JP3817211B2 - Radioactive material storage method and radioactive material storage facility - Google Patents

Description

[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a storage facility and a storage method for storing a heat-generating radioactive material such as spent fuel generated from a nuclear power plant. In particular, the present invention relates to a storage facility and a storage method using a dry storage technique for storing a radioactive material in a concrete storage chamber, wherein the radioactive material is cooled by air flowing horizontally in the storage chamber (horizontal flow).
[0002]
[Prior art]
Spent fuel generated from nuclear power plants must be stored for a long time in a safe and removable manner until reprocessing. The spent fuel is stored using a water pool, a sturdy container called a cask, a concrete storage container, or a concrete storage room. Of these, dry storage methods using casks, concrete storage containers, concrete storage rooms, etc. are safer than underwater storage using water pools, and it is easy to increase storage capacity as needed. For some reason, this technology can be used outside of nuclear reactor facilities.
[0003]
As a conventional method for dry storage of spent fuel, it is a metal container with a limited shielding ability by transporting spent fuel from a nuclear power plant with a transport cask and refilling spent fuel in the storage facility. After refilling and sealing the canister, this canister is stored in a storage tube installed in advance in a concrete storage chamber, and the upper portion of the storage tube is resealed with a plug having a shielding ability, or from a transport cask, There is a method in which spent fuel is directly stored in a storage pipe installed in a concrete storage chamber in advance by a spent fuel refilling facility, and the upper part of the storage pipe is sealed with a plug (see, for example, JP-A-9-11678) .) A cask is a sturdy metal container with a criticality prevention function, radiation shielding function, cooling function, and sealing function, and is a container commonly used for transporting and storing radioactive materials in nuclear power plants. It is.
[0004]
According to Japanese Patent Laid-Open No. 9-11678, the concrete storage chamber includes a ceiling slab that holds the upper end of the storage pipe and a floor slab that is positioned below the ceiling slab and holds the lower end of the storage pipe. A horizontal air passage is formed between them, and the decay heat from the spent fuel stored in the storage pipe is cooled by the air flowing in the air passage. This cooling air flows from the outdoor part of the building through the air passage through the air inlet, the air inlet duct, and a plurality of vertical air rectifying plates arranged in the vertical direction, and then from the air outlet through the air outlet duct. It is discharged outside the building.
[0005]
Furthermore, in Japanese Patent Laid-Open No. 8-15496, for example, a wire mesh baffle plate is provided at the inlet of the air passage, or an intake side louver wall having a structure in which a plurality of air traveling directions are provided. Thus, means for increasing the heat removal effect of the storage pipe installed in the air passage by increasing the speed and turbulence of the flowing air is disclosed.
[0006]
Further, conventionally, when spent fuel or canister is transferred to and stored in a storage pipe of a concrete storage chamber, a means for attaching and detaching a plug for sealing the upper opening of the storage pipe, and the spent fuel or canister are lifted up in the storage pipe. And a means for transporting them separately. In other words, conventionally, when the plug attaching / detaching means is moved to the upper part of the storage pipe and the plug is removed, the plug attaching / detaching means is withdrawn, and after the spent fuel or canister is transported and stored in the storage pipe by the transport means, the transport means is The upper part of the storage tube was resealed by another plug attaching / detaching means.
[0007]
[Patent Document 1]
Japanese Laid-Open Patent Publication No. 9-113678 (paragraphs [0004], [0038] to [0055], FIG. 1, FIG. 3, etc.)
[Patent Document 2]
Japanese Patent Laid-Open No. 8-15496 (paragraphs [0009], [0010], [0012], [0016], FIG. 1, etc.)
[0008]
[Problems to be solved by the invention]
In the conventional technology described above, in the case of a method of temporarily storing spent fuel from a transportation cask in a canister in a storage facility, or a method of directly storing spent fuel from a transportation cask in a storage pipe, the spent fuel is used. Equipment for directly handling the canister or equipment for sealing the storage tube is required. In addition, in order to handle the spent fuel in an unsealed state, the storage facility is contaminated with radioactive materials, and equipment for confining and removing the radioactive materials released from the surface of the spent fuel is required.
[0009]
In addition, in a conventional concrete storage room using a canister, a canister having a size for storing one or several spent fuels in a fuel assembly is stored in a storage tube. Since it increases, the storage efficiency of spent fuel is poor.
[0010]
However, facilities with high storage efficiency are required for spent fuel, which is increasing year by year. Thus, when considering increasing the size of the canister in order to increase the amount of spent fuel stored, the cooling efficiency of the canister must be increased, and it is necessary to provide a cooling means that is higher than the above-described prior art. Moreover, in the storage method of storing in a small canister or storage tube as described above, the storage building becomes large.
[0011]
Furthermore, as in the prior art, in equipment where the plug attaching / detaching means and the means for transporting the canister to the storage pipe are individually provided, when the large canister is transferred and stored, the equipment becomes large, and the storage building also It will increase in size.
[0012]
Also, in the conventional concrete storage room, the wall of the storage room and the ceiling slab on the upper part of the storage pipe are integrally constructed as the building structure of the building. There was a possibility that the temperature of the upper ceiling slab exceeded the limit temperature required from the structural strength of the concrete part as a building structure.
[0013]
Therefore, in view of the above-mentioned problems of the prior art, the object of the present invention is to improve the safety and cooling efficiency of the canister without increasing the size of the storage building, simplify the equipment, and improve the storage efficiency of spent fuel. The object is to provide a material storage method and a radioactive material storage facility including a concrete storage room.
[0014]
[Means for Solving the Problems]
In order to achieve the above object, the spent fuel storage method of the present invention comprises:A step of transporting the canister containing the radioactive material in a space above the ceiling slab of the canister storage room in the storage facility while shielding it, and a step of removing the shielding plug provided at the canister entrance of the ceiling slab Opening and closing doors that can be opened and closed are opened in the canister doorway with the shield plug removed in a closed state, and the opening and closing doors in the closed state are opened and transported. The canister is stored in the canister storage chamber through the canister inlet / outlet while being shielded, and after the canister is stored in the canister storage chamber, the opening / closing door for the inlet / outlet is closed, and the canister inlet / outlet is opened. Remove the open / close shielding door that is closed again and install the shielding plug. And-up, the canister, and a a step of cooling by the air flowing through the canister storage chamber horizontally.
[0015]
In the above storage method,The step of removing the shielding plug is performed prior to the step of transporting while shielding the canister, and the step of removing the shielding plug is performed by installing an opening / closing shielding door for the entrance / exit in the space above the ceiling slab of the canister storage room. A step of transporting, a step of placing the transported doorway shield door in a closed state on a shielded plug provided in the entrance and exit of the canister of the ceiling slab, and a doorway shield door provided in the closed state. The step of opening and removing the shielding plug while shielding, the step of closing the shielding door for the entrance after the shielding plug is removed, and the shielding plug provided at a position different from the entrance and exit of the canister Including transporting to temporary storageIt is preferable. further,The canister has only the upper and lower ends of the canister,Canister storage room ceilingSlabAnd floorSupportHeldThisStored in a wet stateIsIt is preferable.
[0016]
The radioactive substance storage facility of the present invention stores radioactive substances.RukiCanistaSaveStorehouse, canisterThe insideA canister storage room cooled by air flowing horizontally and, KiCanistaA side wall that divides the storage chamber into a plurality of unit chambers, and a ceiling slab of the canister storage chamber that defines the canister storage chamber together with the side wall, and the ceiling slab includes a plurality of concrete plates provided independently of each other. And each of the concrete plates is supported independently of the building structure by corresponding side walls.Such storage facilities include canister storage rooms.,ceilingA canister transfer chamber provided above the slab, and a canister transfer device that is movable in the canister transfer chamber and that transfers the canister to the canister storage chamber. The ceiling slab has a canister transfer device that canister the canister. Has a canister inlet / outlet for transfer into the storage roomApplicable ones are applicable.
[0017]
Also, KiAs a canister transfer device, KiCanistaOr, the shield plug provided in the floor slab can be selectively taken in from the opening provided in the lower end, and the opening at the lower end can be opened and closed at the lower end of the storage body that stores while shielding the canister The storage opening / closing shielding door for the storage body, and the storage body opening / closing shielding door below the storage body opening / closing shielding door, are detachably attached to the storage body, cover the canister entrance and exit in a detached state, and in either state Can be opened and closedA door having an open / close shielding door for entrance and exit can be applied.
[0018]
further,The concrete plate is entirely surrounded by steel platesIt is preferable.
[0019]
As described above, the storage method of the present invention transports a canister sealed with radioactive material such as spent fuel at a nuclear power plant to a storage facility using a transport cask, and stores the canister as it is. The facility does not require spent fuel refilling equipment or ventilation equipment to contain radioactive materials. Further, since spent fuel is handled in a sealed state in a canister, there is no possibility that the inside of the storage facility is contaminated with radioactive substances. Also, safety evaluation due to accidents during refilling of spent fuel is not required.
[0020]
In addition, since the canister is directly stored in the canister storage chamber without going through the storage tube, the heat generated from the canister is directly transferred to the surrounding air as compared with the conventional technology in which the canister is stored in the storage tube disposed in the canister storage chamber. It is reported that the efficiency of removing decay heat of spent fuel is improved.
[0021]
In addition, the air rectifying mechanism of the present invention combining the cylindrical structure and the rectifying plate further enhances the cooling effect as compared with the conventional technology using only the rectifying plate, so that the spent fuel assembly for enlarging and storing the canister can be used. The number of bodies can be increased, and the storage efficiency of spent fuel is improved.
[0022]
Further, the canister transfer device of the present invention can be used for both the attachment / detachment and transfer of the plug that shields the entrance / exit of the canister storage chamber and the transfer of the canister, so that the equipment is compact and the storage building is not enlarged.
[0023]
In addition, the ceiling of the canister storage room is structurally separated from the building structure of the building, and has a structure using multiple divided concrete plates. The thermal expansion of the concrete plates is carried out by the side walls standing on the floor of the canister storage room. Held to allow. Thereby, the temperature restriction | limiting requested | required from the structural strength as a building structure is not imposed on a concrete part. By such a structural measure of the ceiling portion of the canister storage chamber, the canister can be enlarged and the canister storage chamber can be densified, and the storage density of the spent fuel can be improved.
[0024]
DETAILED DESCRIPTION OF THE INVENTION
Hereinafter, embodiments of the present invention will be described with reference to FIGS.
[0025]
FIG. 1 is a cross-sectional view illustrating a radioactive material dry storage facility according to an embodiment of the present invention. FIG. 2 is another sectional view of the radioactive substance dry storage facility of the present embodiment. FIG. 3 is an enlarged view of the canister transfer device shown in FIG. 4 is a cross-sectional view of the canister storage chamber, showing a cross section in a direction perpendicular to FIG. FIG. 5 is a configuration diagram of the air rectifying mechanism 11 of the air inflow portion shown in FIG.
[0026]
The radioactive material dry storage facility 1 of this embodiment carries a transport cask containing a large canister in which a heat generating radioactive material such as spent fuel is sealed in advance in a nuclear power plant, and the canister taken out from the transport cask It is a facility made of concrete that stores the fuel without changing the spent fuel. In this example, the spent fuel will be described as an example of the exothermic radioactive material. However, what can be stored in the storage facility of the present invention includes a high-level vitrified body, components of the fuel assembly, and the like.
[0027]
This storage facility 1 has a canister transfer chamber 2 and a canister storage chamber 3 inside. The canister transfer chamber 2 is located above the canister storage chamber 3. The canister transfer chamber 2 and the canister storage chamber 3 are separated from each other by a concrete ceiling slab 4. A concrete floor slab 5 constitutes the bottom of the canister storage chamber 3.
[0028]
The canister 6 containing the radioactive substance is disposed in the underground canister storage chamber 3. The ceiling slab 4 of the canister storage chamber 3 is provided with a canister outlet 7 for storing the canister 6. The canister inlet / outlet 7 is shielded by a shielding plug 8. The upper end of the canister 6 is held by the hole side surface of the canister outlet 7 of the ceiling slab 4, and the lower end is held by a canister support base 28 on the floor slab 5. Thereby, even if there is no canister storage tube or other additional support in the storage room, the canister can be prevented from overturning in the event of an earthquake, and it has earthquake resistance.
[0029]
The upper portion of the canister 6 has a shielding ability so that a person can approach when the radioactive material is stored and sealed outside the storage facility, but the side trunk portion and the bottom portion have no shielding ability. The radiation emitted from the canister during storage is shielded by the ceiling slab 4, the shielding plug 7, the side wall 17 and the like.
[0030]
The canister storage chamber 3 is divided into a plurality of unit chambers arranged in one direction by a side wall 17 provided vertically between the ceiling slab 4 and the floor slab 5 (FIG. 4). Each unit chamber of the canister storage chamber 3 has an air rectification mechanism 11 at an air inflow portion and an air rectification mechanism 19 at an air outflow portion. These air rectifying mechanisms also have a function of reducing radiation to the outside of the storage facility 1. Further, a cooling air inflow duct 9 and a cooling air discharge duct 10 are provided for each unit chamber. Each cooling air inflow duct 9 has an air inlet 12 and communicates with the unit room of the canister storage room 3. Each cooling air discharge duct 10 has an air discharge port 13 and communicates with the unit room of the canister storage room 3.
[0031]
In each unit chamber of the canister storage chamber 3 of this example, the canisters 6 can be arranged in three rows by five in one row along the air flow direction. For this reason, 5 × 3 canister access ports 7 of the ceiling slab 4 in each unit room are formed.
[0032]
The number of unit rooms and the number of canisters arranged in each unit room are not limited to this example. Further, in this example, one air inlet 12 and one air outlet 13 are provided for each unit chamber. However, in addition to this, there is a method of combining one inlet or outlet for a plurality of units (for example, 4 A unit with an inlet and an outlet), an inlet or an outlet is attached to each unit, and the opposite side is integrated into one unit (for example, each unit of 4 units has an inlet (exhaust port). A single outlet (inlet) is also possible. That is, the number of inlets and outlets is arbitrary as long as the canister can secure an air flow sufficient for cooling.
[0033]
It is also conceivable to attach a blowing means to both or one of the inflow port and the discharge port to forcibly enter the cooling air into the inflow port or to suck out from the discharge port.
[0034]
The ceiling slab 4 of this example has a structure using a concrete plate containing steel plates, and each steel plate-containing concrete plate is arranged for each unit room of the canister storage chamber 3 and is concrete on the side wall 17 standing on the floor slab 5. It is held to allow thermal expansion of the plate. In addition to the structure of this example, the ceiling slab 4 can be applied to a reinforced concrete structure, a structure in which concrete is enclosed in a steel plate, a combination of these, and the strength and storage required for the ceiling slab. It is appropriately selected in consideration of heat received from the room. Since such a ceiling slab 4 is structurally separated from the building structure of the building, the concrete part is not subjected to temperature restrictions required from the structural strength of the building structure. Further, even if the thermal expansion of the ceiling slab 4 is significant, it does not affect other building structures such as the side wall 17.
[0035]
A steel plate 29 is attached to the side wall 17 between the ceiling slab 4 and the floor slab 5 along the wall surface so as to be slightly separated from the wall surface. Temperature rise can be prevented. Therefore, densification of the canister storage chamber can be realized, and the storage density is improved.
[0036]
The canister transfer device 18 includes a lifting device 21, a storage body 22, and a door opening / closing shielding door 23 (FIG. 3). The storage body 22 has a cavity that can store the canister 6 and the shielding plug 8, and an opening / closing shielding door 24 for the storage body that can freely open and close the cavity is provided at the lower end of the storage body 22. Further, the door opening / closing shielding door 23 can be opened and closed with respect to the opening when the housing opening / closing shielding door 24 is opened and the canister loading / unloading opening 7, and the canister transfer device. It is arranged so that it can be detached from 18. The storage body 22 has an ability to shield radiation from a canister that stores spent fuel. Further, the lifting device 21 has a hand portion 25 that can grasp the upper end portions of the canister 6 and the shielding plug 8 through the hollow portion of the storage body 22.
[0037]
The spent fuel taken out of the nuclear power plant reactor is sealed in a large canister 6 at the nuclear power plant, and the canister 6 is stored in a transport cask. The overhead crane 14 receives the transport cask carried from the trailer on the ground and places it on the cask transport carriage 15. After removing the transport cask lid, the cask transport carriage 15 transports the transport cask to below the canister take-out port 20. The canister transport carriage 15 is provided with a lifting mechanism for the transport cask so that the transport cask can be in close contact with the lower portion of the canister take-out port 20 when the canister transfer device 18 pulls out the canister from the transport cask (FIG. 2). .
[0038]
After the canister transfer device 18 moves above the desired canister loading / unloading port 7, the storage body opening / closing shielding door 24 and the loading / unloading opening / closing shielding door 23 at the bottom of the housing 22 are opened, and the hand portion 25 of the lifting device 21 is moved. The shielding plug 8 of the canister loading / unloading port 7 is removed by the hand portion 25, and the hand portion 25 is pulled up to store the shielding plug 8 in the storage body 22. Then, the canister transfer device 18 moves above the shielding plug temporary storage place 16 to place the shielding plug 8, and further moves laterally to lift the canister 6 from the transportation cask through the canister take-out port 20 that has been opened in advance. Then, the storage body 22 is stored, and the storage body opening / closing shielding door 24 is closed. However, while the canister transfer device 18 is leaving the shielding plug 8 and taking the canister 6 in this way, the door opening / closing shielding door 23 in the closed state is disconnected from the canister transfer device 18 and the canister is inserted and removed. Place it on the mouth 7 and close the canister entrance 7 to shield it.
[0039]
The canister transfer device 18 again moves onto the entrance / exit opening / closing shielding door 23 that closes the canister entrance / exit 7, connects the canister transfer device 18 to the upper portion of the entrance / exit opening / closing shielding door 23, and Opening / closing shielding door 24 for storage body and opening / closing shielding door 23 for entrance / exit are opened, and canister 6 in storage body 22 is moved by lifting device 21 to open / close shielding door 24 for storage body, opening / closing shielding door 23 for entrance / exit, and canister entrance / exit Go through 7 in order and lower to canister storage chamber 3. At this time, the lower canister 6 is held at the upper and lower ends by the canister outlet 7 of the ceiling slab 4 and the canister support base 28 on the floor slab 5.
[0040]
When the canister 6 is installed in the canister storage chamber 3, the door opening / closing shielding door 23 is immediately closed. The canister transfer device 18 separates the opening / closing opening / closing shielding door 23 again, and removes the shielding plug 8 of the shielding plug temporary storage place 16 while it is placed on the canister loading / unloading opening 7. And return to the entrance / exit opening / closing shielding door 23. Then, the opening / closing opening / closing shielding door 23 is opened, the shielding plug 8 in the storage body 22 is lowered by the lifting device 21, and the shielding plug 8 is installed in the canister loading / unloading opening 7.
[0041]
When the canister 6 is unloaded from the facility 1, the unloading operation is performed in the reverse procedure.
[0042]
Such a canister transfer device 18 conveys the canister 6 having no radiation shielding ability at the side trunk portion and the bottom portion while being shielded by the storage body 22 and the open / close shielding door 24 for the storage body. It is possible to enter and work in the canister transfer chamber 2 at all times including during transfer of the canister 6.
[0043]
The canister transfer device 18 has a structure in which the storage body 22 is integrated with a trolley that traverses the crane girder and travels on the floor surface of the canister transfer chamber 2, so that the ceiling of the storage building is lowered. Can do.
[0044]
The decay heat of the spent fuel in the canister 6 is removed by the flow of cooling air by natural ventilation generated from the air inlet 12 to the canister storage chamber 3 and the cooling air discharge duct 10. The heat generated by the canister 6 due to the decay heat of the spent fuel heats the air around the canister, and the heated and lightened air rises in the chimney-like cooling air discharge duct 10, so that the cooling air is introduced into the canister storage chamber 3. You can flow. This cooling air is taken from the air inlet 12 from the outside of the storage facility 1 and reaches the canister storage chamber 3 through the cooling air inflow duct 9 and the air rectifying mechanism 11. The cooling air that has flowed in the horizontal direction between the canisters 6 passes through the cooling air discharge duct 10 and is discharged out of the storage facility 1 through the air discharge port 13. At this time, the air rectifying mechanism 11 in the air inflow portion and the air rectifying mechanism 19 in the air outflow portion promote the horizontal flow and enhance the cooling effect.
[0045]
The air rectifying mechanism 11 of the air inflow portion is provided between a columnar structure 26 having a diameter similar to that of the canister 6 arranged at a predetermined interval between the ceiling slab 4 and the floor slab 5, and the columnar structure 26. It comprises a plurality of rectifying plates 27 arranged parallel to the ceiling slab 4 and the floor slab 5 in the gap (FIG. 5). The columnar structure 26 disturbs the air flow when air passes through the gaps between the columnar structures 26, and promotes heat removal of the first row of canisters 6 as viewed from the air inflow side of the canister storage chamber 3. To do. Further, the rectifying plate 27 promotes the horizontal flow of the canister storage chamber 3 and has a shielding effect against radiation components from the canister 6 that cross the rectifying plate 27.
[0046]
On the other hand, the air rectifying mechanism 19 in the air outflow portion does not need a columnar structure for disturbing the air flow, and is composed only of a rectifying plate. This current plate similarly promotes the flow in the horizontal direction, and has a shielding effect against radiation components and the like that cross the current plate.
[0047]
The storage facility 1 of this example can have an independent structure from the air inlet 12 to the air outlet 13 corresponding to a certain unit room to those corresponding to other unit rooms. The canister storage chamber 3 can be easily expanded by extending the travel range of the vehicle or by extending the movement range of the canister transport carriage 15.
[0048]
In this example, the canister that contains the spent fuel assembly and is sealed is stored in the canister storage chamber as it is, so that heat generation from the canister is generated compared to the conventional technology in which the canister is stored in the storage pipe arranged in the canister storage chamber. Directly transmitted to the surrounding air, the efficiency of removing decay heat of spent fuel is improved. In addition, the air rectifying mechanism 11 of the present invention combining the cylindrical structure 26 and the rectifying plate 27 further enhances the cooling effect as compared with the prior art using only the rectifying plate, so that the canister is enlarged and the spent fuel assembly is increased. The number of bodies can be increased, and the storage efficiency of spent fuel is improved.
[0049]
The canister 6 that can be stored in the facility of the present invention has, for example, a diameter of 1.6 to 1.8 mm and a height of about 5 m. A maximum of 24 fuel assemblies of a pressurized water reactor (PWR) can be placed in the canister 6. It can store up to 70 fuel assemblies of boiling water reactor (BWR).
[0050]
【The invention's effect】
According to the radioactive substance storage method and radioactive substance storage facility of the present invention, the following effects are combined.
[0051]
A canister sealed with exothermic radioactive material such as spent fuel at a nuclear power plant is transported to a storage facility with a transport cask, and the canister is stored as it is without being transferred. Does not require spent fuel refilling equipment or ventilation equipment to contain radioactive material. Therefore, it is possible to simplify and reduce ventilation air-conditioning equipment and spent fuel handling equipment. The handling process of canisters can be simplified.
[0052]
From removal from the transport cask to storage in the canister storage chamber, the canister with sealed radioactive material is stored and transferred in a canister transfer device with shielding capability, so that spent fuel is not handled in a naked state. Therefore, there is no environmental release of radioactive materials during handling, and safety evaluation due to a fall accident during refilling of spent fuel becomes unnecessary.
[0053]
Also, since the ceiling and floor of the canister storage room are stored in a state where only the upper and lower ends of the canister are supported, the support structure in the canister storage room for maintaining earthquake resistance is reduced. As a result, the canister storage room And the cooling performance is improved because the flow of cooling air is not hindered.
[0054]
In addition, since the canister is stored directly in the canister storage chamber without using a storage tube as in the prior art, the heat generated from the canister is directly transmitted to the surrounding air, improving the efficiency of removing decay heat such as spent fuel. To do. In addition, the air rectifying mechanism of the present invention combining the cylindrical structure and the rectifying plate further enhances the cooling effect as compared with the conventional technology using only the rectifying plate. Therefore, the canister is enlarged to increase the amount of radioactive material stored. The storage efficiency of radioactive materials can be improved.
[0055]
In addition, the canister transfer device of the present invention allows the plug to be attached / detached and transported to block the entrance / exit of the canister storage chamber, and the canister transport to be combined into a single housing, so the equipment is compact and the storage building is large. Do not turn.
[0056]
The ceiling of the canister storage room is structurally separated from the building structure of the building, and a structure using a divided concrete board is allowed, and the thermal expansion of the concrete board is allowed by the side wall standing on the floor of the canister storage room Hold on. Thereby, the temperature restriction requested | required from the structural strength as a building structure is not imposed on a concrete part. By such structural measures for the ceiling portion of the canister storage chamber, the canister can be enlarged and the canister storage chamber can be densified, and the storage density of the radioactive material can be improved.
[Brief description of the drawings]
FIG. 1 is a cross-sectional view of a radioactive material dry storage facility according to an embodiment of the present invention.
FIG. 2 is another cross-sectional view of a radioactive material dry storage facility according to one embodiment of the present invention.
FIG. 3 is an enlarged view of the canister transfer device shown in FIG. 1;
4 is a cross-sectional view of the canister storage chamber according to an embodiment of the present invention, showing a cross section in a direction perpendicular to FIG.
5 is a configuration diagram of an air rectifying mechanism of an air inflow portion shown in FIG. 1. FIG.
[Explanation of symbols]
1 Radioactive material dry storage facility
2 Canister transfer room
3 Canister storage room
4 Ceiling slab
5 Floor slab
6 Canister
7 Canister slot
8 Shield plug
9 Cooling air inflow duct
10 Cooling air discharge duct
11 Air rectification mechanism at the air inlet
12 Air inlet
13 Air outlet
14 Overhead crane
15 Cask transport cart
16 Shield plug temporary storage
17 Side wall
18 Canister transfer device
19 Air rectification mechanism of air outflow part
20 Canister take-out port
21 Lifting device
22 Storage body
23 Open / close door for entrance
24 Open / close shielding door for storage
25 Hand part
26 Cylindrical structure
27 Rectifier plate
28 Canister support
29 Steel plate

Claims (7)

Transporting the canister containing the radioactive substance to the upper space of the canister storage room in the storage facility via the ceiling slab while shielding it;
Removing the shielding plug provided at the canister outlet of the ceiling slab;
Providing an openable / closable opening / closing shielding door for opening / closing in the canister loading / unloading port from which the shielding plug is removed, in a closed state;
Opening the opening / closing shielding door for the access port provided in a closed state, and storing the transported canister in the canister storage chamber through the canister access port while shielding,
After the canister is stored in the canister storage chamber, the step of closing the door for opening and closing the door;
Removing the open / close opening / closing shielding door for the entrance / exit from the canister entrance / exit, and attaching the shielding plug;
The canister, and cooling by air flowing through the canister storage compartment horizontally,
A radioactive material storage method comprising: The step of removing the shielding plug is performed prior to the step of transporting while shielding the canister,
The step of removing the shielding plug includes
Transporting the doorway open / close door to the upper space of the canister storage room via the ceiling slab;
On the shielding plug provided in the canister entrance / exit of the ceiling slab, placing the transported entrance / exit entrance shielding door in a closed state;
Opening the entrance / exit entrance shielding door provided in a closed state and removing the shielding plug while shielding,
After closing the shielding plug, closing the entrance door shielding door;
Transporting the removed shielding plug to a shielding plug temporary storage provided at a position different from the canister loading / unloading port,
The radioactive substance storage method according to claim 1. The canister, only upper and lower ends of said canister, respectively, wherein Ru is stored in a state of being supported by the ceiling slab and the floor of the canister storage compartment, radioactive material storage method according to claim 1 or 2. The Ruki Yanisuta to house the radioactive material and savings built, and the canister storage compartment cooled by air flowing through the canister, the internal horizontally,
A side wall that divides the canister storage chamber into a plurality of unit chambers;
A ceiling slab of the canister storage chamber defining the canister storage chamber with the sidewall;
Have
The radioactive material storage facility , wherein the ceiling slab includes a plurality of concrete plates provided independently of each other, and each of the concrete plates is independently supported from a building structure by the corresponding side wall . A canister transfer chamber provided above the canister storage chamber via the ceiling slab;
A canister transfer device that is movable in the canister transfer chamber and transfers the canister into the canister storage chamber;
Have
5. The radioactive material storage facility according to claim 4, wherein the ceiling slab has a canister outlet for the canister transfer device to transfer the canister into the canister storage chamber . The canister transfer device comprises:
The shielding plug provided on the canister or the floor slab, selectively incorporating the opening provided in the lower portion, and a housing for housing while shielding the canister,
An opening / closing shielding door for the storage body provided at the lower end portion of the storage body so as to be able to open and close the opening of the lower end portion;
For the loading / unloading port which is provided below the opening / closing shielding door for the housing so as to be detachable from the housing, covers the canister loading / unloading port in a detached state, and can be opened / closed in either state . An open / close shield door,
The radioactive substance storage facility according to claim 5, comprising: The radioactive substance storage facility according to any one of claims 4 to 6 , wherein the concrete plate is entirely surrounded by a steel plate .

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