Multi-Barrier-Based Vertical Transfer Underground Storage and Disposal System for Radioactive Waste Including Guide Rails and an Elevator-Type Transfer Device

Abstract

The present invention relates to technology for the storage and disposal of spent nuclear fuel and radioactive waste, and more specifically, to a technology for an integrated storage system that stores high-level and low-to-intermediate radioactive waste for a long period by transporting it through a vertical transport passage and utilizing an underground space separation structure and a multi-barrier storage facility. The underground radioactive waste storage and disposal system according to the present invention is a facility applicable to both new and existing nuclear power plants. In the case of new nuclear power plants, spent nuclear fuel is transferred directly to an underground temporary storage facility via vertical passages and elevators without installing cooling pools inside the plant, and after the phased vertical transfer is completed, it is transferred to a storage tank connected to the temporary storage facility via waterways for long-term storage and cooling. This eliminates the need to install cooling pools inside the plant, thereby resolving spatial constraints and environmental issues and maintaining the plant in a pleasant condition. Furthermore, in the case of existing nuclear power plants, spent nuclear fuel is directly removed from the cooling pools installed inside the plant and transferred directly to an underground temporary storage facility via vertical passages and elevators, just as in new nuclear power plants. This resolves the spatial constraints caused by cooling pools inside the plant and ultimately allows for the dismantling or elimination of the cooling pools. In addition, since it is connected to an underground temporary storage facility and cooled in a water tank for long-term storage, and then immediately transferred to a nearby connected permanent storage facility, there is no need for long-distance transport as in the past, which has the advantage of resolving issues related to time and cost associated with transportation.

Description

Technology Field

[0001] The present invention relates to technology for the storage and disposal of spent nuclear fuel and radioactive waste, and more specifically, to a technology for an integrated storage system that stores high-level and low-to-intermediate radioactive waste for a long period by transporting it through a vertical transport passage and utilizing an underground space separation structure and a multi-barrier storage facility. Background Technology

[0003] Radioactive waste generated from nuclear power plants is divided into high-level and low- and intermediate-level nuclear waste; high-level nuclear waste must be stored in permanent deep geological storage facilities after being temporarily retained for a certain period.

[0004] Spent nuclear fuel generated at conventional nuclear power plants is cooled in a cooling pit for a sufficient period of time; the cooling pit (also known as a cooling pool) is a temporary storage facility typically installed inside the nuclear power plant.

[0005] Even if the aforementioned spent nuclear fuel is immersed in a cooling pool to cool down, the surrounding area may exhibit high concentrations of radioactive materials, creating a very dangerous environmental condition, and entry into the interior can have adverse effects on the human body.

[0006] In addition, since it is a temporary storage facility but requires long-term storage, there is a problem that if the cooling pool is damaged or the power is cut off due to external factors such as an earthquake, cooling cannot be performed, and the power plant could be destroyed by overheating. In fact, the core explosion accident at the Fukushima nuclear power plant caused by the 2011 Great East Japan Earthquake can be seen as having resulted in even more adverse effects on the fuel rods stored in the pools inside the nuclear power plant.

[0007] In addition, conventional cooling pools are typically installed inside nuclear power plants, but for the decommissioning of a plant, a problem arises in that all spent nuclear fuel in the cooling pools must be moved for dry storage and then permanently stored.

[0008] Spent nuclear waste from existing nuclear power plants is classified into high-level and low-to-intermediate levels, and the method of collecting waste from various locations for storage requires the structures of storage facilities to be large. In particular, for high-level nuclear waste, not only is the installation of safe storage facilities required, but long-distance transportation is also very complex, involving safe storage containers and means of transport. Consequently, even now, about 70 years after the start of nuclear power plant operations, there is no stable and permanent disposal system.

[0009] The existing temporary dry storage method involves loading spent nuclear fuel assemblies into metal canisters, sealing them, and housing them in concrete overpacks or storage modules for shielding protection.

[0010] However, breaking a sealed canister to re-separate the internal fuel assemblies is difficult to regard as a standard operational procedure due to issues such as high radiation, residual heat, contamination diffusion, remote operation, and repackaging. Therefore, when considering transfer to a final disposal facility and rehandling after long-term storage, the specifications and weight of the canister unit must be carefully reviewed in relation to connectivity with the permanent storage facility and the necessity of additional barrier structures.

[0011] In the past, methods such as the case of Finland, which involve digging a cave (tunnel) into a bedrock layer about 500 meters underground to store nuclear waste, have been proposed. However, it has been pointed out that finding a suitable location for such an underground cave (tunnel) is difficult, and that underground tunnel facilities may lack adequate protection against various forms of external forces, such as ground deformation caused by earthquakes or the collapse of tunnel sections.

[0012] Permanent storage facilities for spent nuclear fuel require a system equipped with highly reliable materials and structures that not only perform radioactive waste disposal functions but also possess seismic performance with high tensile strength capable of withstanding high-intensity tremors and resistance to chemical degradation.

[0013] However, existing materials or structural systems do not yet possess such performance capabilities. Since they are limited to using reinforced concrete facilities with a limited lifespan or underground cave facilities that are spatially constrained and vulnerable to earthquakes, they do not serve as a fundamental solution.

[0014] Furthermore, securing a suitable location for installing existing stable facilities is inconvenient and carries the risk of public complaints. In particular, the process of transferring spent nuclear fuel cooled at multiple nuclear power plants to a single collective storage facility is time-consuming and astronomically costly, presenting numerous problems that make realization difficult. Consequently, the current situation involves temporarily storing spent nuclear fuel, cooled in internal cooling pools, in a separate dry storage manner around the plants.

[0015] To address these issues, the applicant has proposed a construction technology for a new dimension of nuclear waste storage facility through the prior registered patent, Korean Patent Registration No. 10-2703296. This technology fundamentally retains radioactive waste disposal performance while, unlike existing reinforced concrete facilities, does not corrode or deteriorate, thus avoiding limitations on the facility's lifespan. Furthermore, by providing seismic performance with excellent tensile strength, it can fundamentally resolve and prevent potential problems as a permanent storage facility for nuclear waste generated from not only small modular reactors (SMRs) but also large reactors.

[0016] This technology proposes a method for constructing a permanent storage facility for spent nuclear fuel using resin mortar having ultra-high strength and high seismic resistance, thereby enabling the resin mortar to secure structural stability of the permanent storage facility that conventional reinforced concrete cannot provide.

[0017] However, while this technology explains that resin mortar possesses characteristics that differ from conventional reinforced concrete facilities, such as superior seismic resistance, shielding, and performance, as well as enhanced resistance to corrosion and deterioration, and that structures utilizing these characteristics offer various advantages over existing concrete storage facilities, it was necessary to secure structural functions that can withstand the low thermal stress of resin mortar and provide higher stability than the previously proposed technology in terms of seismic resistance and shielding through multiple barriers.

[0018] Furthermore, regarding the disposal methods for high- and low-to-intermediate-level nuclear waste, there was a need for technology capable of meeting the requirements for a system that can unify procedural disposal processes, such as pool storage within the nuclear power plant, dry storage, and permanent storage. In particular, there were still issues regarding the need to remove all remaining cooling pools during the decommissioning of nuclear power plants, as well as the need to perform purification and leveling operations after removal. Additionally, spatial constraints and environmental problems persisted because cooling pool facilities remained within the plant. Prior art literature

[0020] 1. Republic of Korea Registered Patent No. 10-1621881 "Low-radiation cement material for nuclear power plant containment walls and method for manufacturing the same" 2. Republic of Korea Published Patent No. 10-2012-0132854 "Composition for neutron shielding containing foamed metal" 3. Republic of Korea Registered Patent No. 10-0779789 "Epoxy resin composition with high neutron shielding capability and transparent neutron shielding material obtained by curing the epoxy resin composition" 4. Republic of Korea Registered Patent No. 10-1688646 "Double shielding concrete for high-level neutron shielding and method for manufacturing the same" 5. Republic of Korea Registered Patent No. 10-1508957 "Radiation shielding concrete composition" 6. Republic of Korea Registered Patent No. 10-1712879 "Concrete for neutron shielding of a primary containment wall of a nuclear power plant and method for manufacturing the same" The problem to be solved

[0021] This invention was developed to resolve the situation of the conventional technology described above. In the case of a new nuclear power plant, the invention aims to provide a technology that allows spent nuclear fuel to be removed from the cooling pool and transported directly to an underground temporary storage facility via a vertical passageway and elevator without the use of vehicles for temporary storage, and subsequently transferred to a storage tank connected to the temporary storage facility via a waterway for long-term storage and cooling. This eliminates the need to install a cooling pool inside the nuclear power plant, thereby resolving spatial constraints and environmental issues and enabling the nuclear power plant to be maintained in a comfortable state.

[0022] Furthermore, the present invention aims to provide a technology that can resolve the spatial constraints caused by cooling pools inside existing nuclear power plants and ultimately enable the dismantling or elimination of cooling pools, even in the case of existing nuclear power plants, by allowing spent nuclear fuel to be directly removed from the cooling pools installed inside the plant and transported to an underground temporary storage facility via vertical passages and elevators, just as in new nuclear power plants.

[0023] Furthermore, the present invention aims to provide a technology that can solve the problems of time and cost associated with transportation by connecting to an underground temporary storage facility, storing it for a long period in a water tank to cool it, and then immediately transferring it to a nearby permanent storage facility for storage, thereby eliminating the need for long-distance travel as in conventional methods.

[0024] In addition, the present invention aims to provide a technology capable of permanently storing spent nuclear fuel, i.e., high-level nuclear waste, along with integrated storage of intermediate and low-level nuclear waste in a single space.

[0025] Furthermore, the present invention aims to provide a technology that enables the smooth decommissioning of nuclear power plants by eliminating the need to remove cooling pools and perform purification and leveling operations as in conventional methods, and by completing the process merely by closing the passageways. means of solving the problem

[0027] In order to achieve the above-mentioned objectives, the present invention

[0028] A transfer device for transferring spent nuclear fuel rods stored in the internal reservoir of an existing nuclear power plant or sealed in a canister in a reactor;

[0029] A vertical transport passage for transporting the above spent nuclear fuel rods in a vertical direction to an underground temporary storage pool; and

[0030] It is configured to include an underground storage space for storing spent nuclear fuel rods transported through the above-mentioned vertical transport passage; and

[0031] The above underground storage space is an underground temporary storage tank for temporarily storing spent nuclear fuel rods transported through the above vertical transport passage,

[0032] A moving channel for transporting spent nuclear fuel rods stored in the above-mentioned underground temporary storage pool in a horizontal direction,

[0033] A storage tank for cooling spent nuclear fuel rods transported through the above-mentioned transport channel and

[0034] The present invention provides an underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste, characterized by being configured to include a permanent storage facility for permanently storing spent nuclear fuel rods cooled in the above-mentioned storage tank.

[0035] In one embodiment of the present invention,

[0036] The above-mentioned vertical transfer passage includes a structure in which a plurality of modules formed of resin mortar are connected in a vertical direction, and

[0037] A guide rail is formed inside the above vertical transfer passage, and

[0038] An elevator-type transfer device that moves along the guide rail is installed within the above vertical transfer passage, and

[0039] The upper part of the above vertical transfer passage is equipped with an automatically opening and closing sealing cap, and

[0040] The above-mentioned vertical transfer passage is characterized by being permanently sealed by resin mortar during nuclear power plant decommissioning.

[0041] In addition, in one embodiment of the present invention,

[0042] The above-described vertical transfer passage is formed by precast modules, and the precast modules are manufactured into standardized shapes using molds and assembled on-site, and are characterized by having a sealing structure formed between the precast modules.

[0043] In addition, in one embodiment of the present invention,

[0044] The above guide rail is characterized by having a structure that extends in a vertical direction and is arranged in a single or multiple numbers at the inner corner of the vertical transfer passage.

[0045] In addition, in one embodiment of the present invention,

[0046] The above guide rail is characterized by having a structure that is combined with a roller or a guide cap, and the roller and the guide cap are configured to form a vibration-free structure.

[0047] In addition, in one embodiment of the present invention,

[0048] The above elevator-type transfer device includes a platform for carrying a storage container and has a structure that is raised and lowered by a driving device,

[0049] The above-mentioned drive device includes wire, chain, hydraulic, or electric drive methods, and

[0050] The above elevator-type transfer device is characterized by being configured to include a fall prevention device and a speed control device.

[0051] In addition, in one embodiment of the present invention,

[0052] The above-described sealing cap is characterized by having a structure that opens and closes automatically, a structure that allows for repeated opening and closing, and is configured to enable remote control.

[0053] In addition, in one embodiment of the present invention,

[0054] The above sealing cap is composed of a single or multiple caps, forms multiple barrier walls, and is characterized by having a filling layer formed between the multiple sealing caps.

[0055] In addition, in one embodiment of the present invention,

[0056] The above-mentioned underground storage space is characterized by being configured such that the workspace and the storage space are separated.

[0057] In addition, in one embodiment of the present invention,

[0058] The inner wall of the space including the above-mentioned underground temporary storage tank, the above-mentioned moving channel, and the above-mentioned water tank storage tank forms a three-layer closed structure in which the outermost layer is a waterproof ordinary concrete layer, the inner layer of the ordinary concrete layer is a resin mortar layer, and the inner layer of the resin mortar layer is an ultra-high-strength concrete layer.

[0059] Between the above-mentioned water tank storage tank and the moving waterway, an ultra-high-strength concrete layer is provided on the outside and a resin mortar layer is provided on the inside, and a management passage is provided on the upper side therefrom.

[0060] The space including the above-mentioned underground temporary storage tank, the above-mentioned moving channel, and the above-mentioned storage tank is characterized by having a transfer hoist provided on the upper side for transferring spent nuclear fuel rods and low- and intermediate-level nuclear waste in a horizontal direction.

[0061] In addition, in one embodiment of the present invention,

[0062] It is characterized by further including a second transfer device for transferring low- and intermediate-level nuclear waste to the above-mentioned underground storage space and a second vertical transfer passage for transferring the low- and intermediate-level nuclear waste to the underground storage space in a vertical direction.

[0063] In addition, in one embodiment of the present invention,

[0064] The above permanent storage facility is characterized by including a second storage space for storing low- and intermediate-level nuclear waste, separated into a separate space, in addition to a first storage space for permanently storing spent nuclear fuel rods cooled in the above storage tank.

[0065] In addition, in one embodiment of the present invention,

[0066] The first storage space has a three-layer closed structure in which the outermost part of the inner wall is a waterproof ordinary concrete layer, a resin mortar layer inside the ordinary concrete layer, and an ultra-high-strength concrete layer inside the resin mortar layer.

[0067] It is composed of a seating space in which a permanent storage container for spent nuclear fuel rods is stored inside the above-mentioned three-layer closed structure, bentonite for filling the permanent storage container within the seating space, a girder made of ultra-high-strength concrete that seals the upper part of the seating space, and a resin mortar layer that seals the upper part of the girder.

[0068] The above first storage space is characterized by having a transfer hoist provided on the upper side for transferring a permanent storage container for spent nuclear fuel rods in a horizontal direction.

[0069] In addition, in one embodiment of the present invention,

[0070] The permanent storage of the above spent nuclear fuel rods is characterized by being composed of a canister in which bentonite or bentonite containing silica sand is filled to a certain thickness on the bottom surface, leveled, and then the container is fixed, and the outside is again filled with bentonite or bentonite containing silica sand and sealed.

[0071] In addition, in one embodiment of the present invention,

[0072] The above-mentioned second storage space has a three-layer multi-barrier closed structure in which the outermost part of the inner wall is a waterproof ordinary concrete layer, a resin mortar layer inside the ordinary concrete layer, and an ultra-high-strength concrete layer inside the resin mortar layer.

[0073] It is configured to include a storage space on the inner side of the above-mentioned three-layer closed structure in which a permanent storage container for low- and intermediate-level nuclear waste is stored, and

[0074] The upper side of the second storage space is characterized by having a transfer hoist for transferring the permanent storage container for the intermediate and low-level nuclear waste in a horizontal direction.

[0075] In addition, in one embodiment of the present invention,

[0076] It is characterized by having a main passageway for accessing the above-mentioned permanent storage facility and an additional emergency passageway provided on the outside of the second storage space.

[0077] In addition, in one embodiment of the present invention,

[0078] It is characterized by having a single or multiple additional managed elevators for accessing the above-mentioned underground storage space.

[0079] In addition, in one embodiment of the present invention,

[0080] The above resin mortar is characterized by being an oil-based resin mortar.

[0081] In addition, in one embodiment of the present invention,

[0082] The above-mentioned oil-based resin mortar comprises a resin liquid main component comprising 70-90% by weight of one or more resin main components selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5-20% by weight of an epoxy resin auxiliary component, 1-5% by weight of a coagulant, and 1-20% by weight of a flame retardant; and

[0083] It is characterized by comprising a curing component comprising 40-60% by weight of polyoxypropylene diamine, 20-40% by weight of isophorone diamine, 10-20% by weight of polyamide amine, 1-10% by weight of one or more amines selected from triethylenetetraamine and diethylenetriamine, and 1-10% by weight of a curing accelerator.

[0084] In addition, in one embodiment of the present invention,

[0085] It is characterized by the formation of a management passageway to allow vehicles or pedestrians to move in one or both directions, and the configuration of an inspection window to allow visual inspection of the internal condition. Effects of the invention

[0087] The underground storage and disposal system for radioactive waste according to the present invention is a facility applicable to both new and existing nuclear power plants. In the case of a new nuclear power plant, spent nuclear fuel is transferred directly to an underground temporary storage facility via a vertical transfer passage and an elevator without installing a cooling pool inside the plant, and after the stepwise vertical transfer is completed, it is transferred to a storage tank connected to the temporary storage facility via a waterway for long-term storage and cooling. This eliminates the need to install a cooling pool inside the plant and resolves spatial constraints and environmental issues, thereby having the effect of maintaining the plant in a comfortable state.

[0088] Furthermore, even in the case of existing nuclear power plants, spent nuclear fuel is directly removed from the cooling pools installed inside the plant and transported to an underground temporary storage facility via vertical passageways and elevators, just like in new plants. This resolves the spatial constraints caused by the cooling pools inside the plant and ultimately allows for the dismantling and removal of the cooling pools.

[0089] In addition, the underground storage and disposal system for radioactive waste according to the present invention connects to an underground temporary storage facility to store waste for a long period in a storage tank, cools it, and then immediately transfers it to a nearby permanent storage facility for storage. Since this eliminates the need for long-distance transport as in conventional methods, it can resolve the issues of time and cost associated with transportation.

[0090] In addition, the underground radioactive waste storage and disposal system according to the present invention can enhance space utilization by enabling the integrated storage of low- and intermediate-level nuclear waste in one space along with the permanent storage of spent nuclear fuel, i.e., high-level nuclear waste, which has been cooled in the storage tank; it has the advantage of being able to permanently store spent nuclear fuel, i.e., high-level nuclear waste, and low- and intermediate-level nuclear waste together; it allows for external inspection and management by installing a management passageway and placing radiation inspection sensors and surveillance cameras (CCTV) inside, and enables continuous post-management through wired and wireless networks.

[0091] In addition, the underground radioactive waste storage and disposal system according to the present invention has the advantage of enabling the decommissioning of nuclear power plants to proceed smoothly, as it does not require removing cooling tanks and performing purification and leveling operations as in conventional methods, and the process is completed simply by closing the passageways.

[0092] In addition, the underground storage and disposal system for radioactive waste according to the present invention has the advantage of being able to operate as a medium- or small-sized storage facility rather than a method of collecting radioactive waste from various locations and storing it in a large structure, thereby maximizing efficiency in the construction of the storage facility and facilitating management.

[0093] Furthermore, advanced countries such as the United States and Europe require the provision of a nuclear waste disposal facility in close proximity to the nuclear power plant as an essential condition for construction permits. When using the underground radioactive waste storage and disposal system according to the present invention, stability such as seismic resistance, radioactivity, non-combustibility, and permanent durability can be secured. Additionally, since construction is easy near the nuclear power plant, the essential requirements for the aforementioned construction can be met. Moreover, by simultaneously constructing a facility capable of storing high-level or low-to-medium-level waste around the nuclear power plant, there is an advantage in that the nuclear waste storage facility can be integrated along with the construction of the nuclear power plant.

[0094] In addition, the underground radioactive waste storage and disposal system according to the present invention can achieve a level of safety that prevents destruction even by external military attacks, such as bunker busters, by constructing a transport elevator, a temporary storage tank space, a water tank storage tank space, and a permanent storage facility using resin mortar having ultra-high strength and ultra-high tensile strength. Brief explanation of the drawing

[0096] FIG. 1 is a diagram showing the overall structure of a radioactive waste underground storage and disposal system according to the present invention. FIG. 2 is a drawing showing a vertical transport passage in an underground radioactive waste storage and disposal system according to the present invention. FIG. 3 is a drawing showing the sealing of a vertical transfer passage when the nuclear power plant decommissioning or vertical transfer is completed in the underground storage and disposal system for radioactive waste according to the present invention. FIG. 4 is a drawing showing the integrated structure of high-level and medium-to-low-level underground storage facilities of a radioactive waste underground storage and disposal system according to the present invention. FIG. 5 is a cross-sectional view showing a storage tank for spent nuclear fuel rods in an underground radioactive waste storage and disposal system according to the present invention. FIG. 6 is a cross-sectional view showing a permanent storage facility for spent nuclear fuel rods in an underground radioactive waste storage and disposal system according to the present invention. FIG. 7 is a cross-sectional view showing a fuel rod fixed in a canister that is stored in a permanent storage facility for spent nuclear fuel rods in a radioactive waste underground storage and disposal system according to the present invention. FIG. 8 is a cross-sectional view showing a permanent storage facility for low- and intermediate-level nuclear waste in an underground radioactive waste storage and disposal system according to the present invention. Specific details for implementing the invention

[0097] The present invention will be described in more detail below.

[0099] FIG. 1 is a diagram showing the overall structure of a radioactive waste underground storage and disposal system according to the present invention.

[0101] As illustrated in the drawing, the underground radioactive waste storage and disposal system according to the present invention is constructed underground at a nuclear power plant and is basically a facility capable of storing spent nuclear fuel rods already stored in the internal reservoir of an existing nuclear power plant, or storing and disposing of newly generated spent nuclear fuel rods from the nuclear power plant (specifically, nuclear fuel rods sealed in canisters) underground.

[0102] Specifically, the underground storage and disposal system for radioactive waste according to the present invention

[0103] A transfer device (100) for transferring spent nuclear fuel rods (10) stored in an internal reservoir (20) of an existing nuclear power plant or sealed in a canister in a reactor;

[0104] A vertical transport passage (200) for transporting the above spent nuclear fuel rods in a vertical direction to an underground temporary storage tank (301); and

[0105] It is configured to include an underground storage space (300) for storing spent nuclear fuel rods transported through the above vertical transport passage, and

[0106] The above underground storage space (300) is an underground temporary storage tank (301) for temporarily storing spent nuclear fuel rods (10) transported through the above vertical transport passage (200).

[0107] A moving channel (302) for transporting spent nuclear fuel rods stored in the above-mentioned underground temporary storage tank in a horizontal direction,

[0108] A storage tank (303) for cooling spent nuclear fuel rods transported through the above-mentioned transport channel (302) and

[0109] It may be configured to include a permanent storage facility (400) for permanently storing spent nuclear fuel rods cooled in the above-mentioned storage tank (303).

[0111] FIG. 2 is a drawing showing a vertical transfer passage in a radioactive waste underground storage and disposal system according to the present invention, and FIG. 3 is a drawing showing sealing the vertical transfer passage when a nuclear power plant is decommissioned or vertical transfer is completed in a radioactive waste underground storage and disposal system according to the present invention.

[0112] As illustrated in the drawing, in the underground storage and disposal system for radioactive waste according to the present invention, the vertical transfer passage (200) comprises a structure in which a plurality of modules (210) formed of resin mortar are connected in a vertical direction, a guide rail (220) is formed inside the vertical transfer passage, an elevator-type transfer device that moves along the guide rail is installed inside the vertical transfer passage, and an automatically opening and closing sealing cap is provided on the upper part of the vertical transfer passage.

[0113] Additionally, when decommissioning the nuclear power plant, the vertical transfer passage (200) can be permanently sealed by resin mortar (240).

[0114] In the underground storage and disposal system for radioactive waste according to the present invention, the vertical transfer passage (200) is formed by a precast module (210), the precast module is manufactured into a standardized shape using a mold and assembled on-site, and a sealing structure is formed between the precast modules.

[0115] In the present invention, the guide rail installed inside the vertical transfer passage (200) is a device that enables an elevator-type transfer device to be transferred up and down. The guide rail has a structure that is combined with a roller or a guide cap, and the roller and guide cap are configured to have a vibration-free structure so that transfer is achieved in a low-friction state.

[0116] The guide rail (220) has a structure that extends in a vertical direction and can be arranged in a single or multiple ways at the inner corner of the vertical transfer passage (200).

[0117] In the present invention, the elevator-type transfer device, although not specifically illustrated in the drawings, includes a platform for carrying a storage container and has a structure that is raised and lowered by a driving device, and the driving device may include a wire, chain, hydraulic, or electric drive method.

[0118] In addition, the elevator-type transfer device is configured to include a fall prevention device and a speed control device, and can be configured to enable remote control.

[0119] In addition, in the underground storage and disposal system for radioactive waste according to the present invention, the sealing cap (230) has a structure that opens and closes automatically, has a structure that allows for repeated opening and closing, and can be configured to enable remote control.

[0120] Additionally, the sealing cap (230) may be composed of a single or multiple caps, forming multiple barrier walls, and a filling layer may be formed between the multiple sealing caps.

[0121] The above vertical transfer passage (200) can be filled with resin mortar (240) and permanently sealed when the nuclear power plant is decommissioned or when the underground storage and disposal system for radioactive waste according to the present invention is closed.

[0122] FIG. 4 is a drawing showing the integrated structure of high-level and medium-to-low-level underground storage facilities of a radioactive waste underground storage and disposal system according to the present invention.

[0123] As illustrated in the drawing, the underground storage space (300) for storing spent nuclear fuel rods (10) transported through the vertical transport passage (200) in the present invention is configured such that the work space and the storage space are separated.

[0124] In the present invention, the underground storage space (300) may be configured in a dome shape overall.

[0125] In the present invention, the underground storage space (300) is an underground temporary storage tank (301) for temporarily storing spent nuclear fuel rods (10) transported through the vertical transport passage (200).

[0126] A moving channel (302) for transporting spent nuclear fuel rods stored in the above-mentioned underground temporary storage tank in a horizontal direction,

[0127] A storage tank (303) for cooling spent nuclear fuel rods transported through the above-mentioned transport channel and

[0128] It is configured to include a permanent storage facility (400) for permanently storing spent nuclear fuel rods cooled in the above-mentioned storage tank (303).

[0129] At this time, a pre-stabilization workspace (304) may be additionally configured before transferring the spent nuclear fuel rods cooled in the above-mentioned storage tank (303) to the permanent storage facility (400).

[0131] FIG. 5 is a cross-sectional view showing a storage tank for spent nuclear fuel rods in an underground radioactive waste storage and disposal system according to the present invention.

[0132] In the present invention, the inner wall of the space including the underground temporary storage tank (301), the moving waterway (302), and the water tank storage tank (303) forms a three-layer closed structure having a waterproof ordinary concrete layer (330) on the outermost side, a resin mortar layer (331) inside the ordinary concrete layer, and an ultra-high strength concrete layer (332) inside the resin mortar layer.

[0133] A super high-strength concrete layer (332) is provided between the above-mentioned water tank storage tank and the moving waterway, and a management passage (333) is provided on the upper side thereof.

[0134] At this time, the above ultra-high strength concrete is concrete with a compressive strength of 100 MPa or more, and there may be differences depending on academic standards or countries, and this is not specifically limited.

[0135] A transfer hoist (310) for transferring spent nuclear fuel rods (10) and low- and intermediate-level nuclear waste (50) in a horizontal direction may be provided on the upper side of the space including the above underground temporary storage tank (301), the above moving waterway (302), and the above water tank storage tank (303).

[0136] Additionally, the radioactive waste underground storage and disposal system according to the invention may further include a second transfer device (21) for transferring low- and intermediate-level nuclear waste (50) to the underground storage space (300) and a second vertical transfer passage (hoist, not shown) for transferring the low- and intermediate-level nuclear waste (50) to the underground storage space in a vertical direction.

[0137] The above low- and intermediate-level nuclear waste (50) is transported to a permanent storage facility via a transport hoist (310) provided on the upper side of the underground space.

[0138] As illustrated in FIG. 4, the permanent storage facility (400) may include a second storage space (500) for storing low- and intermediate-level nuclear waste (50) in addition to a first storage space (410) for permanently storing spent nuclear fuel rods (10) cooled in the water tank storage tank (303) after performing stabilization work in the pre-stabilization workshop (304).

[0139] FIG. 6 is a cross-sectional view showing a permanent storage facility for spent nuclear fuel rods in an underground radioactive waste storage and disposal system according to the present invention.

[0140] As shown in the drawing, the first storage space (410) has a three-layer closed structure in which the outermost part of the inner wall is a waterproof ordinary concrete layer (330), a resin mortar layer (331) inside the ordinary concrete layer, and an ultra-high strength concrete layer (332) inside the resin mortar layer.

[0141] The above-described three-layer closed structure may be configured to include a seating space (430) in which a permanent storage container (420) for spent nuclear fuel rods is stored inside, bentonite (31) for filling the permanent storage container (420) within the seating space, a girder (440) made of ultra-high strength concrete that seals the upper part of the seating space, and a resin mortar layer (450) that seals the upper part of the girder.

[0142] At this time, a transfer hoist (310) for transferring a permanent storage container (420) for spent nuclear fuel rods in a horizontal direction may be provided on the upper side of the first storage space (410).

[0143] FIG. 7 is a cross-sectional view showing a fuel rod fixed in a canister that is stored in a permanent storage facility for spent nuclear fuel rods in a radioactive waste underground storage and disposal system according to the present invention.

[0144] As illustrated in the drawing, the permanent storage container (420) for the spent nuclear fuel rod (10) can be formed by fixing the spent nuclear fuel rod (10) inside and sealing the cap (422) by filling the outside with bentonite (421).

[0145] FIG. 8 is a cross-sectional view showing a permanent storage facility (second storage space) for low- and intermediate-level nuclear waste in an underground storage and disposal system for radioactive waste according to the present invention.

[0146] As shown in the drawing, the second storage space (500) has a three-layer closed structure in which the outermost part of the inner wall is a waterproof ordinary concrete layer (330), a resin mortar layer (331) inside the ordinary concrete layer, and an ultra-high strength concrete layer (332) inside the resin mortar layer.

[0147] The above three-layer closed structure may be configured to include a storage space in which a permanent storage container (50) for low- and intermediate-level nuclear waste is stored inside.

[0148] At this time, a transfer hoist (310) for transferring the permanent storage container of the medium- and low-level nuclear waste (50) in a horizontal direction may be provided on the upper side of the second storage space.

[0150] As shown in FIG. 4, in the underground storage and disposal system for radioactive waste according to the present invention, a main passage (600) for accessing the permanent storage facility is provided, and an emergency passage (700) may be additionally provided outside the second storage space (500).

[0152] Additionally, although not shown in the drawing, a single or multiple managed elevators for accessing the underground storage space (300) may be additionally provided.

[0154] In addition, a management passage is formed to allow vehicles or pedestrians to move in one or both directions, and an inspection window is configured to allow visual inspection of the internal condition.

[0155] In addition, a radiation detection sensor and a surveillance camera (CCTV) may be installed in the underground storage space (300) to monitor and manage the internal state from the outside via wired or wireless communication.

[0156] Facilities such as inspection windows and work doors used in the present invention may also be manufactured using resin mortar according to the present invention in a form suitable for the required shape using a formwork.

[0157] In addition, it is preferable to use corrosion-resistant metal materials for all equipment-related materials used in the present invention.

[0158] In addition, the inner concrete surface of the above-mentioned tank can be fixedly installed and replaced with various configurations of known metal liners.

[0159] In addition, the storage cell, overflow structure, and cooling structure of the above-mentioned tank can be replaced with various known configurations and can be applied independently of the vertical transfer structure, multi-barrier storage structure, and resin mortar-based sealing structure, which are core components of the present invention.

[0160] In the present invention, the ultra-high strength concrete may further include a reinforcing member made of a corrosion-resistant metal material to improve load-bearing capacity, flexural strength, shear strength, and impact resistance. The reinforcing member may be manufactured in the form of a reinforcing bar, a lattice material, a mesh material, a plate, or a frame and placed inside a structure, and may include one or more selected from stainless steel including copper, titanium alloy, nickel-based alloy, corrosion-resistant alloy steel, or metal material with a surface anti-corrosion treatment.

[0161] The above ultra-high strength concrete may be placed on one or more of the inner or outer sides of the storage structure, and may be optionally installed in the entire or part of the storage space to improve structural stability, load-bearing capacity, and load distribution against thermal stress.

[0162] In the present invention, it is preferable to use an oil-based resin mortar.

[0163] The resin mortar used in the present invention may be the ultra-high strength resin mortar having multi-functional properties of water-soluble and positive properties proposed by the inventor in the prior registered patent (Republic of Korea Registered Patent No. 10-2106352), or a modified version thereof, and the resin mortar having multi-functional properties of water-soluble and positive properties will be described in detail below.

[0165] The mortar composition of the present invention is characterized by being composed of an ultra-low viscosity resin that contains no volatile organic compounds, is non-chalking, and is composed of a non-polluting resin as the main component.

[0166] The resin mortar having a hydrophilic and hydrophilic function according to the present invention is composed of a main component and a curing component.

[0167] Specifically, the main component comprises 70-90% by weight of one or more resin main components selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5-20% by weight of epoxy resin auxiliary components, 1-5% by weight of a coagulant, and 1-20% by weight of a flame retardant. A resin mortar composition is formed by mixing 10-50% by weight of a curing component, comprising 40-60% by weight of polyoxypropylene diamine, 20-40% by weight of isophorone diamine, 10-20% by weight of polyamide amine, 1-10% by weight of one or more amines selected from triethylenetetraamine and diethylenetriamine, and 1-10% by weight of a curing accelerator, with respect to 100% by weight of the resin liquid main component thus composed, on-site.

[0169] Although additional components such as various reactive diluents and various non-reactive diluents used in the resin mortar composition of the present invention may be included, these are additives for various specific uses and may be added separately, for example, in a composition having a coating or thin film layer, but they are not essential components.

[0171] More specifically, in the present invention, the resin mortar composition comprises a main component containing a polyglycidyl ether resin or a trimethylolpropene triglycidyl ether which is trifunctional, and an amine-based curing component.

[0172] Specifically, it consists of a resin liquid main component comprising 70-90% by weight of one or more resin main components selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5-20% by weight of an epoxy resin auxiliary component, 1-5% by weight of a coagulant, and 1-20% by weight of a flame retardant, and a curing component comprising 40-60% by weight of polyoxypropylene diamine, 20-40% by weight of isophorone diamine, 10-20% by weight of polyamide amine, 1-10% by weight of one or more amines selected from triethylenetetraamine and diethylenetriamine, and 1-10% by weight of a curing accelerator.

[0173] In the present invention, the resin main component and the curing component each comprise 100 parts by weight : 10 to 50 parts by weight to form a mixed component.

[0174] It is preferable to use a resin mortar obtained by mixing 150 to 1000 parts by weight of an inorganic component, including silica sand and inorganic fillers, based on 100 parts by weight of a mixed component obtained by mixing a main component and a curing component containing the above resin main component on-site.

[0175] In the present invention, an emulsifier is prepared in the curing component so that the hydration reaction can be promoted by using water as a diluent after mixing with the main component at the site. The curing component may be composed by including 0.1 to 3 parts by weight of an emulsifier and 3 to 5 parts by weight of a reaction resin based on 100 parts by weight of the curing component, and polymerizing the above or copolymerizing one or more of the Kookdo Chemical product standard names KH-700, KH-701, and H-23 in a range of 1 to 10% by weight based on 100 parts by weight of the curing component.

[0176] The emulsifiers that can be used in the present invention include those disclosed in Korean Registered Patent No. 10-0989942, which was previously filed and registered by the inventors, such as copolymers of polyoxyethylene and polyoxypropylene, copolymers of polyoxyethylene and polyoctylphenyl ether, sodium dodecylbenzene sulfide, etc., but are not necessarily limited thereto; any emulsifier capable of imparting oily and aqueous positive characteristics may be used without limitation.

[0177] In this way, due to the characteristics of having both oil- and water-positive functions in the present invention, even with a minute amount of emulsion polymerization of the curing component, the activation of the curing reaction upon mixing with the resin component leads to increased adsorption and condensation energy at the interface, and the silanol groups capture water, thereby enabling the curing component to perform its function more stably.

[0178] In addition, the resin mortar composition according to the present invention can achieve both oil-based and water-based functions by forming silanol groups and capturing a large amount of water through the activation of condensation power.

[0179] In the present invention, an acrylic resin may be used as the reaction resin.

[0180] The above mixed component may comprise 1 to 50 parts by weight of nano metal powder and nano metal oxide powder, either alone or in combination, based on 100 parts by weight of the main resin component, and may further comprise 1 to 80 parts by weight of an inorganic additive based on 100 parts by weight of the main resin component.

[0181] In addition, to pour the resin mortar composition, 150 to 1000 parts by weight of inorganic materials such as silica sand and inorganic fillers are mixed on-site based on 100 parts by weight of the obtained mixture component to form a mortar mixture that can be used in structures.

[0182] In addition, some crushed stone may be included in addition to the silica sand mentioned above.

[0183] The above epoxy resin may include a diglycidyl-based, triglycidyl-based, tetraglycidyl-based, or polyglycidyl-based epoxy compound having two or more epoxy groups within one molecule. For example, the above epoxy resin is N,N,O-Triglycidyl-p-aminophenol.Triglycidyl p-aminophenol, N,N,O-Triglycidyl-m-aminophenol, Trisphenol methane triglycidyl ether Trihydroxybiphenyl triglycidyl ether, Phloroglucinol triglycidyl ether Trimethylolpropane triglycidyl ether, Glycerol triglycidyl ether Trimethylolethane triglycidyl ether, Propoxylated glycerol triglycidyl ether Triglycidyl isocyanurate, Triglycidyl cyanurate, Cardanol-based triglycidyl epoxy Triglycidyl ether of 2-aminobenzyl alcohol, Triglycidyl ethylene ether of bisphenol A 등의 수지에 골격을 갖는 다관능 글리시딜 에테르 화합물, Polyethylene glycol diglycidyl ether, Resorcinol diglycidyl ether, Thio-Diphenyl diglycidyl ether, Glycerol polyglycidyl ether,Pentaerythritol polyglycidyl ether, Castor oil polyglycidyl ether, Sorbitol polyglycidyl etherN,N-DiglycidylAniline,N,N-Diglycidyl-o-toluidine, Triglycidyl-p-Aminophenol, Tetraglycidyl-diamino diphenyl methane, Tetraglycidyl-m-Xylenediamine 중에서 선택된 1종 이상을 포함할 수 있다.

[0184] In addition, epoxy resins commonly used in the field to which the present invention belongs may be used, and general epoxy resins, chlorine-containing epoxy resins, or tri, tetrafunctional epoxy resins, cyclopolymer resins, phenol novolac resins, cresol novolac epoxy resins, or modified types using compounds that do not contain volatile organic compounds may be used.

[0185] In the present invention, the inorganic filler used in addition to or together with (or optionally) the silica sand is preferably one or more selected from the group consisting of powders such as calcium carbonate, talc, heavy carbon, silica, magma silica composites, and ceramics, but is not limited thereto.

[0186] In the present invention, the flame retardant may be a halogen-based flame retardant, a non-halogen-based flame retardant, a phosphorus-based flame retardant, an antimony-based flame retardant, a bromine-based flame retardant, etc. Specifically, the non-halogen epoxy resin from the Kukdo Chemical product KDP 555 MC series may be replaced with the base resin by weight, and approximately 20% of a non-halogen inorganic material (product APP-263) or approximately 5-10% of antimony trioxide may be mixed into 100 parts by weight of the base resin or 10-30% of the non-halogen inorganic material.

[0187] In the present invention, additives such as coagulants and accelerators may be optionally mixed and used with the main component.

[0188] In the present invention, the coagulant is preferably one or more selected from the group consisting of silicon dioxide aerosol, cellulose, silica gel, sol, galenatite hard anhydrous silica, bentonite, white carbon, and asobest, but is not limited thereto.

[0189] In the present invention, the accelerator that promotes curing may be phenol, nonylphenol, Kukdo Chemical product standard name KH-30, KH-3001 A-399, etc., but is not limited thereto.

[0191] Next, the curing component comprises 40 to 650 weight% of polyoxypropylene diamine, 20 to 40 weight% of polyamide amine, 1 to 10 weight% of one or more amine compounds selected from triethylenetetraamine and diethyltriamine, and 1 to 10 weight% of a curing accelerator.

[0192] In the composition of the above curing component, one or more selected from methylene dianiline, methaxylene diamine, triethylene phentamine, N-aminoethyl piperazine, diethyleneaminopropylamine, M-phenylene diamine, diaminodiphenyl sulfone, and isocyanate may be mixed with polyoxypropylene diamine and used as an adduct with added epoxy, which is a product of copolymerization or heated pressurized condensation reaction of a monomer, dimer, trimer, organic fatty acid and an aliphatic amine. Alternatively, a type in which isophorone diamine, methylene dianiline, and methaxylene diamine are mixed and modified with polyamide amine may be mixed with polyoxypropylene diamine.

[0193] In addition, one or more selected from acid anhydride-based aliphatic tertiary amines, polyamide amines or polypropylene amines, isophorone diamines, methaxylene diamines, diaminodiphenylene pulphon, and 4,4-diaminodiphenylmethane may be mixed, or triethylene tetraamine and diethylene triamine may be subsequently added by adducting with an epoxy, thereby replacing polyoxypropylene diamine in the curing agent composition or partially mixing it.

[0194] In addition, one or more selected from the group consisting of difunctional aromatic glycidyl esters, difunctional glycidyl amines, alicyclic epoxy resins, N,N-diglycidyl aniline, N,N-diglycidyl-o-toluidine, triglycidyl-p-aminophenol, tetraglycidyl-diaminodiphenylmethane, tetraglycidyl-m-xylene diamine, and triglycidyl-m-aminophenol may be used in combination.

[0195] The types of amines that can be used as the above-mentioned curing components are classified and explained as follows.

[0196] 1. Cyclic amine base: Copolymer or adduct of cycloaliphatic amines such as polyoxypropylene diamine, methylene dianiline, metaxylene diamine, triethylenepentamine, N-aminoethyl piperazine, diethyleneaminopropylamine, M-phenylene diamine, and diaminodiphenyl sulfone.

[0197] 2. Aliphatic amine bases: Chemically modified adducts such as diethylenetriamine, triethylenetetramine, and tetraethylenephentamine

[0198] 3. Aromatic amine base: Chemically modified adducts: Chemically modified adducts such as diaminodiphenylene sulfone, 4,4'-diaminodiphenylmethane, etc.

[0199] 4. Polyamide Amine: Polyamide curing agents and epoxy-added adducts resulting from the heated and pressurized condensation reaction of monomers, dimers, and trimers of organic fatty acids and aliphatic amines.

[0200] 5. Acid anhydrides: Adactants of phthalic anhydride, hexahydrophthalic anhydride, and methyl tetrahydrophthalic anhydride

[0202] A resin composition comprising a coagulant, a flame retardant, an accelerator, etc., in the resin component of the present invention is mixed in a flow state of ultra-low viscosity and maintains stable immobility through increased adsorption and condensation energy at the interface by an amine with high reactive activity. This composition can be mixed with silica sand or crushed stone on-site and then poured into a formwork using a machine. At this time, watertightness can be increased by vibrating simultaneously with pouring, and the surface layer can be constructed to have a smooth surface by compression plastering and manual rolling using a honeycomb or brush-shaped roller.

[0203] In addition, it may be applied to leveling work by forming a coating film on the surface of a structure using resin mortar by mixing an appropriate amount of inorganic filler or various inorganic materials including cement and silica sand on various surfaces, and laying, pressing, plastering, or pouring.

[0205] In the present invention, the curing components can be broadly classified into four types: amine-based, polyamine-based, acid anhydride-based and latent-based, and imidazole. Additionally, modified types may be applied to suit various characteristics. Furthermore, in the case of resin mortar, the condensing force must be activated through interaction during the curing reaction when the base resin component and the curing component are mixed on-site in order for the mortar to exhibit its characteristics.

[0206] In addition, a tertiary amine is used as a catalyst in the latent curing component to form silanol groups in the resin and pre-latent it, and a mortar is formed together with silica sand, aggregate, and filler, which can be used to produce a mold for a precast module for a structure requiring high thermal denaturation.

[0207] Furthermore, the function of the mortar is the active reaction resulting from the mixing of resin and curing components. In resin mortar compositions, silanol groups are formed, and these formed silanol groups require an optimal aggregation value. During the curing process, they exhibit a low-exothermic reaction that accelerates the activation of condensation power over a long period. Due to these characteristics, pure water can be added after mixing the curing component with the resin on-site, allowing for the inclusion of a large amount of pure water; consequently, both oil-based and water-based functions can be achieved depending on the required characteristics.

[0208] In addition, by containing a large amount of pure water, it functions as a resin mortar, allowing for smooth mixing with silica sand, fillers, cement, crushed stone, etc., and enables the resin to settle uniformly even under heavy weights, thereby exhibiting stable curing properties.

[0210] Furthermore, the present invention may select one or more of boron carbide, boron nitride, borate, barium sulfate, iron oxide, bismuth oxide, tungsten oxide, aluminum oxide, magnesium oxide, silicon carbide, and mixtures thereof as shielding performance aids for the resin mortar.

[0211] In addition, the resin mortar can be composed of nano metal powder and nano metal oxide powder, either alone or in a mixture.

[0212] In the present invention, the nano metal powder and nano metal oxide powder serve as components that absorb and ultimately eliminate radiation, and are characterized by having nano-sized particles and an internal structure that is porous with a large absorption cross-sectional area.

[0213] In the present invention, the nano metal powder may be one or a mixture of two or more selected from the group consisting of aluminum, titanium, zirconium, scandium, yttrium, cobalt, tantalum, molybdenum, and tungsten.

[0214] In addition, in the present invention, the nano metal oxide powder may be one or more mixtures selected from the group consisting of palladium oxide, iridium oxide, ruthenium oxide, osmium oxide, rhodium oxide, platinum oxide, nickel oxide, cobalt oxide, indium oxide, and titanium oxide.

[0215] In addition, in the present invention, the nano metal powder and nano metal oxide powder may be used in an unprocessed form, but it is preferable to use a coated form to prevent them from fusing together within the composition, and specifically, it is preferable to use a form with a surface coated with graphite oxide.

[0216] In the present invention, the graphite oxide is one or more types of graphite selected from natural graphite, plate graphite, artificial graphite, expanded graphite, etc., treated with an oxidizing agent such as sulfuric acid, nitric acid, potassium permanganate, or calcium chlorate. The method of coating the surface of the nano metal powder or nano metal oxide powder with graphite oxide is to first mix the nano metal powder or nano metal oxide powder and the graphite oxide in a certain ratio, add a small amount of water to form a slurry, and then irradiate with ultraviolet rays so that the graphite oxide combines with the nano metal powder or nano metal oxide powder to form a coating layer on the surface.

[0217] Nano metal powders and nano metal oxide powders with a coating layer formed on their surfaces in this way are not easily re-fused with each other, thereby improving dispersion stability.

[0218] However, the scope of the present invention includes not only nano metal powder or nano metal oxide powder with a coating layer formed thereon, but also powders that have undergone other treatments and powders that have not been treated, as they are.

[0220] Furthermore, the present invention may additionally include inorganic additives to enhance the flame-retardant function of the structure.

[0221] In addition, the present invention may further include, but is not limited to, bromine-based flame retardants, non-halogen-based flame retardants, phosphorus-based flame retardants, etc., in addition to the above-mentioned inorganic additives.

[0222] The above-mentioned inorganic additive can serve to provide flame-retardant or non-combustible functions in the event of a fire.

[0223] In addition, the above-mentioned inorganic additive may use salts such as metal hydroxides or carbonates, and may use one or more mixtures selected from the group consisting of powders such as calcium hydroxide, calcium carbonate, magnesium hydroxide, magnesium carbonate, barium chloride and barium sulfate, ceramics, and diatomaceous earth. In addition, all inorganic materials in powder form may be mixed.

[0224] In the present invention, it is preferable for performance optimization that the inorganic additive be included in a range of about 1 to 80 parts by weight based on 100 parts by weight of the base resin.

[0225] In addition, the present invention includes silica sand in a certain proportion to form the resin mortar composition. The silica sand may be one or more types of silica sand selected from the group consisting of artificial silica sand, natural silica sand, etc., and it is preferable to include 150 to 1,000 parts by weight per 100 parts by weight of the base resin.

[0226] In addition, since it is used for structures, general crushed stone, aggregate, and wood chips may be included in addition to silica sand, and the size can be from 0.5 to 30 mm.

[0227] In addition, it may include silica sand, crushed stone, aggregate, wood chips, as well as metal chips, glass chips, and bead-shaped materials, and the size can be used from 0.5 to 30 mm.

[0228] In addition, the present invention may further include functional fibers to further enhance physical properties such as tensile strength and impact strength of the resin mortar composition.

[0229] In the present invention, the functional fiber may be one type or a mixture of two or more types selected from glass fiber, aramid fiber, and carbon fiber.

[0230] The above functional fiber may use fiber chips with a length in the range of about 2 to 10 mm.

[0231] In the present invention, it is preferable that the functional fiber additionally include about 1 to 50 parts by weight based on 100 parts by weight of the main resin component.

[0232] For other components not specifically exemplified in the present invention, reference may be made to the inventor's prior patents No. 10-0989942 and No. 10-1811350, which may be interpreted as being included within the scope of the present invention by reference.

[0233] The resin mortar formed according to the present invention can secure excellent structural integrity when applied to the vertical transport passage according to the present invention, and has the advantage of completely resolving the problems of conventional concrete, such as waterproofing / crack stability and shrinkage / expansion stability. Accordingly, in the radioactive waste underground storage and disposal system according to the present invention, it can be applied not only to the vertical transport passage but also to the outer walls of the underground storage space and sealing materials during decommissioning, thereby exhibiting seismic resistance in addition to radiation shielding, bulletproofing, and protection functions, which has the advantage of improving the structural stability of the underground storage space. Explanation of the symbols

[0235] 10: Spent nuclear fuel rods 20: Underground reservoirs of existing nuclear power plants 21 : Second vertical transfer passage 100 : Transfer device 200: Vertical transfer passage 210: Module 220: Guide rail 230: Sealing cap 240 : Resin mortar 300 : Underground storage space 301: Underground temporary storage tank 302: Transfer channel 303: Water storage tank 304: Post-processing space 310: Transfer device 330: General concrete layer 331: Resin mortar layer 332: Ultra-high strength concrete layer 333 : Management Channel 400: Permanent storage facility 410: First storage space 420: Permanent storage container for spent nuclear fuel rods 421 : Bentonite 422 : Cap 423 : Canest 430 : Landing space 431 : Bentonite 440 : Girder 450 : Resin mortar layer 500 : Second storage space 600 : Main passage 700 : Emergency Exit

Claims

Claim 1 A transfer device for transferring spent nuclear fuel rods stored in an internal reservoir of an existing nuclear power plant or sealed in a canister in a reactor; a vertical transfer passage for transferring the spent nuclear fuel rods vertically to an underground temporary storage tank; An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste, comprising: an underground storage space for storing spent nuclear fuel rods transported through the vertical transport passage; wherein the underground storage space comprises an underground temporary storage tank for temporarily storing spent nuclear fuel rods transported through the vertical transport passage, a moving channel for transporting spent nuclear fuel rods stored in the underground temporary storage tank in a horizontal direction, a water tank storage tank for cooling spent nuclear fuel rods transported through the moving channel, and a permanent storage facility for permanently storing spent nuclear fuel rods cooled in the water tank storage tank; wherein the vertical transport passage comprises a structure in which a plurality of modules formed of resin mortar are connected in a vertical direction, a guide rail is formed inside the vertical transport passage, an elevator-type transport device that moves along the guide rail is installed inside the vertical transport passage, and an automatically opening and closing sealing cap is provided on the upper part of the vertical transport passage, and wherein the vertical transport passage is permanently sealed by resin mortar upon decommissioning of the nuclear power plant. Claim 2 delete Claim 3 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, wherein the vertical transfer passage is formed of precast modules, the precast modules are manufactured into a standardized shape using a mold and assembled on-site, and a sealing structure is formed between the precast modules. Claim 4 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, wherein the guide rail has a structure extending in a vertical direction and is arranged in a single or multiple numbers at the inner corner of the vertical transfer passage. Claim 5 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste, characterized in that, in claim 4, the guide rail has a structure coupled to a roller or a guide cap, and the roller and the guide cap are configured to form a vibration-free structure. Claim 6 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste, characterized in that, in claim 1, the elevator-type transfer device comprises a platform for carrying a storage container and has a structure that is raised and lowered by a drive device, the drive device comprises a wire, chain, hydraulic, or electric drive method, and the elevator-type transfer device comprises a fall prevention device and a speed control device. Claim 7 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, characterized in that the sealing cap has a structure that opens and closes automatically, has a structure that allows for repeated opening and closing, and is configured to be remotely controllable. Claim 8 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, wherein the sealing caps are composed of a single or multiple caps, form multiple barrier walls, and a filling layer is formed between the multiple sealing caps. Claim 9 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, characterized in that the underground storage space is configured such that a work space and a storage space are separated. Claim 10 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, wherein the inner wall of the space including the underground temporary storage tank, the moving channel, and the water tank storage tank forms a three-layer closed structure in which the outermost layer is a waterproof ordinary concrete layer, the inner layer of the ordinary concrete layer is a resin mortar layer, and the inner layer of the resin mortar layer is an ultra-high-strength concrete layer, and between the water tank storage tank and the moving channel, an ultra-high-strength concrete layer is provided on the outside and a resin mortar layer is provided on the inside, and a management passage is provided on the upper side thereof, and a transfer hoist for transporting spent nuclear fuel rods and low- and intermediate-level nuclear waste in a horizontal direction is provided on the upper side of the space including the underground temporary storage tank, the moving channel, and the water tank storage tank. Claim 11 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste, characterized in that, in claim 1, it further comprises a second transfer device for transferring low- and intermediate-level nuclear waste to the underground storage space and a second vertical transfer passage for transferring the low- and intermediate-level nuclear waste to the underground storage space in a vertical direction. Claim 12 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, characterized in that, in addition to a first storage space for permanently storing spent nuclear fuel rods cooled in the storage tank, the permanent storage facility includes a second storage space for storing low- and intermediate-level nuclear waste, which is separated into a separate space. Claim 13 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 12, wherein the first storage space comprises a three-layer closed structure in which the outermost part of the inner wall is a waterproof ordinary concrete layer, a resin mortar layer inside the ordinary concrete layer, and an ultra-high strength concrete layer inside the resin mortar layer, wherein the system comprises a seating space in which a permanent storage container for spent nuclear fuel rods is stored inside the three-layer closed structure, bentonite for filling the permanent storage container within the seating space, a girder made of ultra-high strength concrete that seals the upper part of the seating space, and a resin mortar layer that seals the upper part of the girder, wherein a transfer hoist for transporting the permanent storage container for spent nuclear fuel rods in a horizontal direction is provided on the upper side of the first storage space. Claim 14 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 13, wherein the permanent storage of the spent nuclear fuel rods is characterized by being composed of a canister in which bentonite or bentonite containing silica sand is filled to a certain thickness on the bottom surface, leveled, and then the container is fixed, and the outside is again filled with bentonite or bentonite containing silica sand and sealed. Claim 15 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 12, wherein the second storage space comprises a three-layer multi-barrier closed structure in which the outermost part of the inner wall is a waterproof ordinary concrete layer, a resin mortar layer inside the ordinary concrete layer, and an ultra-high-strength concrete layer inside the resin mortar layer, and comprises a storage space in which a permanent storage container for low- and intermediate-level nuclear waste is stored inside the three-layer multi-barrier closed structure, and wherein a transfer hoist is provided on the upper side of the second storage space to transfer the permanent storage container for low- and intermediate-level nuclear waste in a horizontal direction. Claim 16 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 12, characterized in that a main passage for accessing the permanent storage facility is provided, and an emergency passage is additionally provided outside the second storage space. Claim 17 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, characterized in that a single or multiple managed elevators for accessing the underground storage space are additionally provided. Claim 18 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste, characterized in that, in claim 1, the resin mortar is an oil-based resin mortar. Claim 19 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 18, wherein the oil-based resin mortar comprises: a resin liquid main component comprising 70-90% by weight of one or more resin main components selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5-20% by weight of an epoxy resin auxiliary component, 1-5% by weight of a coagulant, and 1-20% by weight of a flame retardant; and a curing component comprising 40-60% by weight of polyoxypropylene diamine, 20-40% by weight of isophorone diamine, 10-20% by weight of polyamide amine, 1-10% by weight of one or more amines selected from triethylenetetraamine and diethylenetriamine, and 1-10% by weight of a curing accelerator. Claim 20 An underground storage and disposal system for integrated storage of spent nuclear fuel and radioactive waste according to claim 1, characterized in that a management passage is formed to allow vehicles or pedestrians to move in one direction or both directions, and an inspection window is configured to allow visual inspection of the internal condition.

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