CN115831415A - Control area arrangement structure of offshore nuclear power platform and offshore nuclear power platform - Google Patents
Control area arrangement structure of offshore nuclear power platform and offshore nuclear power platform Download PDFInfo
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- CN115831415A CN115831415A CN202211620033.7A CN202211620033A CN115831415A CN 115831415 A CN115831415 A CN 115831415A CN 202211620033 A CN202211620033 A CN 202211620033A CN 115831415 A CN115831415 A CN 115831415A
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Abstract
The invention relates to the field of design of an arrangement structure of an offshore nuclear power platform, in particular to a control area arrangement structure of the offshore nuclear power platform and the offshore nuclear power platform. The control area arrangement structure can be used for an offshore nuclear power platform, and the offshore nuclear power platform comprises a cabin, a reactor cabin arranged in the cabin and an auxiliary cabin arranged above the reactor cabin; the control area arrangement structure comprises a wall body and a top which are detachably arranged on the cabin and are positioned above the auxiliary cabin, and the wall body and the top are mutually connected and form a closed temporary control area with a deck of the cabin. According to the invention, by installing the detachable control area arrangement structure on the cabin of the offshore nuclear power platform, a long-term refueling area is prevented from being built on the cabin, the height, the gravity center of a hull, the wind resistance of the platform and the like are reduced, and the stability and the universality of the platform are improved.
Description
Technical Field
The invention relates to the field of design of an arrangement structure of an offshore nuclear power platform, in particular to a control area arrangement structure of the offshore nuclear power platform and the offshore nuclear power platform.
Background
The existing offshore nuclear power platform is generally provided with a special refueling area for refueling operation, and a special new fuel storage and maintenance device and a special radioactive and non-radioactive maintenance area are arranged in the refueling area, so that the occupied area is greatly increased; secondly, the reloading equipment is arranged in a centralized manner, so that the risk of mutual interference of the lifting lines of the equipment exists; in addition, a special equipment transportation channel using a scooter and a horizontal supporting mechanism is arranged between the material changing equipment storage area and the reactor, so that more equipment is needed, and the operation is complex. The lifting routes of the equipment are close, and human errors are easy to occur.
Moreover, the in-pile component shielding storage box is arranged in the fuel loading and unloading cabin, so that the occupied space is large. The radioactivity of the internals is strong, which is not easy for the access of the staff. The in-pile components need to be shielded in a relatively thick and heavy manner, the fuel loading and unloading cabin is relatively high in position, and the stability of the ship body is negatively affected. The equipment such as a spent fuel crane is not arranged in the fuel loading and unloading cabin, occupies the cabin space of the auxiliary cabin and is not beneficial to equipment maintenance and operation.
Disclosure of Invention
The invention aims to solve the technical problem of arrangement of offshore platform refueling equipment, and provides a control area arrangement structure of an offshore nuclear power platform and the offshore nuclear power platform.
According to the technical scheme adopted by the invention for solving the technical problem, a control area arrangement structure is constructed and can be used for an offshore nuclear power platform, wherein the offshore nuclear power platform comprises a cabin, a reactor cabin arranged in the cabin and an auxiliary cabin arranged above the reactor cabin, and the control area arrangement structure comprises a wall body and a top which are detachably arranged on the cabin and are positioned above the auxiliary cabin; the walls and roof are interconnected and form a closed temporary control area with the deck of the hold.
Preferably, the auxiliary cabin comprises a detachable equipment cabin door and a receiving device positioned below the equipment cabin door;
the control area arrangement structure further comprises a container crane track located within the control area above the auxiliary bay;
a container crane slidably mounted on said container crane track for lifting new fuel assemblies to said receiving means or spent fuel assembly transport containers from said receiving means; and the hoisting operation of the pile top assembly, the refueling water jacket, the rotary shield, the upper pile inner member hoisting tool and the lower pile inner member hoisting tool is required to be undertaken.
The depleted pool crane rail is positioned in the control area and above the auxiliary cabin;
a spent pool crane slidably mounted on the spent pool crane track for hoisting fresh fuel assemblies within a spent fuel pool to the receiving means or fresh fuel storage grid and for hoisting spent fuel assemblies from the reactor bay to a spent fuel storage grid or the spent fuel assembly transport container.
Preferably, the container crane rail and the depleted pool crane rail are respectively located at the main structure of the auxiliary cabin.
Preferably, the control area comprises a fuel access passage area arranged in the hoisting range of the container crane and refueling equipment storage areas positioned on two sides of the fuel access passage area.
Preferably, the fuel access passage area comprises a transfer sub-area, a new fuel assembly storage sub-area and a new fuel assembly unpacking sub-area which are positioned between the container crane rails; the container crane reciprocates in the transfer sub-area, the new fuel assembly storage sub-area and the new fuel assembly unpacking sub-area to hoist the new fuel assembly and the spent fuel assembly transportation container;
the transfer sub-area is provided with a transfer trolley used for receiving a new fuel assembly box or sending out a spent fuel assembly transport container;
the new fuel assembly storage sub-area is used for lifting the container crane and temporarily placing a new fuel assembly box;
the new fuel assembly unpacking sub-area is arranged close to the receiving device and used for enabling the container crane to hoist the new fuel assembly box from the new fuel assembly storing sub-area to the new fuel assembly unpacking sub-area for storing and unpacking.
Preferably, the auxiliary chamber further comprises a cleaning pool separately and oppositely arranged with respect to the receiving device;
the refueling equipment storage area comprises a refueling water jacket subregion, an upper in-pile member lifting appliance subregion and a refueling container subregion which are sequentially arranged on one side of the fuel inlet and outlet passage region; the lower reactor internals hanger subregion, the rotary shielding subregion and the reactor top assembly subregion are arranged on the other side of the fuel inlet and outlet passage region in sequence;
the material changing water jacket subregion is used for placing a material changing water jacket;
the upper reactor internals spreader sub-region is used for placing an upper reactor internals spreader;
the sub-area of the material changing container is arranged close to the cleaning pool and used for placing the material changing container;
the lower reactor internals spreader sub-region is used for placing a lower reactor internals spreader;
the rotary shielding sub-region is used for arranging rotary shielding placement and rotary shielding equipment;
the stacking assembly sub-area is used for storing the stacking assembly.
Preferably, the control area further comprises an equipment door sub-area, and the equipment door sub-area is provided with a double-layer door; the double-layer door comprises a first air gate for opening and closing the control area and a second air gate arranged opposite to the first air gate; and a transition area is arranged between the first air lock door and the second air lock door.
The invention also provides an offshore nuclear power platform, which comprises a cabin and a deck for sealing the cabin; the cabin comprises a reactor cabin and an auxiliary cabin arranged above the reactor cabin; the offshore nuclear power platform further comprises any one of the control area arrangement structures.
Preferably, the auxiliary cabin comprises a main structure, an equipment cabin door detachably mounted on the main structure, a receiving device positioned below the equipment cabin door, a cleaning pool separately and oppositely arranged with the receiving device, and a cleaning pool cover plate detachably covering the cleaning pool.
Preferably, the container crane rail of the control area arrangement structure is arranged in parallel with the length direction of the cabin;
and the depleted tank crane rail of the control area arrangement structure is vertical to the length direction of the cabin.
Preferably, the fuel access passage area and the refueling equipment storage area of the control area arrangement structure are arranged in parallel with the length direction of the cabin.
The control area arrangement structure of the offshore nuclear power platform and the offshore nuclear power platform have the following beneficial effects that: the detachable control area arrangement structure is arranged on the cabin of the offshore nuclear power platform, so that a long-term refueling area is prevented from being built on the cabin, the height, the gravity center of a ship body, the wind resistance of the platform and the like are reduced, and the stability and the universality of the platform are improved.
Furthermore, through the reasonable arrangement of each sub-area in the control area, the material changing efficiency is improved, the equipment material changing path is shortened, the mutual interference of the equipment lifting path is avoided, the material changing time is saved, and the safety and the economical efficiency of the ship platform are improved.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic diagram of a control area arrangement structure of an offshore nuclear power platform provided by an embodiment of the invention;
FIG. 2 is a schematic illustration of a new fuel assembly transportation path provided by an embodiment of the present invention;
FIG. 3 is a schematic view of a spent fuel assembly transportation path provided by an embodiment of the invention;
FIG. 4 is a schematic illustration of a transfer path for an upper internals provided by an embodiment of the present invention;
FIG. 5 is a schematic view of a transfer path of a lower internals provided by an embodiment of the present 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. It is to be understood that the drawings are provided solely for the purposes of reference and illustration and are not intended as a definition of the limits of the invention. The connections shown in the drawings are for clarity of description only and are not limiting as to the manner of connection.
It should be understood that the terms "first", "second", "third", "fourth", etc. are used for convenience in describing the technical solutions of the present invention, and do not indicate that the referred devices or elements must have a specific sequence, and thus, the present invention should not be construed as being limited. It will be understood that when an element is referred to as being "coupled" to another element, it can be directly coupled to the other element or intervening elements may also be present. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs. The terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention.
FIG. 1 illustrates a control area arrangement in some embodiments of the invention, which may be used on an offshore nuclear power platform. The offshore nuclear power platform comprises a cabin, a reactor cabin and an auxiliary cabin, wherein the reactor cabin is arranged in the cabin, the auxiliary cabin is arranged above the reactor cabin, and the auxiliary cabin comprises a detachable equipment cabin door 18, a receiving device positioned below the equipment cabin door and a cleaning pool 3 which is separated from the receiving device and is arranged oppositely.
In an embodiment of the invention, the control area arrangement 1 comprises walls and a roof detachably mounted on the cabin above the auxiliary tank, the control area arrangement 1 being used for fuel component replacement in the reactor cabin and in-core component replacement in the reactor cabin. The walls and roof are interconnected and form a closed temporary control area with the deck of the hold.
Preferably, the wall body and the top can be formed by surrounding and fixing detachable steel plates, the fixing mode can be welding or bolt connection, and certain airtight requirements can be met when bolt connection is adopted. In one embodiment the control zone arrangement 1 is rectangular in shape and enclosed within. It will be appreciated that in other embodiments the control zone arrangement 1 may be shaped otherwise.
In an embodiment of the invention, the control zone arrangement 1 further comprises a container crane track, a container crane 19, a depleted pool crane track and a depleted pool crane. The container crane rails are arranged at the tops of two sides of the control area arrangement structure 1 and above the auxiliary cabin; a container crane 19 is slidably mounted on the container crane rail for lifting new fuel assemblies to and from the receiving means for lifting spent fuel assembly transport containers; the container crane 19 is also used to hoist the upper internals spreader 12 from the upper internals spreader sub-region, the lower internals spreader 14 from the lower internals spreader sub-region, the refueling jacket 11 from the refueling jacket sub-region, the rotating shielding device 15 from the rotating shielding sub-region, the topping assembly 17 from the topping assembly sub-region, and the upper internals spreader 12, the lower internals spreader 14, the refueling jacket 11, the rotating shielding device 15, the topping assembly 17 back to the above-described regions.
The spent pool crane track is arranged in the control area and above the auxiliary cabin; the spent pool crane is slidably mounted on a spent pool crane rail for hoisting new fuel assemblies to a receiving device or a new fuel storage grid within the spent fuel pool 2 and for hoisting spent fuel assemblies from the reactor bay to the spent fuel storage grid or a spent fuel assembly transport container. The container crane track and the depleted pool crane track are respectively positioned at the main structure of the auxiliary cabin. It will be appreciated that the container crane and the spent pool crane may be a gantry crane, a travelling crane or a cantilever crane.
In this embodiment, the container crane track and the depleted pool crane track are arranged at the main structure of the auxiliary cabin, so that the range of motion of the container crane 19 and the depleted pool crane is maximized, and the hoisting process is ensured not to be hindered by foreign objects.
In an embodiment of the invention, the control zone arrangement 1 comprises a fuel access passage area 4 and a refueling equipment storage area. The fuel access passage area 4 is provided in the lifting range of the container crane 19, and serves as a space for new fuel to enter the control area, unpacking and inspection of new fuel assemblies, and discharging spent fuel assemblies. The refueling equipment storage areas are positioned on two sides of the fuel inlet and outlet channel area 4 and used for storing the refueling equipment.
The fuel access passage area 4 further comprises a transfer sub-area, a new fuel assembly storage sub-area and a new fuel assembly unpacking sub-area, which are located between the container crane rails and are used as spaces for the container crane 19 to reciprocate to hoist new fuel assemblies or to send spent fuel assemblies out.
The transfer sub-area comprises a transfer trolley for receiving a new fuel assembly box or sending out a spent fuel assembly transport container; a new fuel assembly storage sub-area for the container crane 19 to hoist and temporarily store new fuel assembly containers; a new fuel assembly unpacking sub-area, disposed adjacent the receiving means, for the container crane 19 to hoist new fuel assembly boxes from the new fuel assembly storage sub-area to the new fuel assembly unpacking sub-area for storage and unpacking.
The refueling equipment storage area also comprises a refueling water jacket subregion, an upper in-pile member lifting appliance subregion and a refueling container subregion which are sequentially arranged on one side of the fuel inlet and outlet passage region 4; and the lower reactor internals hanger sub-region, the rotary shielding sub-region and the reactor roof assembly sub-region are sequentially arranged on the other side of the fuel inlet and outlet channel region 4.
The material changing water jacket subregion is used for placing the material changing water jacket 11, the material changing water jacket 11 is used for filling water and shielding radiation; the upper internals spreader sub-area is used for placing an upper internals spreader 12 that grabs the upper internals; the sub-area of the refueling container is arranged close to the position of the cleaning pool 3 and is used for placing a refueling container 13 for loading fuel assemblies; the lower internals spreader sub-area is used for placing a lower internals spreader 14 that grabs the lower internals; the rotary shielding subarea is used for arranging a rotary shielding placing and rotary shielding device 15, and the rotary shielding device 15 is used for calibrating the position of the refueling container 13 and the fuel assembly; the stacker assembly sub-area is used to deposit the stacker assembly 17.
In an embodiment of the invention, the auxiliary bay further comprises an equipment refueling channel 16, arranged on the same vertical axis as the reactor bay, for facilitating the replacement of fuel assemblies and in-stack assemblies, for connecting the control area arrangement 1 with the reactor bay. The top of the equipment refueling passage 16 is provided with an equipment hatch 18 closing the passage.
A material changing water jacket sub-region, an upper in-pile member lifting appliance sub-region, a material changing container sub-region and an equipment cabin door 18 are sequentially arranged on one side of the equipment material changing channel 16; specifically, the refueling water jacket sub-zone, the upper internals spreader sub-zone, the refueling container sub-zone, and the equipment bay door 18 are sequentially disposed on the starboard side of the control zone.
Specifically, the other side of the equipment refueling channel 16 opposite to the equipment refueling channel is sequentially provided with a lower in-pile member hanger sub-region, a rotary shielding sub-region and a pile top assembly sub-region; specifically, the lower internals spreader sub-region, the slewing shield sub-region and the heap top assembly sub-region are arranged in sequence on the port side of the control region.
Wherein the lower internals spreader subregion of the port side, the slewing shield subregion, the refueling water jacket subregion, and the upper internals spreader subregion of the starboard side, the refueling container subregion are arranged close to the equipment refueling passage 16 on the horizontal axis; the starboard side equipment bay door 18 and the port side sub-area of the heap assembly are disposed away from the equipment refueling passage 16 on a horizontal axis.
In an embodiment of the invention, the control zone arrangement 1 further comprises an equipment door sub-zone 5, the equipment door sub-zone 5 being provided close to the fuel access area 4 side. The equipment compartment door sub-region 5 is provided with a double-layer door and a transition region, and comprises a first air gate and a second air gate; the first air gate is used for opening and closing the control area; the second air gate is communicated with the outside and is arranged opposite to the first air gate; the transition area is arranged between the first air gate and the second air gate and used for isolating the temporary control area and the non-temporary control area when personnel and equipment enter and exit to prevent radiation leakage. It will be appreciated that the first and second airlock doors may be pneumatic or electric.
Specifically, during refueling, the hatch cover at the top of the reactor cabin is opened, the reactor cabin is communicated with the control area, and the cabin communicated with the reactor cabin also belongs to the radioactive area because the reactor cabin belongs to the radioactive area. The control area thus belongs to a radioactive control area, which is provided with a door sub-area in order to avoid the risk of radioactive leakage due to the fact that personnel equipment enters and exits the radioactive control area and communicates with the outside atmosphere.
Referring to FIG. 2, a schematic illustration of a new fuel assembly transportation path is provided for an embodiment of the present invention.
As shown by the arrows in fig. 2, in the present embodiment, the process of using the control zone arrangement 1 to complete the loading of new fuel assemblies is as follows:
first, a new fuel assembly is loaded into a new fuel container, which is placed on the flat bed transport vehicle. And opening the second air gate, enabling the flat transport vehicle to enter the transition area of the sub-area of the equipment compartment, closing the second air gate, opening the first air gate, and enabling the flat transport vehicle to enter the fuel inlet and outlet passage area 4 of the temporary control area. The container crane 19 removes the new fuel container from the flat bed transport vehicle and hoists to the new fuel assembly storage sub-area.
The container crane 19 then grabs a new fuel container from the new fuel assembly storage sub-area and hoists the new fuel container to the new fuel assembly unpacking sub-area, the container crane 19 uses tools to open the new fuel container and uses special tools to remove the new fuel assembly in the new fuel container, and the container crane 19 hoists the new fuel assembly to the receiving device location.
After the receiving device receives the new fuel assembly, the fuel cabin in the receiving device descends the new fuel assembly to the interior of the spent pool, and the spent pool crane grabs the new fuel assembly from the fuel cabin of the receiving device and hoists the new fuel assembly to the new fuel grillwork. At this point, the incoming load of the new fuel assembly is complete.
Referring to fig. 3, a schematic diagram of a transportation path of the spent fuel assembly according to an embodiment of the present invention is provided.
As shown by the arrows in fig. 3, in the present embodiment, the process of using the control zone arrangement 1 to complete the transportation of spent fuel assemblies is as follows:
firstly, a spent fuel assembly in the reactor is grabbed by a spent pool crane and hoisted into a special spent fuel assembly transport container by the container crane 19, the spent fuel assembly transport container is grabbed by the container crane 19, the whole spent fuel assembly transport container is hoisted out, and the spent fuel assembly transport container is hoisted to a cleaning pool 3 beside a spent fuel pool 2 to clean the outer surface of the spent fuel assembly transport container. The container crane 19 then grabs the spent fuel assembly transport container out of the wash tank 3 and lifts it onto the transfer trolley in the transfer sub-area. The transfer trolley approaches the door of the first air gate of the equipment door sub-region 5, the first air gate is opened, and the transfer trolley enters the transition region through the first air gate. And closing the first air gate to complete air exchange of the transition area, opening the second air gate, closing the second air gate by the transfer trolley, and thus successfully transporting the spent fuel assembly transport container out of the plant by the transfer trolley.
Referring to fig. 4 and 5, schematic diagrams of upper and lower internals transportation paths according to an embodiment of the present invention are shown.
As shown by the arrows in fig. 4, in the present embodiment, the transfer process of the upper internals at the time of refueling is as follows:
firstly, the container crane 19 lifts the equipment hatch 18 covered on the top of the equipment refueling passage 16 to the equipment hatch subarea to open the equipment refueling passage 16; then, the refueling water jacket 11 is hung from the region of the refueling water jacket, enters the reactor cabin through the equipment refueling passage 16, and the refueling water jacket 11 is sleeved on a pressure vessel of the reactor cabin and is injected with water to shield.
The reactor roof assembly 17 is then hoisted from the reactor bay to the sub-area of the roof assembly through the equipment refueling passage 16; the upper internals spreader 12 is hoisted from the upper internals spreader sub-area and hoisted from the reactor bay into the wash tank 3 using the upper internals spreader 12, the upper internals are placed on the upper internals support racks in the wash tank 3 completing the internal gripper tripping, the container crane 19 hoists the empty upper internals spreader 12 back to the upper internals sub-area.
After spent fuel assemblies are unloaded from the reactor bay and new fuel assemblies are installed into the pressure vessel of the reactor bay, the vessel crane 19 retrieves the rotating shielding device 15 from the rotating shielding sub-area and places the rotating shielding device 15 on the pressure vessel through the device refueling passage 16. Water in the refueling water jacket 11 is drained, the container crane 19 is used for dismantling the refueling water jacket 11 and lifting the water jacket from the reactor cabin to a refueling water jacket sub-region of a control region; the refueling container 13 is hoisted from the refueling container subregion and through the equipment refueling passage 16 to the reactor compartment for loading of fuel assemblies, and the position of the refueling container 13 and the fuel assemblies is calibrated using the rotary shielding equipment 15. After loading a new fuel assembly, the container crane 19 unloads the rotary shielding device 15 and lifts the rotary shielding device 15 to the rotary shielding sub-area; the upper internals spreader 12 is hoisted from the upper internals spreader sub-area using the vessel crane 19 and the upper internals spreader 12 is hoisted from the wash tank 3 back into the pressure vessel of the reactor bay, followed by the hoisting of the roof assembly 17 from the roof assembly sub-area of the control area back onto the pressure vessel.
The lower internals are not generally lifted out, and only after the spent fuel assemblies are completely unloaded from the reactor and the lower internals need to be serviced, as indicated by the arrows in fig. 5, the process is as follows:
the container crane 19 lifts the refueling water jacket 11 from the region of the refueling water jacket, and the refueling water jacket enters the reactor cabin through the equipment refueling passage 16, and the refueling water jacket 11 is sleeved on the pressure container of the reactor cabin and is injected with water for shielding. The lower internals spreader 14 is hoisted from the lower internals spreader sub-area and the lower internals are hoisted from the reactor bay using the lower internals spreader 14 onto a support frame common to the lower internals and spent fuel transport vessel. Upon completion of the internal gripper tripping, the container crane 19 swings the empty lower in-stack component spreader 14 back to the lower in-stack component spreader sub-area.
After the lower reactor internals are overhauled, the lower reactor internals are hoisted back before the new fuel assemblies are not installed in the reaction cabin. The vessel crane 19 lifts the lower internals spreader 14 from the lower internals spreader sub-area and uses the lower internals spreader 14 to hoist the lower internals from the support frame back onto the pressure vessels of the reactor bay and then to hoist the empty lower internals spreader 14 back into the lower internals spreader sub-area of the control area.
In combination with the above-mentioned material changing process, the material changing equipment is dispersedly arranged on the two sides of the equipment material changing channel 16 according to the use sequence and the use frequency of the equipment, so that the total path length of equipment hoisting is shortened, and the interference problem of the equipment hoisting route is avoided. In addition, the material changing equipment is distributed at the position close to the main structure support, so that the structural design pressure is reduced.
In this embodiment, the spent fuel pool 2 is provided with a spent fuel lattice for storing spent fuel, a new fuel lattice for storing new fuel, a receiving device for delivering fuel, a sipping device for detecting fuel, and a lower internals support for storing lower internals.
In this embodiment, the spent fuel pool 2 and the cleaning pool 3 are not in the control area arrangement structure 1, and in the refueling process, the upper reactor internals and the lower reactor internals with higher radioactivity are temporarily stored in the cleaning pool 3 and the spent fuel pool 2 respectively, so that the radioactivity dose in the control area arrangement structure 1 is greatly reduced, the accessibility of the personnel in the control area arrangement structure 1 is enhanced, and the operation safety of the personnel in the temporary control area is improved.
In addition, in another embodiment of the invention, an offshore nuclear power platform comprises a cabin, a deck covering the cabin, a control area arrangement structure 1, and particularly, the cabin further comprises a reactor cabin and an auxiliary cabin arranged above the reactor cabin. It will be appreciated that an offshore nuclear power platform includes any one of the structures of the control area arrangement 1.
In an embodiment of the present invention, the auxiliary compartment includes a main structure, an equipment hatch detachably mounted on the main structure, a receiving device located below the equipment hatch, a cleaning tank 3 separately disposed opposite to the receiving device, and a cleaning tank cover detachably covering the cleaning tank.
Further, a container crane track of the control area arrangement structure 1 of the offshore nuclear power platform is arranged in parallel with the length direction of the cabin; the spent pool crane track of the control area arrangement structure 1 is vertical to the length direction of the cabin; the fuel inlet and outlet passage area 4 and the refueling equipment storage area of the control area arrangement structure are arranged in parallel with the length direction of the cabin.
Compared with the existing offshore nuclear power platform structure and offshore platform, the control area arrangement structure 1 and offshore platform in the embodiment at least have the following beneficial effects:
(1) By dispersedly arranging the refueling equipment on two sides of the equipment refueling channel 16 according to the use sequence and the use frequency of the equipment, the total path length of equipment hoisting is shortened, and the problem of interference of equipment hoisting routes is avoided.
(2) The reloading equipment is all distributed near the main structure support, so that the structural design pressure is reduced. By providing the crane rails at the main structure of the control area arrangement 1, the range of motion of the crane is maximized.
(3) The upper reactor internals and the lower reactor internals with higher radioactivity in the refueling process are respectively temporarily stored in the cleaning pool 3 and the spent fuel pool 2 outside the control area arrangement structure 1, so that the radioactivity dose in the control area arrangement structure 1 is greatly reduced, and the accessibility and the operation safety of personnel in a control area are enhanced.
(4) The top of the equipment refueling passage 16 without being opened is used as an unpacking and checking space for new fuel assemblies, and a special new fuel assembly storage and checking interval is not required to be set, so that the space is recycled, and the arrangement space is favorably reduced. By analyzing the minimum hoisting height, the total height of the control area is compressed, the total height of the control area is reduced, the wind resistance of the control area is reduced, and the economy of the offshore platform is improved.
(5) The equipment cabin door sub-area 5 is arranged in the control area, and fuel enters and exits the control area through the double gates of the equipment cabin door sub-area 5, so that the air tightness of the boundary of the temporary control area is ensured, the radioactivity is prevented from leaking to a non-control area, and the safety of the offshore platform is improved.
It is to be understood that the foregoing examples, while indicating the preferred embodiments of the invention, are given by way of illustration and description, and are not to be construed as limiting the scope of the invention; it should be noted that, for those skilled in the art, the above technical features can be freely combined, and several changes and modifications can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention; therefore, all equivalent changes and modifications made within the scope of the claims of the present invention should be covered by the claims of the present invention.
Claims (11)
1. A control area arrangement structure of an offshore nuclear power platform can be used for the offshore nuclear power platform, the offshore nuclear power platform comprises a cabin, a reactor cabin arranged in the cabin and an auxiliary cabin arranged above the reactor cabin, and the control area arrangement structure is characterized by comprising a wall body and a top which are detachably arranged on the cabin and are positioned above the auxiliary cabin; the walls and the roof are interconnected and form a closed temporary control area with the deck of the hold.
2. The control zone arrangement of claim 1, wherein the auxiliary compartment comprises a removable equipment compartment door, a receiving device located below the equipment compartment door;
the control area arrangement structure further comprises a container crane track located within the control area and above the auxiliary compartment;
a container crane slidably mounted on the container crane track for lifting new fuel assemblies to the receiving means or spent fuel assembly transport containers from the receiving means;
the depleted pool crane rail is positioned in the control area and above the auxiliary cabin;
a spent pool crane slidably mounted on the spent pool crane track for hoisting fresh fuel assemblies within a spent fuel pool to the receiving means or fresh fuel storage grid and for hoisting spent fuel assemblies from the reactor bay to a spent fuel storage grid or the spent fuel assembly transport container.
3. The control area arrangement as claimed in claim 2, wherein the container crane track and the depleted pool crane track are located at the main structure of the auxiliary cabin, respectively.
4. The control area arrangement as claimed in claim 2, wherein the control area comprises a fuel access passage area provided within the reach of the vessel crane, and refueling equipment storage areas located on both sides of the fuel access passage area.
5. The control zone arrangement of claim 4, wherein the fuel access passage area comprises a transfer sub-area, a new fuel assembly storage sub-area, a new fuel assembly unpacking sub-area between the container crane rails; the container crane reciprocates in the transfer sub-area, the new fuel assembly storage sub-area and the new fuel assembly unpacking sub-area to hoist the new fuel assemblies and the spent fuel assembly transport container;
the transfer sub-area is provided with a transfer trolley which is used for receiving the new fuel assembly or sending out the spent fuel assembly transportation container;
the new fuel assembly storage sub-area is used for the container crane to hoist and temporarily place a new fuel assembly box;
the new fuel assembly unpacking sub-area is disposed proximate to the receiving device for the container crane to hoist and unpack the new fuel assembly pod from the new fuel assembly storage sub-area to the new fuel assembly unpacking sub-area.
6. The control area arrangement of claim 5, wherein the auxiliary compartment further comprises a wash tank disposed separately opposite the receiving means;
the refueling equipment storage area comprises a refueling water jacket subregion, an upper in-pile member lifting appliance subregion and a refueling container subregion which are sequentially arranged on one side of the fuel inlet and outlet passage region; the lower reactor internals hanger sub-region, the rotary shielding sub-region and the reactor roof assembly sub-region are sequentially arranged on the other side of the fuel inlet and outlet channel region;
the material changing water jacket subregion is used for placing a material changing water jacket;
the upper reactor internals spreader sub-region is used for placing an upper reactor internals spreader;
the sub-area of the material changing container is arranged close to the cleaning pool and used for placing the material changing container;
the lower reactor internals spreader sub-region is used for placing a lower reactor internals spreader;
the rotary shielding sub-region is used for arranging rotary shielding placement and rotary shielding equipment;
the heap top assembly sub-area is used for storing heap top assemblies.
7. Control zone arrangement according to any of claims 1-6, wherein the control zone further comprises an equipment door sub-zone provided with a double door; the double-layer door comprises a first air gate for opening and closing the control area and a second air gate which is arranged opposite to the first air gate by 5; and a transition area is arranged between the first air lock door and the second air lock door.
8. An offshore nuclear power platform comprises a cabin and a deck for covering the cabin; the cabin comprises a reactor cabin and an auxiliary cabin arranged above the reactor cabin; characterized in that the offshore nuclear power platform further comprises a control area arrangement according to any one of claims 1 to 7.
9. The offshore nuclear power platform of claim 8, wherein the auxiliary tank includes a primary structure 0, an equipment bay door detachably mounted on the primary structure, a receiving device located below the equipment bay door, a purge tank disposed separately opposite the receiving device, and a purge tank cover plate detachably covering the purge tank.
10. An offshore nuclear power platform according to claim 8, wherein the container crane rails of the control area arrangement are arranged parallel to the length direction of the hold;
5 the depleted tank crane track of the control area arrangement structure is perpendicular to the length direction of the cabin.
11. The offshore nuclear power platform of claim 8, wherein the fuel access passage area and the refueling equipment storage area of the control area arrangement are arranged parallel to the length direction of the hold.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211620033.7A CN115831415A (en) | 2022-12-15 | 2022-12-15 | Control area arrangement structure of offshore nuclear power platform and offshore nuclear power platform |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211620033.7A CN115831415A (en) | 2022-12-15 | 2022-12-15 | Control area arrangement structure of offshore nuclear power platform and offshore nuclear power platform |
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| CN115831415A true CN115831415A (en) | 2023-03-21 |
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| CN202211620033.7A Pending CN115831415A (en) | 2022-12-15 | 2022-12-15 | Control area arrangement structure of offshore nuclear power platform and offshore nuclear power platform |
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| CN (1) | CN115831415A (en) |
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