the in-pile components need to be maintained regularly, and if the spent fuel storage period after the shutdown of the nuclear power plant is not kept properly, the in-pile components cannot be used normally.
The existing in-pile component lifting appliance is specially designed for fine operation adopted for protecting the reactor in-pile components from being damaged in the operation stage, and during the refueling of a nuclear power plant, the whole upper in-pile component is generally lifted to a storage rack of an in-pile component pool by using the in-pile component lifting appliance for temporary storage. However, during the decommissioning, after the control rod guide cylinders are removed and the support columns are disconnected from the upper support plate and the upper core plate, the upper support plate and the upper core plate are respectively lifted to specific cutting positions and further separated so as to be loaded into a waste container and sent to a radioactive waste temporary storage for treatment or disposal. The environment and the use demand of the power plant in the retirement stage are greatly changed, and the original in-pile member lifting appliance is not suitable any more.
In view of the above, there is a need for a hoisting tool for decommissioning upper internals of a nuclear power plant, which is simple to operate and can reduce the intake of personnel.
Disclosure of Invention
The invention aims to: the hoisting tool for the nuclear power plant retired upper reactor internals is simple to operate and capable of reducing the intake of personnel dosage.
In order to achieve the above object, the present invention provides a hoisting tool for a decommissioned upper internals of a nuclear power plant, comprising:
the hydraulic pipeline is arranged in the central support and is connected with the hydraulic pump;
the suspension arms are uniformly arranged around the central support at intervals, one end of each suspension arm is rotatably connected to the central support, and the other end, far away from the central support, of each suspension arm is provided with a grabbing hook used for hooking the flange of the upper support plate and the edge of the upper plate of the reactor core;
the hydraulic telescopic cylinders are uniformly arranged around the central support at intervals, one ends of the hydraulic telescopic cylinders are rotatably connected to the central support, the other ends of the hydraulic telescopic cylinders, far away from the central support, are connected to the corresponding suspension arms, and the hydraulic telescopic cylinders drive the suspension arms to grab and release through stretching under the driving of the hydraulic pump; and
and the balance rods are respectively arranged between two adjacent suspension arms and can slide up and down along the sliding grooves formed in the suspension arms.
As an improvement of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant, the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant is provided with three suspension arms, three hydraulic telescopic cylinders and three balance rods, wherein the three suspension arms are arranged around a central support at intervals of 120 degrees, the three hydraulic telescopic cylinders are arranged around the central support at intervals of 120 degrees, and two ends of each balance rod are respectively arranged in sliding chutes formed in two adjacent suspension arms.
As an improvement of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant, the central support is provided with a first support trunnion, the suspension arm is provided with a first suspension arm lug ring, and the first suspension arm lug ring is connected to the first support trunnion through a bolt and can freely rotate around the first support trunnion.
As an improvement of the hoisting tool for the nuclear power plant retired upper reactor internals, the central support is provided with a second support trunnion, one end, close to the central support, of the hydraulic telescopic cylinder is provided with a hydraulic telescopic cylinder lug ring, and the hydraulic telescopic cylinder lug ring is connected with the second support trunnion of the central support through a bolt.
As an improvement of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant, the first support trunnion is positioned below the second support trunnion.
As an improvement of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant, the first support trunnion and the second support trunnion are welded on the central support.
As an improvement of the hoisting tool for the nuclear power plant retired upper reactor internals, one end, far away from the central support, of the hydraulic telescopic cylinder is provided with a hydraulic telescopic cylinder trunnion, the suspension arm is provided with a second suspension arm lug ring, and the second suspension arm lug ring is connected with the trunnion of the hydraulic telescopic cylinder through a bolt.
As an improvement of the hoisting tool for the nuclear power plant retired upper reactor internals, a lifting lug is arranged above the suspension arm and close to the grapple.
As an improvement of the hoisting tool for the nuclear power plant retired upper reactor internals, a convex groove is formed in the side wall of the lifting hook, inward-inclined rollers are arranged at two ends of the balancing rod, and the inward-inclined rollers can slide up and down in the groove.
As an improvement of the hoisting tool for the ex-service upper reactor internals of the nuclear power plant, the hydraulic pump is connected with the hydraulic telescopic cylinder through an extension hydraulic pipe.
Compared with the prior art, the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant has the following technical effects:
1) the upper supporting plate and the upper reactor core plate assembly which are disassembled can be respectively hoisted by the same tool;
2) the action of the lifting appliance can be controlled only by controlling the power output of the hydraulic pump, the operation process is simple, the training of personnel is facilitated, and the operation time is shortened while the human error is reduced;
3) an operator remotely controls and lifts the upper supporting plate and the upper reactor core plate at the side of the reactor pool, so that radiation risks and conventional industrial risks are avoided;
4) the hoisting tool is small in size and light in weight, can be integrally transported to a 20m platform of the reactor plant after being assembled outside the reactor plant, and reduces the operation time in a radiation environment.
Drawings
The hoisting tool for the decommissioned upper reactor internals of the nuclear power plant and the technical effects thereof are described in detail with reference to the accompanying drawings and the specific implementation modes, wherein:
FIG. 1 is a schematic structural diagram of a hoisting tool for an upper reactor internals in decommissioning of a nuclear power plant.
Fig. 2 is a schematic structural diagram of a central support of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant.
FIG. 3 is a schematic structural diagram of a boom of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant.
Fig. 4 is a schematic structural diagram of a hydraulic telescopic cylinder of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant.
Fig. 5 is a structural schematic diagram of a balance bar of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant.
Fig. 6A and 6B are schematic diagrams of hoisting states of the hoisting tool for the decommissioned upper reactor core component of the nuclear power plant respectively, and respectively hoist the reactor core upper plate and the upper supporting plate.
The attached drawings are marked as follows:
10-a central support; 100-first bracket trunnion; 102-a second bracket trunnion;
20-a boom; 200-a first boom earring; 202-a second boom earring; 204-lifting lug; 206-grapple; 208-a chute;
30-hydraulic telescopic cylinder; 300-hydraulic telescopic cylinder earrings; 302-hydraulic telescopic cylinder trunnion;
40-a balance bar; 400-cross bar; 402-tilt-in roller.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention more clear, the present invention is further described in detail below with reference to the accompanying drawings and the detailed description. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1 to 5, the present invention provides a hoisting tool for an out-of-service upper reactor internals of a nuclear power plant, comprising:
a center support 10, wherein a hydraulic pipeline (not shown) is arranged in the center support 10 and is connected with a hydraulic pump (not shown);
a plurality of suspension arms 20 which are arranged around the central support 10 at intervals, wherein one end of each suspension arm 20 is rotatably connected to the central support 10, and the other end of each suspension arm 20, which is far away from the central support 10, is provided with a grapple 206 for hooking the edges of the upper support plate and the upper plate of the reactor core;
the hydraulic telescopic cylinders 30 are uniformly arranged around the central support 10 at intervals, one end of each hydraulic telescopic cylinder 30 is rotatably connected to the central support 10, the other end, far away from the central support 10, of each hydraulic telescopic cylinder 30 is connected to the corresponding suspension arm 20, and the hydraulic telescopic cylinders 30 drive the suspension arms 20 to grab and release through stretching under the driving of hydraulic pumps; and
and a plurality of balance rods 40 which are respectively arranged between two adjacent suspension arms 20 and can slide up and down along the slide grooves 208 formed on the suspension arms 20.
In the embodiment shown in fig. 1, the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant is provided with three booms 20, three hydraulic telescopic cylinders 30 and three balance rods 40, wherein the three booms 20 are arranged around a central support 10 at intervals of 120 °, the three hydraulic telescopic cylinders 30 are arranged around the central support 10 at intervals of 120 °, and two ends of each balance rod 40 are respectively arranged in sliding grooves 208 formed in two adjacent booms 20.
Referring to fig. 2, the central support 10 is a hexagonal prism structure, which is a core stressed portion of the whole hoisting tool, and the upper and lower surfaces of the central support are welded with the second support trunnion 102 and the first support trunnion 100, which provide a rotation pivot for the hydraulic telescopic cylinder 30 and the boom 20. Inside the center frame 10, hydraulic lines connected to the hydraulic telescopic cylinder 30 may be laid to transmit hydraulic power.
Referring to fig. 2 and 3, the boom 20 performs the function of actually picking up/lowering the upper support plate and the upper core plate, the center support 10 is provided with a first support trunnion 100, the boom 20 is provided with a first boom trunnion 200, and the first boom trunnion 200 is bolted to the first support trunnion 100 and can freely rotate around the first support trunnion 100. The end of the boom 20 far away from the central support 10 is provided with a grapple 206 which can hook and fix the reactor core upper plate and the upper support plate and prevent the two from sliding and falling off in the hoisting process. A convex groove 208 is dug on the side wall of the boom 20, and the inward-inclined rollers 402 at the two ends of the balance bar 40 can slide up and down in the groove 208. A lifting lug 204 is provided above boom 20 adjacent to grapple 206, and lifting lug 204 may be connected to a looped crane hook.
When the hydraulic telescopic cylinder 30 extends, a downward moment is applied to the boom 20, so that the boom 20 is forced to rotate downward around the first boom eye 200, and the three booms 20 approach to the center to realize a 'grabbing' action; the hydraulic telescopic cylinder 30 is shortened to generate an upward moment on the boom 20, so that the boom 20 is forced to rotate upward around the first boom eye 200, and the three booms 20 move away from the center to realize a 'loosening' action.
Referring to fig. 4, one end of the hydraulic telescopic cylinder 30 close to the central support 10 is provided with a hydraulic telescopic cylinder ear ring 300, and one end of the hydraulic telescopic cylinder 30 far from the central support 10 is provided with a hydraulic telescopic cylinder trunnion 302. The hydraulic telescopic cylinder ear 300 is bolted to the second support trunnion 102 of the central support 10 and the hydraulic telescopic cylinder trunnion 30 is bolted 2 to the second boom ear 202. When the hydraulic pump is pressurized in the positive direction, the hydraulic telescopic cylinder 30 extends to force the boom 20 to rotate downwards, and meanwhile, the hydraulic telescopic cylinder 30 also rotates to be close to the central support 10; the hydraulic pump is pressurized in reverse direction and the hydraulic telescopic cylinder 30 is shortened, so that the boom 20 rotates upwards while the hydraulic telescopic cylinder 30 rotates around the hydraulic telescopic cylinder earring 300 away from the center support 10. It should be noted that the hydraulic telescopic cylinder adopted by the invention is consistent with the existing bidirectional hydraulic telescopic cylinder in method and principle.
Referring to fig. 5, the balance bar 40 includes a steel cross bar 400 and inward-inclined rollers disposed at two ends of the steel cross bar 400 for unifying the inclination angles of the three suspension arms 20. When the boom 20 is grabbed and loosened, the three balance rods 40 can slide up and down along the slide grooves 208 in the boom 20, so that a certain boom 20 is prevented from having a large action amplitude, and the action consistency of the three booms 20 is maintained. Under the restriction of the balance bar 40, the inclination angles of the three suspension arms 20 are consistent all the time, and the grapple 206 is also maintained on the same horizontal plane, so that the upper support plate and the reactor core upper plate are ensured to be horizontal all the time in the hoisting process.
The hydraulic pump used in the hoisting tool for the ex-service upper reactor internals of the nuclear power plant is connected with the hydraulic telescopic cylinder 30 by virtue of the extension hydraulic pipe, and is placed on a platform of 20m in a reactor factory building during operation, so that the strong radioactivity of the reactor internals is prevented from damaging electronic components in the reactor factory building. It should be noted that the hydraulic pump used in the present invention is consistent with the existing hydraulic pump in terms of method and principle.
Referring to fig. 6A and 6B, the implementation process of the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant of the present invention is as follows:
assembling a central support 10, a suspension arm 20, a hydraulic telescopic cylinder 30 and a balance rod 40 under the radiation environment of the foreign objects in the reactor factory;
the assembled hoisting tool and the hydraulic pump are transported to a 20m platform of a reactor factory together;
connecting a hoisting tool with a main hoisting hook by means of a sling and a shackle, and adjusting the levelness;
connecting the central support 10 with a hydraulic pump by using a hydraulic extension pipe, testing that the hydraulic power of the lifting appliance is normal, and normally grasping and releasing the lifting arm 20;
the lifting appliance is lifted to the position right above the upper plate of the upper supporting plate/reactor core in the reactor pool, and the lifting appliance is slowly lowered to a proper position where the lifting arm 20 can grab the upper plate of the upper supporting plate/reactor core (the lifting appliance is paid attention to timely paying off of the hydraulic extension pipe in the lowering process to prevent breaking);
the hydraulic pump supplies pressure, the three suspension arms 20 are close to the center, and the edge of the upper support plate flange/reactor core upper plate is seized;
lifting the main hook by a lifting ring, and lifting the upper support plate/reactor core upper plate;
the ring crane moves horizontally to convey the upper support plate/reactor core upper plate to a designated cutting position;
slowly descending the upper support plate/reactor core upper plate, after the upper support plate/reactor core upper plate is pressed by the hydraulic pump, keeping the three suspension arms 20 away from each other, and loosening the upper support plate/reactor core upper plate;
lifting the lifting appliance to the side of the reactor pool, disassembling the hydraulic extension pipe, lifting the hydraulic extension pipe to a transport trolley, and transporting the hydraulic extension pipe out of a reactor plant.
Compared with the prior art, the hoisting tool for the decommissioned upper reactor internals of the nuclear power plant has the following technical effects:
1) the upper supporting plate and the upper reactor core plate assembly which are disassembled can be respectively hoisted by the same tool;
2) the action of the lifting appliance can be controlled only by controlling the power output of the hydraulic pump, the operation process is simple, the training of personnel is facilitated, and the operation time is shortened while the human error is reduced;
3) an operator remotely controls and lifts the upper supporting plate and the upper reactor core plate at the side of the reactor pool, so that radiation risks and conventional industrial risks are avoided;
4) the hoisting tool is small in size and light in weight, can be integrally transported to a 20m platform of the reactor plant after being assembled outside the reactor plant, and reduces the operation time in a radiation environment.
The present invention can be modified and adapted appropriately from the above-described embodiments, according to the principles described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (10)
1. The utility model provides a nuclear power plant retires upper portion internals lifting device which characterized in that includes:
the hydraulic pipeline is arranged in the central support and is connected with the hydraulic pump;
the suspension arms are uniformly arranged around the central support at intervals, one end of each suspension arm is rotatably connected to the central support, and the other end, far away from the central support, of each suspension arm is provided with a grabbing hook used for hooking the flange of the upper support plate and the edge of the upper plate of the reactor core;
the hydraulic telescopic cylinders are uniformly arranged around the central support at intervals, one ends of the hydraulic telescopic cylinders are rotatably connected to the central support, the other ends of the hydraulic telescopic cylinders, far away from the central support, are connected to the corresponding suspension arms, and the hydraulic telescopic cylinders drive the suspension arms to grab and release through stretching under the driving of the hydraulic pump; and
and the balance rods are respectively arranged between two adjacent suspension arms and can slide up and down along the sliding grooves formed in the suspension arms.
2. The nuclear power plant decommissioning upper reactor internals hoisting tool according to claim 1, wherein the nuclear power plant decommissioning upper reactor internals hoisting tool is provided with three booms, three hydraulic telescoping cylinders and three balance rods, wherein the three booms are arranged around a central support at an interval of 120 °, the three hydraulic telescoping cylinders are arranged around the central support at an interval of 120 °, and two ends of each balance rod are respectively arranged in sliding grooves formed in two adjacent booms.
3. The nuclear power plant decommissioning upper internals hoisting tool according to claim 1, wherein the central support is provided with a first support trunnion and the boom is provided with a first boom ear, the first boom ear being bolted to the first support trunnion and being freely rotatable about the first support trunnion.
4. The hoisting tool for the decommissioned upper reactor internals of a nuclear power plant according to claim 3, wherein the central support is provided with a second support trunnion, one end of the hydraulic telescopic cylinder close to the central support is provided with a hydraulic telescopic cylinder trunnion ring, and the hydraulic telescopic cylinder trunnion ring is connected with the second support trunnion of the central support through a bolt.
5. The nuclear power plant decommissioning upper internals hoisting tool according to claim 4, wherein the first support trunnion is located below the second support trunnion.
6. The nuclear power plant decommissioning upper internals hoisting tool according to claim 4, wherein the first and second support trunnions are welded to the central support.
7. The hoisting tool for the decommissioned upper reactor internals according to claim 4, wherein one end of the hydraulic telescopic cylinder far away from the central support is provided with a hydraulic telescopic cylinder trunnion, the jib is provided with a second jib ear ring, and the second jib ear ring is connected with the trunnion of the hydraulic telescopic cylinder through a bolt.
8. The nuclear power plant decommissioning upper internals hoisting tool according to claim 1, wherein a lifting lug is provided above the boom near the grapple.
9. The nuclear power plant decommissioning upper reactor internals hoisting tool according to claim 1, wherein the side wall of the lifting hook is provided with a "convex" groove, and the two ends of the balance bar are provided with inward-inclined rollers which can slide up and down in the groove.
10. The nuclear power plant decommissioning upper internals hoisting tool according to any one of claims 1 to 9, wherein the hydraulic pump is connected with a hydraulic telescopic cylinder through an extended hydraulic pipe.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011094402.4A CN112299238A (en) | 2020-10-14 | 2020-10-14 | Hoisting tool for nuclear power plant retired upper reactor internals |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011094402.4A CN112299238A (en) | 2020-10-14 | 2020-10-14 | Hoisting tool for nuclear power plant retired upper reactor internals |
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| Publication Number | Publication Date |
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| CN112299238A true CN112299238A (en) | 2021-02-02 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202011094402.4A Pending CN112299238A (en) | 2020-10-14 | 2020-10-14 | Hoisting tool for nuclear power plant retired upper reactor internals |
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| CN (1) | CN112299238A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113793708A (en) * | 2021-06-11 | 2021-12-14 | 中国核工业第五建设有限公司 | In-position adjusting device and in-position adjusting method for lower reactor internals of nuclear power station |
| CN114014140A (en) * | 2021-11-04 | 2022-02-08 | 中广核研究院有限公司 | Reactor module hoisting device |
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| CN106185612A (en) * | 2016-08-31 | 2016-12-07 | 天津甘泉集团有限公司 | A kind of full-tubular pump rotor iron core hanging apparatus |
| CN205820702U (en) * | 2016-06-12 | 2016-12-21 | 张家港浦项不锈钢有限公司 | A kind of electric hydaulic orange-peel bucket |
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2020
- 2020-10-14 CN CN202011094402.4A patent/CN112299238A/en active Pending
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|---|---|---|---|---|
| JPH0753175A (en) * | 1993-08-19 | 1995-02-28 | Yoshiaki Takakura | Grabbler for scrap |
| JP2008214026A (en) * | 2007-03-05 | 2008-09-18 | Hitachi Constr Mach Co Ltd | Grapple |
| CN102070077A (en) * | 2009-10-29 | 2011-05-25 | 日立建机株式会社 | Grab |
| CN201980859U (en) * | 2011-04-11 | 2011-09-21 | 杭州电子科技大学 | Electric four-leaf hydraulic grab bucket |
| CN205820702U (en) * | 2016-06-12 | 2016-12-21 | 张家港浦项不锈钢有限公司 | A kind of electric hydaulic orange-peel bucket |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113793708A (en) * | 2021-06-11 | 2021-12-14 | 中国核工业第五建设有限公司 | In-position adjusting device and in-position adjusting method for lower reactor internals of nuclear power station |
| CN113793708B (en) * | 2021-06-11 | 2023-07-07 | 中国核工业第五建设有限公司 | Positioning adjustment device and positioning adjustment method for nuclear power station lower part in-pile components |
| CN114014140A (en) * | 2021-11-04 | 2022-02-08 | 中广核研究院有限公司 | Reactor module hoisting device |
| CN114014140B (en) * | 2021-11-04 | 2023-07-18 | 中广核研究院有限公司 | Reactor module hoist device |
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Application publication date: 20210202 |