CN108529443B - Lifting method for equipment in nuclear reactor control area - Google Patents
Lifting method for equipment in nuclear reactor control area Download PDFInfo
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- CN108529443B CN108529443B CN201810219676.8A CN201810219676A CN108529443B CN 108529443 B CN108529443 B CN 108529443B CN 201810219676 A CN201810219676 A CN 201810219676A CN 108529443 B CN108529443 B CN 108529443B
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- control area
- equipment
- temporary
- nuclear reactor
- temporary control
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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
- B66C19/00—Cranes comprising trolleys or crabs running on fixed or movable bridges or gantries
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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
- B66C13/00—Other constructional features or details
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- Mechanical Engineering (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a control area equipment hoisting device, which is used for hoisting equipment in a nuclear reactor control area (3) of an offshore nuclear power platform and comprises the following components: the temporary control area (1) is built on a deck (4) above the control area (3), covers a first equipment cabin door (40) above the control area (3) and is provided with a closed space, and a second equipment cabin door (10) is arranged on the side wall of the temporary control area (1); the lifting device (2) is arranged in the temporary control area (1) and used for lifting equipment between the temporary control area (1) and the control area (3). The invention also discloses a corresponding offshore nuclear power platform and a control area equipment hoisting method. By implementing the method, the integrity of the control area boundary can be ensured, the height of the offshore nuclear platform is reduced, and the economy and the self-navigation performance of the offshore nuclear platform are improved; meanwhile, the temporary control area can be commonly used for a plurality of offshore nuclear power platforms, and the adaptability is wide.
Description
Technical Field
The invention relates to the technical field of nuclear fuel transfer in an offshore nuclear power platform, in particular to a method for lifting equipment in a nuclear reactor control area.
Background
According to the radiation protection requirement of a nuclear power plant, corresponding protection measures are needed for operation, treatment and storage of radioactive objects, and a complete control area boundary is needed in the hoisting process of radioactive equipment.
In the prior art, the hoisting of the offshore nuclear power platform equipment in and out of the control area is realized by arranging corresponding hoisting devices and reserving hoisting spaces in a cabin where a reactor is located. The lifting device comprises a lifting mechanism arranged at the top of the cabin and an equipment transportation channel. The height of a lifting device and a lifting space arranged in a cabin where the reactor is located generally needs to be about ten meters; meanwhile, the control area is an area with higher radiation risk in the offshore nuclear power platform and is an area which needs and possibly needs special protection measures or safety measures. Therefore, in the process of lifting equipment, equipment lifting operation among the outside of the offshore nuclear power platform, the cabin where the reactor is located and the primary control area (such as a containment vessel) is realized by controlling the closing of the equipment channel at different stages.
Therefore, in the prior art, the operation space and the lifting device are arranged to increase the volume of the whole offshore nuclear power platform occupied by the control area, and certain requirements are required for the height of the platform.
Disclosure of Invention
The invention aims to solve the technical problem of providing a lifting device and a lifting method for equipment in a nuclear reactor control area and a corresponding offshore nuclear power platform, which can not occupy the volume of the offshore nuclear power platform, reduce the height of the offshore nuclear power platform and ensure the complete boundary of the control area in the lifting process of the equipment in the control area by adding a temporary control area and the lifting device.
In order to solve the technical problem, an embodiment of the present invention provides a control area equipment hoisting device for hoisting equipment in a nuclear reactor control area of an offshore nuclear power platform, including:
the temporary control area is built on a deck above the control area, covers the first equipment door above the control area and is provided with a closed space, and a second equipment door is arranged on the side wall of the temporary control area;
and the lifting device is arranged in the temporary control area and used for lifting the equipment between the temporary control area and the control area.
The temporary control area is fixed on a deck above the control area by adopting a detachable steel plate, and the fixing mode is welding or bolt connection.
Wherein, the temporary control area is square in shape.
Wherein the first equipment hatch door is a pneumatic gate or an electric gate.
The lifting device adopts one of a gantry crane, a travelling crane and a cantilever crane; the lifting device is arranged on a deck inside the temporary control area, connected with the deck through a rail and limited, and the rail is fixed on the deck through foundation bolts.
The lifting device adopts one of a gantry crane, a travelling crane and a cantilever crane; the track of the lifting device is arranged on the temporary control area body structure.
Correspondingly, in another aspect of the present invention, an offshore nuclear power platform is further provided, including a nuclear reactor, and a control area equipment handling device is disposed on a deck outside a control area of the nuclear reactor, where the control area equipment handling device includes:
the temporary control area is built on a deck above the control area, covers the first equipment door above the control area and is provided with a closed space, and a second equipment door is arranged on the side wall of the temporary control area;
and the lifting device is arranged in the temporary control area and used for lifting the equipment between the temporary control area and the control area.
The temporary control area is fixed on a deck above the control area by adopting a detachable steel plate, and the fixing mode is welding or bolt connection;
the temporary control area is square in shape;
the first equipment cabin door is a pneumatic gate or an electric gate.
The lifting device adopts one of a gantry crane, a travelling crane and a cantilever crane;
the lifting device is arranged on a deck in the temporary control area, is connected with the deck through a rail and is limited, and the rail is fixed on the deck through foundation bolts; or the track of the hoisting device is arranged on the temporary control area body structure.
Correspondingly, in another aspect of the embodiments of the present invention, there is also provided a method for lifting control area equipment, including the following steps:
the method comprises the steps that a control area equipment lifting device is built on a deck, located above a nuclear reactor control area, of an offshore nuclear power platform, and comprises a temporary control area and a lifting device;
opening a second equipment cabin door of the temporary control area, transporting required equipment into the temporary control area for temporary storage, and closing the second equipment cabin door of the temporary control area after transportation is finished;
opening a first equipment cabin door above the control area, carrying out lifting operation on the equipment between the control area and the temporary control area by a lifting device positioned in the temporary control area, and closing the first equipment cabin door above the control area after finishing the lifting operation of the equipment;
opening a second equipment cabin door of the temporary control area, and transporting the equipment needing to be transported to the outside out of the temporary control area;
and after all the hoisting work is finished, the temporary control area and the hoisting device are dismantled.
The implementation of the invention has the following beneficial effects:
in the embodiment of the invention, a temporary control area and a lifting device are arranged on a deck at the upper part of the control area; the hoisting device and the operation space are arranged in the temporary control area outside the control area, and on the premise of ensuring the integrity of the boundary of the control area, the installation, operation and maintenance space of hoisting equipment is not required to be arranged in the control area of the offshore nuclear power platform, so that the height of the platform is reduced, the compact layout of the control area is realized, and the economy of the offshore nuclear power platform is improved; meanwhile, for the offshore nuclear power platform with self-propulsion capability, the reduction of the height of the platform is also beneficial to reducing the swing of the platform in a storm environment, so that relatively stable propulsion speed and self-propulsion performance are guaranteed;
the temporary control area can be commonly used for a plurality of offshore nuclear power platforms, and has wide adaptability;
meanwhile, the lifting device can be constantly arranged on the upper part of the deck of the platform and can be used for lifting other material equipment of the platform.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to these drawings without creative efforts.
FIG. 1 is a schematic structural diagram of a first embodiment of an offshore nuclear power platform provided by the invention;
FIG. 2 is a schematic structural diagram of a second embodiment of an offshore nuclear power platform provided by the invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
As shown in fig. 1, a schematic structural diagram of a first embodiment of an offshore nuclear power platform provided by the present invention is shown, in this embodiment, the offshore nuclear power platform is an offshore nuclear power platform, and includes a nuclear reactor 5, a control area equipment handling device is disposed on a deck outside a control area of the nuclear reactor, and is configured to handle equipment in the nuclear reactor control area of the offshore nuclear power platform, and the control area equipment handling device includes:
a temporary control area 1 which is built on a deck 4 above a control area 3, covers a first equipment door 40 above the control area 3 and has a closed space, and a second equipment door 10 is arranged on the side wall of the temporary control area 1;
and the lifting device 2 is arranged in the temporary control area 1 and is used for lifting equipment between the temporary control area 1 and the control area 3.
The temporary control area 1 is a detachable structure, for example, it can be fixed on the deck 4 above the control area 3 by a detachable steel plate, and the fixing mode is welding or bolting, where the bolting needs to be able to achieve a certain airtight requirement.
In one embodiment, the temporary control area 1 has a square shape, and the inside is a closed space, it is understood that in other embodiments, the temporary control area 1 may have other shapes.
Wherein the first equipment door 40 is a pneumatic gate or an electric gate.
The lifting device 2 adopts one of a gantry crane, a travelling crane and a cantilever crane; the lifting device 2 is arranged on a deck in the temporary control area 1, connected with the deck through a rail 20 and limited, and the rail 20 is fixed on the deck through foundation bolts.
As shown in fig. 2, a schematic structural diagram of a second embodiment of the offshore nuclear power platform provided by the present invention is shown, in this embodiment, the structure of the second embodiment differs from that in the first embodiment in that in this embodiment, the track 20 of the lifting device 2 is arranged on the body structure of the temporary control area 1, and other structures are substantially similar and will not be described in detail herein.
Meanwhile, the invention also provides a control area equipment hoisting method, which specifically comprises the following steps:
the method comprises the following steps that a control area equipment lifting device shown in the figure 1 or 2 is built on a deck 4 of an offshore nuclear power platform above a nuclear reactor control area 3, and comprises a temporary control area 1 and a lifting device 2;
opening a second equipment cabin door 10 of the temporary control area 1, transporting required equipment into the temporary control area 1 for temporary storage, and closing the second equipment cabin door 10 of the temporary control area 1 after transportation is finished;
opening a first equipment cabin door 40 above the control area 3, carrying out lifting operation on the equipment between the control area 3 and the temporary control area 1 by a lifting device 2 positioned in the temporary control area 1, and closing the first equipment cabin door 40 above the control area 3 after finishing the lifting operation of the equipment;
opening a second equipment cabin door 10 of the temporary control area 1, and transporting the equipment needing to be transported to the outside out of the temporary control area 1;
and after all the hoisting work is finished, the temporary control area 1 is dismantled. It will be appreciated that in some embodiments, for example when the control area handling apparatus of figure 1 is employed, only the temporary control area 1 may be removed, leaving the trolley 2 for handling other material on deck.
The implementation of the invention has the following beneficial effects:
in the embodiment of the invention, a temporary control area and a lifting device are arranged on a deck at the upper part of the control area; the hoisting device and the operation space are arranged in the temporary control area outside the control area, and on the premise of ensuring the integrity of the boundary of the control area, the installation, operation and maintenance space of hoisting equipment is not required to be arranged in the control area of the offshore nuclear power platform, so that the height of the platform is reduced, the compact layout of the control area is realized, and the economy of the offshore nuclear power platform is improved; meanwhile, for the offshore nuclear power platform with self-propulsion capability, the reduction of the height of the platform is also beneficial to reducing the swing of the platform in a storm environment, so that relatively stable propulsion speed and self-propulsion performance are guaranteed;
the temporary control area can be commonly used for a plurality of offshore nuclear power platforms, and has wide adaptability;
meanwhile, the lifting device can be constantly arranged on the upper part of the deck of the platform and can be used for lifting other material equipment of the platform.
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiment, it is to be understood that the invention is not to be limited to the disclosed embodiment, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
Claims (5)
1. A lifting method for equipment in a nuclear reactor control area is characterized by comprising the following steps:
s1, constructing a control area equipment lifting device for lifting equipment in a nuclear reactor control area (3) on a deck (4) of the offshore nuclear power platform above the nuclear reactor control area (3) in a detachable steel plate fixing mode, wherein the control area equipment lifting device comprises a temporary control area (1) and a lifting device (2);
the temporary control area (1) is built on a deck (4) above the nuclear reactor control area (3) in a detachable steel plate fixing mode, covers a first equipment door (40) above the nuclear reactor control area (3) and is provided with a closed space, and a second equipment door (10) is arranged on the side wall of the temporary control area (1);
the lifting device (2) is arranged in the temporary control area (1) and used for lifting equipment between the temporary control area (1) and the nuclear reactor control area (3);
the lifting device (2) is arranged on a deck in the temporary control area (1), is connected with the deck through a rail (20) and is limited, and the rail (20) is fixed on the deck through foundation bolts; or the track (20) of the lifting device (2) is arranged on the body structure of the temporary control area (1);
s2, opening a second equipment cabin door (10) of the temporary control area (1), transporting required equipment into the temporary control area (1) for temporary storage, and closing the second equipment cabin door (10) of the temporary control area (1) after transportation is finished;
step S3, opening a first equipment cabin door (40) above the nuclear reactor control area (3), enabling a lifting device (2) located in the temporary control area (1) to lift the equipment between the nuclear reactor control area (3) and the temporary control area (1), and closing the first equipment cabin door (40) above the nuclear reactor control area (3) after the lifting operation of the equipment is completed;
step S4, opening a second equipment cabin door (10) of the temporary control area (1), and transporting the equipment which needs to be transported to the outside out of the temporary control area (1);
and step S5, after all the lifting work is finished, removing the temporary control area (1).
2. The handling method of nuclear reactor control area equipment of claim 1, wherein the detachable steel plate is fixed by welding or bolting.
3. A handling method for nuclear reactor control area equipment according to claim 2, characterized in that the temporary control area (1) is square in shape.
4. A method for handling nuclear reactor control area equipment according to claim 2, wherein the first equipment bay door (40) is a pneumatic or electric gate.
5. A handling method for nuclear reactor control area equipment according to any one of claims 1 to 4, characterized in that the handling device (2) is one of a gantry crane, a travelling crane and a cantilever crane.
Priority Applications (1)
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CN201810219676.8A CN108529443B (en) | 2018-03-16 | 2018-03-16 | Lifting method for equipment in nuclear reactor control area |
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CN201810219676.8A CN108529443B (en) | 2018-03-16 | 2018-03-16 | Lifting method for equipment in nuclear reactor control area |
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CN108529443A CN108529443A (en) | 2018-09-14 |
CN108529443B true CN108529443B (en) | 2022-04-29 |
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CN110010257B (en) * | 2019-04-09 | 2022-03-25 | 中国核动力研究设计院 | Device and method for assembling and disassembling strong radioactive core components of reactor of floating nuclear power station |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2092099A (en) * | 1980-12-05 | 1982-08-11 | Setri | A hoisting apparatus for use in a confined space and including a cantilevered telescopic boom |
CN103569878A (en) * | 2013-09-10 | 2014-02-12 | 胡江 | Gantry deck crane |
CN103771048A (en) * | 2014-01-27 | 2014-05-07 | 广东明阳风电产业集团有限公司 | Platform maintenance container with auxiliary hoisting equipment and sealing cabin opening |
CN105059489A (en) * | 2015-07-15 | 2015-11-18 | 中国海洋石油总公司 | Constantly stable offshore nuclear power platform |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP4871968B2 (en) * | 2009-02-17 | 2012-02-08 | 日立Geニュークリア・エナジー株式会社 | Heavy structure installation method |
US20110011320A1 (en) * | 2009-07-15 | 2011-01-20 | My Technologies, L.L.C. | Riser technology |
CN102602818A (en) * | 2012-03-16 | 2012-07-25 | 江苏海泰船舶成套设备有限公司 | Shaft linkage coordinable deck loading crane for large geotextiles-laying vessel |
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2018
- 2018-03-16 CN CN201810219676.8A patent/CN108529443B/en active Active
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2092099A (en) * | 1980-12-05 | 1982-08-11 | Setri | A hoisting apparatus for use in a confined space and including a cantilevered telescopic boom |
CN103569878A (en) * | 2013-09-10 | 2014-02-12 | 胡江 | Gantry deck crane |
CN103771048A (en) * | 2014-01-27 | 2014-05-07 | 广东明阳风电产业集团有限公司 | Platform maintenance container with auxiliary hoisting equipment and sealing cabin opening |
CN105059489A (en) * | 2015-07-15 | 2015-11-18 | 中国海洋石油总公司 | Constantly stable offshore nuclear power platform |
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