Nuclear waste storage facility using resin mortar composition having ultrahigh strength and high durability and construction method therefor

Abstract

The present invention comprises a nuclear waste storage facility in which is formed a storage tank that is formed with an overall circular dome shape and includes: a waterproof non-woven fabric installed on an excavated tunnel wall surface and shotcrete poured on the outside thereof; a first resin mortar poured along the excavated surface on the outside of the shotcrete layer; a second resin mortar poured along the excavation surface on the outer surface of the first resin mortar, wherein the bottom part is formed by pouring a third resin mortar in the middle lower part of the storage tank or compacting aggregate, and a nuclear waste burying facility is installed in the bottom part. The nuclear waste burying facility is characterized in that the nuclear waste burying facility is formed by installing nuclear waste storage tanks at regular intervals in the bottom part, nuclear waste is directly stored in each storage tank or is stored by burying nuclear waste storage containers. and the upper end portion of the bottom part is sealed by using a fourth resin mortar, and the bottom surface and the side surface portion of the nuclear waste burying facility are connected to be connected to the second resin mortar at the upper portion to seal the inside, and the first resin mortar and the second resin mortar are installed to be fixed to a ground joint surface of the excavated tunnel wall surface by using a fixing member.

Description

Nuclear waste storage facility using a resin mortar composition with ultra-high strength and high seismic performance and its construction method

[0001] The present invention relates to a technology for constructing a storage facility for high-level as well as intermediate-level nuclear waste using a resin mortar composition having ultra-high strength and high seismic performance, and more specifically, to a technology for constructing a nuclear waste storage facility using a mortar composition having ultra-high strength and high seismic performance that can be applied to structures for nuclear waste storage facilities by overcoming the limitations of concrete structures.

[0002] Nuclear waste generated from nuclear power plants is divided into high-level nuclear waste and low- and intermediate-level nuclear waste, which must be stored in permanent storage facilities after being temporarily stored for a certain period of time.

[0003] Conventional radioactive nuclear waste was stored in storage facilities with outer walls made of reinforced concrete, usually more than 4 meters thick, to prevent external leakage of radiation.

[0004] However, storage facilities constructed of reinforced concrete face limitations: the steel is susceptible to corrosion, internal cracking can occur during the curing process, and potential deterioration can occur due to crack growth and propagation. This makes it difficult to construct facilities that exceed the expected service life of the concrete. Furthermore, reinforced concrete facilities lack significant tensile strength, making them susceptible to earthquake collapse. This has led to criticism that reinforced concrete structures are inadequate for nuclear waste storage.

[0005] Previously, a method proposed, like the Finnish example, involved digging a cavern (tunnel) approximately 500 meters underground into the bedrock to store nuclear waste. However, concerns have been raised that these underground tunnels may be inadequately prepared for various external damage, such as ground deformation caused by earthquakes or tunnel collapse.

[0006] In addition, both existing reinforced concrete storage facilities and underground tunnel storage facilities have the problem of having to deal with groundwater generated in the ground layer, which has led to problems such as excessive costs continuously being incurred to discharge it and maintenance issues.

[0007] Therefore, permanent storage facilities for radioactive nuclear waste must not only function as radioactive waste disposal facilities, but also have high tensile strength to withstand high-intensity earthquakes and durability to ensure that the facilities can be maintained permanently without deterioration.

[0008] However, existing permanent storage facilities do not yet have these capabilities and are limited to using reinforced concrete facilities with limited lifespans or underground cave facilities that are spatially constrained and vulnerable to earthquakes, so they are not a fundamental solution.

[0009] If you look at the related technologies,

[0010] First, Korean Patent No. 10-1712879 relates to concrete for neutron shielding of a primary protective wall of a nuclear power plant and a method for manufacturing the same, wherein the concrete for neutron shielding of a primary protective wall of a nuclear power plant is installed to surround an area where neutrons are generated to prevent neutrons from leaking to the outside, wherein the hydrogen (H) component contained in the HB shielding aggregate formed of boron trioxide, polymethyl methacrylate (PMMA), and polyethylene (PE) acts to scatter neutron rays, and the boron (B) component acts to absorb neutrons, thereby improving the neutron shielding performance of neutrons, and further, by forming the HB shielding aggregate to wrap boron (B) with polymethyl methacrylate (PMMA) and polyethylene (PE), the reduction in strength development that occurs when boron (B) is wrapped with polyethylene (PE) can be prevented, and the phenomenon of boron (B) dissolution can be reduced. Disclosed are concrete for neutron shielding and a method for manufacturing the same.

[0011] In addition, Korean Patent No. 10-1621881 relates to a low-radiation cement material for a protective wall of a nuclear power plant and a method for manufacturing the same, and relates to a low-radiation cement material for a protective wall of a nuclear power plant and a method for manufacturing the same, which has excellent low-radiation properties by minimizing the content of Eu and Co, which are major components in cement that are radiated by neutrons, and is manufactured by grinding clinker made by mixing 79 to 81 wt% of limestone, 12 to 18 wt% of clay raw material, 2 to 5 wt% of ladle slag, and the remainder of silica together with gypsum, and proposes a cement material and a method for manufacturing the same, characterized in that the contents of Co (cobalt) and Eu (europium) are 7 ppm or less and 0.5 ppm or less, respectively.

[0012] In addition, Korean Patent No. 10-1508957 relates to a radiation shielding concrete composition, which uses industrial by-products to provide higher shielding performance for radiation such as gamma rays and neutron rays than existing concrete shields, and thus can contribute to the formation of shielding walls for nuclear power plant facilities, hospital facilities, social infrastructure, etc., and is both environmentally friendly and economical. In addition, steelmaking slag is replaced with coarse aggregate and fine aggregate, and while maintaining the strength of shear resistance, the unit weight is maintained to block radiation, and at the same time, high-density polyethylene included as fine aggregate mixes well with concrete and scatters radiation, thereby contributing to double radiation shielding. In particular, since the shielding rate is higher than that of a general concrete composition, the thickness of the shielding wall can be reduced while maintaining the same shielding effect, thereby increasing the exclusive area. The present invention proposes a construction technology for a radiation shielding concrete facility.

[0013] In this way, most existing technologies only propose technologies regarding compositions that can improve the radioactive waste disposal performance of reinforced concrete radioactive waste disposal facilities. However, there has been no technology to date that can fundamentally solve and prevent potential problems as a permanent storage facility for nuclear waste by providing a corrosion-free facility and earthquake-resistant performance with excellent tensile strength, separate from the radioactive waste disposal performance.

[0014] [Prior Art Literature]

[0015] [Patent Document]

[0016] 1. Republic of Korea Patent No. 10-1621881, "Low-radiation cement material for nuclear power plant protective walls and its manufacturing method."

[0017] 2. Republic of Korea Patent Publication No. 10-2012-0132854, "Composition for Neutron Shielding Containing Foamed Metal"

[0018] 3. Republic of Korea Patent No. 10-0779789 "Epoxy resin composition with high neutron shielding ability and transparent neutron shielding material cured from the epoxy resin composition"

[0019] 4. Republic of Korea Patent No. 10-1688646, "Double Shielding Concrete for High-Level Neutron Shielding and Manufacturing Method Thereof."

[0020] 5. Republic of Korea Patent No. 10-1508957 "Radiation Shielding Concrete Composition"

[0021] 6. Republic of Korea Patent No. 10-1712879, "Concrete for Neutron Shielding of the Primary Protective Wall of a Nuclear Power Plant and Its Manufacturing Method"

[0022] The present invention was developed to improve the situation of the prior art as described above, and while maintaining the basic radiation shielding performance, unlike existing reinforced concrete facilities, it does not corrode or deteriorate, so it is not limited by the lifespan of the facility, and at the same time, it has excellent tensile strength and seismic performance, thereby fundamentally solving and preventing potential problems as a permanent storage facility for nuclear waste generated from not only small-sized reactors (SMRs) but also large-scale reactors. We would like to propose a construction technology for a new-level nuclear waste storage facility.

[0023] In addition, the present invention has low viscosity and smooth flowability, so that the flowability is appropriately controlled during the hardening reaction, and various inorganic materials and silica sand including an appropriate amount of cement are smoothly mixed, and uniform watertightness is achieved inside the structure after casting. The characteristics of this composition are that it is composed of a main component of a multifunctional resin and an amine-based hardener component, so that it has ultra-high strength properties such as compressive strength and tensile strength, and a rapid process processing is possible, so that it can be used as a structure for a nuclear waste disposal facility by replacing existing concrete, alone or together with existing concrete, and it can also have an earthquake-resistant function, so that it can be used as an earthquake-resistant structure, and it aims to provide a technology for constructing a facility that can safely and permanently store low- and intermediate-level radioactive nuclear waste and high-level radioactive nuclear waste generated from not only small reactors (SMRs) but also large reactors.

[0024] In order to achieve the above-mentioned task, the present invention

[0025] Waterproof non-woven fabric installed on the wall of an excavated tunnel and shotcrete poured on the outside;

[0026] First resin mortar poured along the excavated surface on the outside of the shotcrete layer; and

[0027] A storage container is formed in the shape of a circular dome by pouring a second resin mortar along the excavated surface on the outer surface of the first resin mortar;

[0028] A nuclear waste storage facility characterized in that a bottom is formed by pouring a third resin mortar or compacting aggregate in the middle lower part of the above storage facility, and a nuclear waste landfill facility is installed in the bottom part.

[0029] The above nuclear waste landfill facility is formed by installing nuclear waste storage tanks at regular intervals on the floor, directly storing nuclear waste in each storage tank or burying nuclear waste storage containers, and sealing the upper part of the floor using a fourth resin mortar, thereby forming a nuclear waste landfill facility.

[0030] The bottom and side of the above nuclear waste disposal facility are connected to the second resin mortar above, so that the interior is sealed.

[0031] The above-mentioned first resin mortar and second resin mortar are provided as a nuclear waste storage facility characterized in that they are installed to be fixed to the ground joint surface of the excavated tunnel wall using a fixing member.

[0032] In one embodiment of the present invention,

[0033] The above nuclear waste disposal facility is characterized in that it is formed by pre-filling the lower part of each nuclear waste storage tank with bentonite, storing nuclear waste therein, then filling the upper part with bentonite, inserting and fixing a sealed storage container, and sealing the surface of the nuclear waste storage tank with resin mortar or a separate resin mortar cap.

[0034] Additionally, in one embodiment of the present invention,

[0035] The above nuclear waste landfill facility is characterized in that it is formed by pre-inserting and fixing a sealed storage container for storing nuclear waste in each nuclear waste storage tank without pre-filling with bentonite, injecting the first resin mortar around the storage container, and sealing the surface of the nuclear waste storage tank with resin mortar or a separate resin mortar cap.

[0036] Additionally, in one embodiment of the present invention,

[0037] Each of the above nuclear waste storage tanks is formed in a circular or square shape, and its periphery is characterized by being surrounded by the fourth resin mortar.

[0038] Additionally, in one embodiment of the present invention,

[0039] The above first resin mortar, third resin mortar, and fourth resin mortar are oil-based or water-based resin mortars, and the second resin mortar layer is characterized in that it is water-based resin mortar.

[0040] Additionally, in one embodiment of the present invention,

[0041] The above nuclear waste storage container is characterized in that high-level nuclear waste is stored therein.

[0042] Additionally, in one embodiment of the present invention,

[0043] The above nuclear waste storage container is characterized in that it is manufactured using a mold on the inner surface of a container made of a circular or square copper pipe, and is manufactured by installing a quaternary resin mortar on the inner surface of the container in a non-deformable manner.

[0044] Additionally, in one embodiment of the present invention,

[0045] It is characterized by loading a container containing low- and intermediate-level nuclear waste on the upper part of the formed floor.

[0046] Additionally, in one embodiment of the present invention,

[0047] The space for burying a storage container for storing high-level nuclear waste is characterized in that it is formed inside the nuclear waste storage facility.

[0048] Additionally, in one embodiment of the present invention,

[0049] The above nuclear waste storage facility is characterized by being formed in an overall I shape.

[0050] Additionally, in one embodiment of the present invention,

[0051] The above nuclear waste storage facility is characterized by being formed in an overall T-shape or cross shape.

[0052] In addition, in one embodiment of the present invention, it is characterized in that a management passage is formed between the wall surface of the formed dome-shaped storage and the square-shaped sealing facility.

[0053] At this time, the management passage is formed so that the vehicle can move in one direction or two directions, and is characterized by having an inspection window configured so that the internal condition can be visually inspected.

[0054] Additionally, in one embodiment of the present invention,

[0055] The interior connected in the above square shape is characterized by installing a radiation detection sensor and a surveillance camera (CCTV) to monitor and manage the internal status through wired and wireless communication from the outside.

[0056] In one embodiment of the present invention,

[0057] The above-mentioned oil-based resin mortar comprises a resin liquid main component comprising 70 to 90 wt% of at least one resin main component selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5 to 20 wt% of an epoxy resin auxiliary component, 1 to 5 wt% of a coagulant, and 1 to 20 wt% of a flame retardant; and

[0058] A resin mortar is manufactured, characterized by comprising a curing component including 40 to 60 wt% of polyoxypropylene diamine, 20 to 40 wt% of polyamide amine, 1 to 10 wt% of at least one amine selected from triethylenetetramine and diethylenetriamine, and 1 to 10 wt% of a curing accelerator.

[0059] It is characterized by being composed by mixing 5 to 50 parts by weight of cement component and 500 to 750 parts by weight of silica sand based on 100 parts by weight of the above-mentioned manufactured resin mortar.

[0060] Additionally, in one embodiment of the present invention,

[0061] The above water-based resin mortar is characterized in that it is obtained by adding 10 to 100 parts by weight of water based on 100 parts by weight of the above oil-based resin mortar composition.

[0062] In addition, in order to achieve the above task, the present invention

[0063] The first step is to excavate a tunnel, install waterproof non-woven fabric on the wall of the excavated tunnel, and pour and harden shotcrete on the outside;

[0064] A second step of forming a storage facility in the shape of an overall circular dome by spreading the first resin mortar along the excavated surface on the outside of the above-mentioned hardened shotcrete layer;

[0065] A method for constructing a nuclear waste storage facility, characterized in that a bottom is formed by pouring a third resin mortar or compacting aggregate in the middle lower part of the storage facility, and a nuclear waste landfill facility is installed in the bottom part.

[0066] The above nuclear waste landfill facility is formed by installing nuclear waste storage tanks at regular intervals on the floor, directly storing nuclear waste in each storage tank or burying and storing nuclear waste storage containers, and resealing the upper part of the floor using a fourth resin mortar, thereby forming a nuclear waste landfill facility.

[0067] The bottom and side of the above nuclear waste disposal facility are connected to the second resin mortar above, so that the interior is sealed.

[0068] The present invention provides a method for constructing a nuclear waste storage facility, characterized in that the first resin mortar and the second resin mortar are installed so as to be fixed to the ground joint surface of the excavated tunnel wall using a fixing member.

[0069] The nuclear waste storage facility according to the present invention can exhibit sufficient shielding performance even when installed to a thickness of about 1 meter without having to be constructed to a thickness of 4 meters or more like conventional reinforced concrete, and while it basically retains shielding performance, unlike conventional reinforced concrete facilities, it does not corrode or deteriorate, so it is not subject to restrictions on the lifespan of the facility, and at the same time, it has excellent tensile strength and seismic performance, so it is a new-level nuclear waste storage facility that can fundamentally solve and prevent potential problems as a permanent storage facility for nuclear waste generated from not only small-sized reactors (SMRs) but also large-scale nuclear reactors.

[0070] The resin mortar used in the present invention has a composition using a multifunctional resin and has the characteristics of being both oily and water-soluble, so that it can be configured using the properties of each of the oily and water-soluble properties, and can be used by mixing a large amount of water through interaction in cross-linking, and due to these characteristics, it can perform the function of a mortar by mixing it with cement, silica, and aggregate, so that it can be used in nuclear waste storage structures as a substitute for existing concrete. In addition, the resin mortar has low viscosity and smooth flowability, and its flowability is appropriately controlled during the hardening reaction to smoothly mix various inorganic substances and silica sand including an appropriate amount of cement, and to achieve uniform watertightness inside the structure after casting, and it has ultra-high strength properties such as compressive strength and tensile strength as it is composed of a main component and an amine-based hardener component, and it allows for rapid processing, so that it can be used as a nuclear waste facility structure by replacing existing concrete, alone or together with existing concrete, and it can also have an earthquake-resistant function, so that it can be used as an earthquake-resistant structure, and it can construct a facility that can safely and permanently store low- and intermediate-level radioactive nuclear waste and high-level radioactive nuclear waste generated from not only small reactors (SMRs) but also large reactors.

[0071] In addition, resin mortar has a structural characteristic that can capture water from the surface layer by the interaction during the curing reaction with the number and concentration of functional groups controlled, and the energy of adsorption and condensation is activated in the cross-linking with amine, and due to this characteristic, it has the characteristic of being easy to use even when mixed with a large amount of water. In addition, by using water-based resin mortar with a water content of 10% or more and up to 100% at the time of mortar manufacturing in a certain area, it is possible to achieve an eco-friendly non-combustible and semi-combustible function that does not generate gas, and it can control the heat that may be generated from radioactive nuclear waste with a more stable function than existing concrete in heat conduction and fracture due to direct fire, and even when the above water-based resin mortar is used, smooth curing and hydration reactions are possible, and compatibility and compatibility with the main components can be completely secured.

[0072] In addition, in the resin mortar composition according to the present invention, the epoxide main component having a multifunctional group and the amine-based curing component have a bonding force formed by non-reduction and substitution, and a structure in which the N of the curing component is formed by substitution with OH, and the composition does not use volatile organic solvents, emulsifiers, plasticizers, anti-foaming agents, etc., so that the bonding force is weakened by cross-linking after hardening or the causative substances that can remain inside after hardening and promote deterioration are fundamentally blocked, thereby satisfying the conditions for continued strength maintenance. In addition, unlike existing mortars or concrete, it can be constructed without reinforcing bars, so that it can exhibit sufficient required physical properties such as tensile strength and compressive strength, and accordingly, problems such as rust caused by reinforcing bars, crack expansion, and expansion due to spalling can be solved.

[0073] In addition, the resin mortar composition according to the present invention can greatly improve earthquake resistance due to its ultra-high strength characteristics, and can be expected to be useful in shielding performance including waterproof performance due to its non-conductive characteristics and high density, integrity, and sealing properties, so that it can be applied to safety structures such as nuclear power plants and nuclear waste storage containers and treatment plants, and since its performance can be maintained permanently rather than having a certain lifespan like existing concrete, it can be used as a permanent storage facility for nuclear waste.

[0074] In addition, the resin mortar composition according to the present invention can be prepared by adding a flame retardant in the case of oil-based composition, but by forming a structure together with inorganic cement, filler, silica sand, and aggregate in a subsequent process, flame retardancy, semi-fireproof, and non-combustible performance are possible depending on the selective content of resin or inorganic material, and in the case of water-based composition, by forming a structure by mixing inorganic cement, silica sand, and aggregate with the weight of water and existing concrete composition, it can exhibit a semi-fireproof or non-combustible function without adding a separate flame retardant.

[0075] In addition, the present invention can store not only low- and intermediate-level nuclear waste but also high-level nuclear waste, and has the advantage of being able to be inspected and managed from the outside by installing a management passageway with a radiation inspection sensor and a surveillance camera (CCTV) inside, and continuous post-management is possible through a wired and wireless network.

[0076] The nuclear waste storage facility according to the present invention can completely block external leakage of radiation through at least four stages of overlapping blocking, firstly by blocking radiation leakage through the nuclear waste storage container, secondly by blocking through the resin mortar of the inner wall of the storage tank, thirdly by blocking through the outer wall of the storage tank, and fourthly by blocking through the tunnel wall.

[0077] In addition, in developed countries such as the United States and Europe, the provision of a nuclear waste disposal site near a nuclear power plant is a prerequisite for the construction of a nuclear power plant, and when the resin mortar and construction method according to the present invention are used, stability such as earthquake resistance, radiation suppression, and non-combustibility as well as permanent durability can be secured, and since construction is easy near a nuclear power plant, there is an effect of being able to satisfy the essential requirements for the construction of the nuclear power plant.

[0078] In addition, a method is currently being used in which nuclear fuel rods are cooled by immersing them in a cooling reservoir for a certain period of time and then stored in a temporary storage tank. However, in the case of using the resin mortar according to the present invention, a facility can be constructed simultaneously to install a connecting passageway underground or above ground from the nuclear fuel rod cooling reservoir and store them in a high-level or low-intermediate-level storage facility, thereby having the advantage of integrating nuclear waste storage facilities along with the construction of a nuclear power plant.

[0079] Figure 1a is a cross-sectional view showing the overall shape of a nuclear waste storage facility according to the present invention, and is a drawing showing the process of burying a nuclear waste storage container.

[0080] Figure 1b is a cross-sectional view showing the overall shape of a nuclear waste storage facility according to the present invention, and is a drawing showing the state after a nuclear waste storage container is buried.

[0081] Figure 2 is a drawing showing a process of sealing nuclear waste in a nuclear waste storage container buried in a nuclear waste storage facility according to the present invention.

[0082] Figure 3 is a drawing showing a process for manufacturing a nuclear waste storage container (circular) to be buried in a nuclear waste storage facility according to the present invention.

[0083] Figure 4 is a drawing showing a process for manufacturing a nuclear waste storage container (square) to be buried in a nuclear waste storage facility according to the present invention.

[0084] Figure 5 is a schematic drawing showing a nuclear waste storage container buried in a nuclear waste storage facility according to the present invention.

[0085] Hereinafter, the present invention will be described in more detail.

[0086] FIG. 1a is a cross-sectional view showing the overall shape of a nuclear waste storage facility according to the present invention, and is a drawing showing the process of burying a nuclear waste storage container, and FIG. 1b is a cross-sectional view showing the overall shape of a nuclear waste storage facility according to the present invention, and is a drawing showing after a nuclear waste storage container is buried.

[0087] In addition, FIG. 2 is a drawing showing a process of sealing nuclear waste in a nuclear waste storage container buried in a nuclear waste storage facility according to the present invention, FIG. 3 is a drawing showing a process of manufacturing a nuclear waste storage container (circular) buried in a nuclear waste storage facility according to the present invention, and FIG. 4 is a drawing showing a process of manufacturing a nuclear waste storage container (square) buried in a nuclear waste storage facility according to the present invention.

[0088] As shown in the drawing, the nuclear waste storage facility according to the present invention is constructed by excavating a tunnel and constructing it inside the excavated tunnel. Basically, there is no difference from a conventional general tunnel in that a waterproof non-woven fabric (20) is installed on the wall surface (10) of the excavated tunnel and shotcrete (30) is poured on the outside and hardened.

[0089] However, the present invention is characterized in that after constructing the shot creek, the resin mortar proposed by the inventor is poured along the excavated surface on the outside thereof.

[0090] As shown in the drawing, a first resin mortar (40) is laid on the outer surface of the formed shotcrete to form a resin mortar layer.

[0091] The above first resin mortar can optionally be an oil-based resin mortar without water or a water-based resin mortar with water, and it is preferable that the thickness be constructed in the range of 1,000 to 1,500 mm.

[0092] Next, a second resin mortar (50) is laid along the excavated surface on the outer surface of the first resin mortar constructed above to form a resin mortar layer.

[0093] At this time, it is preferable to use a water-based resin mortar in which a certain ratio of water is mixed into the oil-based resin mortar to improve the fire resistance of the second resin mortar (50).

[0094] It is desirable that the construction thickness of the above second resin mortar be in the range of 50 to 1,000 mm.

[0095] In this way, waterproof non-woven fabric, shotcrete, first resin mortar, and second resin mortar are constructed to form a storage facility in the shape of an overall circular dome.

[0096] Next, a third resin mortar (60) is poured or aggregate is compacted into the middle lower portion of the storage area to form a bottom portion. A nuclear waste disposal facility (70), which will be described later, is installed in the bottom portion.

[0097] The above nuclear waste disposal facility (7) installs nuclear waste storage tanks (71) at regular intervals on the floor, and stores nuclear waste directly in each storage tank or stores it by burying a separately manufactured nuclear waste storage container (72).

[0098] The above nuclear waste usually refers to spent nuclear fuel rods (high-level nuclear waste) or various wastes other than nuclear fuel rods generated from nuclear power plants (low- and intermediate-level nuclear waste).

[0099] Next, the upper part of the above-mentioned bottom part is sealed using the fourth resin mortar (80) to form a nuclear waste landfill facility. At this time, an additional resin mortar (80-1) can be formed on top of the fourth resin mortar (80).

[0100] Next, the bottom and side surfaces of the nuclear waste disposal facility formed above are interconnected to the second resin mortar (50) above, thereby sealing the interior. At this time, it is preferable that the connection to the second resin mortar (50) be formed so that the cross-sectional shape is approximately square.

[0101] As shown in the drawing, a moving means such as a hoist can be installed on the upper part of the storage facility to move nuclear waste or a nuclear waste storage container.

[0102] At this time, it is preferable that the first resin mortar and the second resin mortar are installed so as to be fixed to the ground joint surface of the excavated tunnel wall using a fixing member (120, e.g., rock bolt). In addition, it is preferable that the fixing member is formed of a copper material.

[0103] By configuring it in this way, as shown in the drawing, it is configured in an overall circular dome shape, and a structure is formed in which a total of three layers of resin mortar are formed on the wall surface and at least two layers are formed on the floor surface.

[0104] By forming a structure like this, low-level nuclear waste can be stored by loading containers containing low-level nuclear waste inside, and high-level nuclear waste can be permanently stored by burying it at the bottom.

[0105] At this time, a container for storing low- and intermediate-level nuclear waste can be manufactured into an appropriate container shape using a formwork using the resin mortar according to the present invention.

[0106] In addition, when storing the above low- and intermediate-level nuclear waste, partitions can be constructed at regular intervals, and the partitions can also be manufactured in an appropriate partition shape using a formwork using the resin mortar according to the present invention.

[0107] In addition, in the present invention, after inserting spent nuclear fuel rods into the high-level nuclear waste storage container, the upper part of the spent nuclear fuel rods is sealed using resin mortar, the upper part of the resin mortar is filled with water, and the high-level nuclear waste storage container is sealed using a cover (cap, 72-1) manufactured using resin mortar, thereby storing high-level nuclear waste.

[0108] At this time, the high-level nuclear waste storage container can be manufactured into an appropriate container shape using a formwork using the resin mortar according to the present invention.

[0109] In one embodiment of the present invention, the nuclear waste disposal facility can be formed by pre-filling each nuclear waste storage tank (71) with bentonite (73), storing nuclear waste (90) therein, inserting and fixing a sealed storage container (70), and then sealing the surface of the nuclear waste disposal tank (71) with resin mortar or a separate cap.

[0110] In addition, as another embodiment, the nuclear waste disposal facility can be formed by pre-inserting and fixing a sealed storage container for storing nuclear waste in each nuclear waste storage tank without pre-filling with bentonite, injecting the first resin mortar around the storage container, and sealing the surface of the nuclear waste storage tank with resin mortar or a separate cap.

[0111] In addition, as another embodiment, it can be formed by injecting resin mortar (72-2) into each nuclear waste storage tank, directly storing nuclear waste (90), and then sealing it using a cap (72-1). (Fig. 2)

[0112] In addition, each of the above nuclear waste storage tanks (71) may be formed in a circular or square shape, and its periphery may be installed so as to be surrounded by the fourth resin mortar (60).

[0113] In addition, the nuclear waste storage container according to the present invention can be manufactured by using a mold on the inner surface of a container made of a circular or square copper pipe, and by installing a quaternary resin mortar on the inner surface of the container in a non-detachable manner. Specifically, the nuclear waste storage container can be manufactured by installing a quaternary resin mortar (72-5) on the inner surface of a container (72-4) made of a circular or square copper pipe by using a method such as centrifugal force, and the cap (72-1) for sealing can also be manufactured using the resin mortar according to the present invention. (Figs. 3 and 4)

[0114] The nuclear waste storage facility according to the present invention may be formed in an overall I shape, a T shape, or a cross shape.

[0115] At this time, it is preferable that the space for burying the high-level nuclear waste storage container is formed inside the nuclear waste storage facility according to the present invention.

[0116] In addition, as shown in the drawing, a management passage (100) may be formed between the wall of the storage and the square-shaped sealing facility in the formed dome-shaped storage, and a work passage and work door (130) for moving and storing nuclear waste may be formed in the central portion.

[0117] In addition, in the present invention, it is preferable that the management passage be formed so that the vehicle can move in one direction or two directions, and the management passage may be formed through the side of the tunnel.

[0118] Additionally, an inspection window may be configured on the side of the above management passage to enable visual inspection of the internal condition.

[0119] In addition, a radiation detection sensor can be installed inside the above-mentioned square shape and a surveillance camera (CCTV) can be installed to monitor and manage the internal status from the outside through wired or wireless communication.

[0120] The facilities such as the inspection window and work door used in the present invention can also be manufactured in an appropriate required shape using a formwork using the resin mortar according to the present invention.

[0121] In addition, it is preferable that all equipment-related materials used in the present invention be made of copper to prevent corrosion.

[0122] The resin mortar used in the present invention is classified into oil-based resin mortar and water-based resin mortar. The water-based resin mortar is made by adding water at a rate of about 10 to 100 parts by weight based on 100 parts by weight of the oil-based resin mortar, and has the same basic composition.

[0123] The resin mortar used in the present invention may be an ultra-high strength resin mortar having a multi-function of both oil and water as proposed by the inventor in the previously applied patent (Korean Patent No. 10-2106352). Hereinafter, the ultra-high strength resin mortar having a multi-function of both oil and water is described in detail.

[0124]

[0125] The mortar composition of the present invention is characterized by being composed of an ultra-low viscosity resin that does not contain any volatile organic compounds, has no chalking properties, and is composed of a pollution-free resin as its main component.

[0126] The resin mortar having a water-soluble positive function of the present invention is composed of a main component and a hardening component.

[0127] Specifically, the main component comprises 70 to 90 wt% of at least one resin main component selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5 to 20 wt% of an epoxy resin auxiliary component, 1 to 5 wt% of a coagulant, and 1 to 20 wt% of a flame retardant, and for 100 wt% of the resin liquid main component thus composed, 10 to 50 wt% of a curing component including 40 to 60 wt% of polyoxypropylene diamine, 20 to 40 wt% of polyamide amine, 1 to 10 wt% of at least one amine selected from triethylenetetramine and diethylenetriamine, and 1 to 10 wt% of a curing accelerator is mixed on site, and 150 to 1000 wt% of an inorganic material mixed with silica sand is further mixed based on 100 wt% of the mixed component obtained by mixing the mixed component on site to form a resin mortar composition.

[0128] 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 further included, these are additives for the functions of various specific purposes, and may be added separately, for example, in a composition having a coating film or thin film layer, but they are not essential components.

[0129] More specifically, in the present invention, the resin mortar composition comprises a main component including a trifunctional polyglycidyl ether resin or trimethylene propylene triglycidyl ether and an amine-based curing component.

[0130] Specifically, it is composed of a resin liquid main component comprising 70 to 90 wt% of at least one resin main component selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5 to 20 wt% of an epoxy resin auxiliary component, 1 to 5 wt% of a coagulant, and 1 to 20 wt% of a flame retardant, and a curing component comprising 40 to 60 wt% of polyoxypropylene diamine, 20 to 40 wt% of polyamide amine, 1 to 10 wt% of at least one amine selected from triethylenetetramine and diethylenetriamine, and 1 to 5 wt% of a curing accelerator.

[0131] In the present invention, the resin main component and the curing component are each comprised of 100 parts by weight: 10 to 50 parts by weight to form a mixed component.

[0132] It is preferable to use a resin mortar obtained by mixing 150 to 1000 parts by weight of an inorganic component including silica sand, inorganic filler, etc. based on 100 parts by weight of a mixed component obtained by mixing the main component including the above resin main component and the hardening component on site.

[0133] In the present invention, by preparatively adding an emulsifier to the curing component, it is possible to promote a hydration reaction by mixing it with the main component in the field and then using water as a diluent, and based on 100 parts by weight of the curing component, 0.1 to 3 parts by weight of the emulsifier and 3 to 5 parts by weight of the reaction resin are included, and the curing component can be formed by polymerization reaction or by hybrid polymerization of at least one of Kookdo Chemical product specifications 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.

[0134] As an emulsifier that can be used in the present invention, emulsifiers disclosed in Korean Patent No. 10-0989942, previously filed and registered by the inventor of the present invention, such as copolymers of polyoxyethylene and polyoxypropylene, copolymers of polyoxyethylene and polyoctylphenyl ether, sodium dodecylbenzene sulfide, etc. can be used, but are not necessarily limited thereto, and any emulsifier that can impart amphoteric properties of oil and water can be used without limitation.

[0135] In this way, in the present invention, due to the characteristics of having both oil-based and water-based functions, even with a very small amount of emulsification polymerization in the curing component, the curing reaction is activated when mixed with the resin component, and the silanol group captures water along with an increase in adsorption and condensation energy at the interface, enabling the function to be performed more stably.

[0136] In the present invention, an acrylic resin can be used as the reaction resin.

[0137] The above mixed component may include 1 to 50 parts by weight of a single or a mixture of nano metal powder and nano metal oxide powder based on 100 parts by weight of the above-described main resin component, and may further include 1 to 80 parts by weight of an inorganic additive based on 100 parts by weight of the above-described main resin component.

[0138] In addition, in order to pour the resin mortar composition, 150 to 1000 parts by weight of inorganic materials such as silica and inorganic fillers are mixed on site based on 100 parts by weight of the obtained mixed components, and the mortar can be mixed and used in a structure.

[0139] Additionally, it may include some crushed stone in addition to the above-mentioned silica.

[0140] Additionally, in the present invention, in addition to the resin component of the above composition, the composition may further comprise resins such as Polyethylene glycol diglycidyl ether, Resorcinol diglycidyl ether, Thio-Diphenyl diglycidyl ether, Glycerol polyglycidyl ether, Pentaerythritol polyglycidyl ether, Castor oil polyglycidyl ether, and Sorbitol polyglycidyl ether.

[0141] In the present invention, in addition to the resin component of the above composition, high-functionality epoxy resins such as N,N-Diglycidyl Aniline, N,N-Diglycidyl -o-toluidine, Triglycidyl-p-Aminophenol, Tetraglycidyl-diamino diphenyl methane, Tetraglycidyl-m-Xylenediamine, and Triglycidyl-m-aminophenol can be further added to the composition.

[0142] In addition, an epoxy resin commonly used in the field to which the present invention belongs can be used, and a general epoxy resin, an epoxy resin containing chlorine, or a 3, 4-functional epoxy resin, a cyclopropyl resin, a phenol novolac resin, a cresol novolac epoxy resin, or a modified type using a compound that does not contain a volatile organic compound can be used.

[0143] In the present invention, the inorganic filler used in addition to or together with (or optionally) the silica sand is preferably at least one selected from the group consisting of powders of calcium carbonate, talc, bicarbonate, silica, magma silica composite, ceramic, etc., but is not limited thereto.

[0144] 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 brominated flame retardant, etc., and specifically, the non-halogen epoxy resin in the KDP 555 MC series of Kukdo Chemical Products may be replaced with the basic resin weight, and about 20% of a non-halogen inorganic substance (product APP-263) may be mixed with 100 parts by weight of the basic resin, or about 5 to 10% of antimony trioxide may be mixed with 10 to 30% of the non-halogen inorganic substance.

[0145] In the present invention, additives such as coagulants and accelerators can be optionally mixed and used in the main component.

[0146] In the present invention, the coagulant is preferably at least one selected from the group consisting of silicon dioxide aerosol, cellulose, silica gel, sol, garemite hard anhydrous silicic acid, bentonite, white carbon, and asobest, but is not limited thereto.

[0147] In the present invention, the accelerator promotes hardening and may be phenol, nonyl phenol, Kukdo Chemical product specifications KH-30, KH-3001 A-399, etc., but is not limited thereto.

[0148]

[0149] Next, the curing component comprises 40 to 650 wt% of polyoxypropylene diamine, 20 to 40 wt% of polyamide amine, 1 to 10 wt% of one or more amine compounds selected from triethylenetetramine and diethyltriamine, and 1 to 10 wt% of a curing accelerator.

[0150] In the composition of the above curing component, one or more selected from isophorone diamine, methylenedianiline, metaxylene diamine, triethylene pentamine, N-aminoethyl piperazine, diethyleneaminopropyl amine, M-phenylene diamine, diaminodiphenyl sulfone, and isocyanate can be mixed and used in addition to polyamide amine, which is a result of a copolymerization or a heating and pressurizing condensation reaction of a monomer, dimer, or trimer organic fatty acid and an aliphatic amine, and an adduct to which epoxy is added. It is also possible to use a type in which isophorone diamine, methylenedianiline, and metaxylene diamine are mixed and modified with polyamide amine and mixed with polyoxypropylene diamine.

[0151] In addition, it is also possible to mix one or more selected from acid anhydride-based aliphatic tertiary amines, polyamide amines, polypropylene amines, isophorone diamine, metaxylene diamine, diamino diphenylene pulphone, 4,4-diamino diphenyl methane, or adduct using epoxy to post-add triethylene tetraamine and diethylene triamine to replace polyoxypropylene diamine in the curing agent composition or to mix them partially.

[0152] In addition, one or more selected from the group consisting of a bifunctional aromatic glycidyl ester, a bifunctional glycidyl amine, an alicyclic epoxy resin, N,N-diglycidyl aniline, N,N-diglycidyl-o-toluidine, triglycidyl-p-aminophenol, tetraglycidyl-diamino diphenylmethane, tetraglycidyl-m-xylene diamine, and triglycidyl-m-aminophenol may be used in combination.

[0153] The types of amines that can be used as the above-mentioned curing component are categorized and explained as follows.

[0154] 1. Alicyclic amine base: Copolymerization or adduct of alicyclic amines such as polyoxypropylene diamine, isophorone diamine, methylene dianiline, meta-xylene diamine, triethylene pentamine, N-aminoethyl piperazine, diethyleneaminopropyl amine, M-phenylene diamine, and diaminodiphenyl sulfone.

[0155] 2. Aliphatic amine base: chemically modified adducts such as diethylene triamine, triethylene tetramine, and tetraethylene pentamine.

[0156] 3. Aromatic amine base: Chemically modified adducts such as diamino diphenylene sulfone and 4,4'-diamino diphenyl methane

[0157] 4. Polyamide amine: Polyamide curing agent and epoxy-added adduct resulting from the heat-pressure condensation reaction of monomer, dimer, and trimer organic fatty acids and aliphatic amines.

[0158] 5. Acid anhydrides: adducts of phthalic anhydride, hexahydrophthalic anhydride, and methyl tetrahydrophthalic anhydride.

[0159] The resin composition of the present invention, which includes a coagulant, a flame retardant, an accelerator, etc., is mixed in an ultra-low viscosity fluid state, and maintains stable immobility by increasing the adsorption and condensation energy at the interface by an amine with a large active reaction, and 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, the watertightness can be increased by vibrating simultaneously with the pouring, and the surface layer can be constructed to have a smooth surface by manual rolling using a pressing plaster and a honeycomb or brush-shaped roller.

[0160] In addition, it can be applied to leveling work by mixing an appropriate amount of cement and various inorganic substances including silica sand and pouring, pressing, or pouring resin mortar to form a coating on the surface of a structure.

[0161] In the present invention, the curing components can be broadly categorized into four types: amines, polyamines, acid anhydrides, latent compounds, and imidazoles. Modified types may also be applied to suit various characteristics. Furthermore, in the case of resin mortars, the basic resin component and curing component must be mixed on-site to stably maintain an appropriate level of immobility through a curing reaction in order to exhibit their properties as mortars.

[0162] Here, the key factor that can stably maintain the immobility is the activation reaction that comes from mixing the base resin component and the curing component. In general solvent-free compositions, flowability is controlled only by using a large amount of a coagulant such as aerosol. This large amount of coagulant results in poor workability and the mortar cannot function. To solve this problem, a method can be used in which an appropriate amount of a coagulant such as aerosol is added to the base resin component, and at least one selected from triethylenetetramine and diethylenetriamine, which are highly reactive amines toward active oxygen, is polymerized through a copolymerization or adduct method, and the resulting curing agent is mixed with the prepared resin component on site. In this case, the moisture contained in the resin component increases the adsorption and condensation energy at the interface, resulting in swelling, and the fluidity is strongly controlled. In addition, the fluidity is continuously maintained even in cross-linking by reaction, so that the body is in the form of a disconnected body in the pores between the framework and silica sand, and heat generation due to the reaction can be controlled. When mixed with silica sand, aggregate, other inorganic substances, and metal grains, it is uniformly positioned in the pores.

[0163] Next, the present invention may further include a radiation absorbing powder component in the resin mortar.

[0164] That is, the resin mortar can be composed of a single or a mixture of nano metal powder and nano metal oxide powder.

[0165] In the present invention, the nano metal powder and nano metal oxide powder are components that absorb radiation and ultimately extinguish it, and are characterized by having a nano-sized particle size and an internal structure that is porous with a large absorption cross-section.

[0166] In the present invention, the nano metal powder may be a mixture of one or two or more selected from the group consisting of aluminum, titanium, zirconium, scandium, yttrium, cobalt, tantalum, molybdenum, and tungsten.

[0167] In addition, in the present invention, the nano metal oxide powder may be one or a mixture of two or more selected from the group consisting of palladium oxide, iridium oxide, ruthenium oxide, osmium oxide, rhodium oxide, platinum oxide, iron oxide, nickel oxide, cobalt oxide, indium oxide, aluminum oxide, titanium oxide, tungsten oxide, and magnesium oxide.

[0168] 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 powder to prevent them from fusing with each other in the composition, and specifically, it is preferable to use a powder whose surface is coated with graphite oxide.

[0169] In the present invention, the graphite oxide is obtained by treating at least one type of graphite selected from natural graphite, plate-like graphite, artificial graphite, expanded graphite, etc. with an oxidizing agent such as sulfuric acid, nitric acid, potassium permanganate, or calcium chlorate, and the method for coating the surface of the nano metal powder or nano metal oxide powder with graphite oxide is as follows: first, the nano metal powder or nano metal oxide powder and the graphite oxide are mixed at a certain ratio, a small amount of water is added to form a slurry, and then ultraviolet rays are irradiated to allow the graphite oxide to combine with the nano metal powder or nano metal oxide powder to form a coating layer on the surface.

[0170] Nano metal powder and nano metal oxide powder with a coating layer formed on the surface in this way are not easily refused with each other, thereby improving dispersion stability.

[0171] However, in the present invention, the use of not only nano metal powder or nano metal oxide powder having a coating layer formed, but also powder that has been treated or not treated is also included in the scope of the present invention.

[0172] Next, the present invention may further include an inorganic additive to enhance the flame retardant function of the structure.

[0173] In addition, in the present invention, in addition to the above-mentioned inorganic additives, a brominated flame retardant, a non-halogenated flame retardant, a phosphorus flame retardant, etc. may be additionally included, but are not limited thereto.

[0174] The above-mentioned inorganic additives can serve to provide flame retardant or non-combustible functions in the event of a fire.

[0175] In addition, the above-mentioned inorganic additive may be a salt such as a metal hydroxide or carbonate, and for example, one or a mixture of two or more selected from the group consisting of powders such as calcium hydroxide, calcium carbonate, magnesium hydroxide, magnesium carbonate, barium chloride, barium sulfate, ceramics, and diatomaceous earth may be used. In addition, all inorganic substances in powder form may be mixed.

[0176] In the present invention, it is preferable to include the inorganic additive in an amount of about 1 to 80 parts by weight based on 100 parts by weight of the base resin to optimize performance.

[0177] In addition, in order to form the resin mortar composition of the present invention, silica sand is included in a certain proportion. The silica sand may be one or more selected from the group consisting of artificial silica sand, natural silica sand, colored silica sand, etc., and is preferably included in an amount of 150 to 1,000 parts by weight per 100 parts by weight of the base resin.

[0178] Additionally, since it is used for structures, it may include general crushed stone, aggregate, and wood chips in addition to silica sand, and the size can range from 0.5 to 30 mm.

[0179] It can also include sand, crushed stone, aggregate, wood chips, metal chips, glass chips, and beads, and the size can be from 0.5 to 30 mm.

[0180] In the present invention, cement may be optionally further included in the resin mortar composition, and it is preferable to use refractory, alumina cement as the cement, but the present invention is not limited thereto.

[0181] In the present invention, it is preferable that the refractory cement is included in an amount of 10 to 300 parts by weight based on 100 parts by weight of the main resin component.

[0182] In the present invention, it is preferable to use the refractory cement that is mixed with graphite oxide and treated with ultraviolet rays to coat the surface of the cement with graphite oxide. Specifically, the refractory cement may be obtained by mixing refractory cement powder and graphite oxide in a certain ratio, adding a small amount of water to form a slurry, and then irradiating the mixture with ultraviolet rays to cause the graphite oxide to bind with the refractory cement powder and form a coating layer on the surface.

[0183] In addition, in the present invention, the resin mortar composition may further include functional fibers to further enhance physical properties such as tensile strength and impact strength.

[0184] In the present invention, the functional fiber may be one or a mixture of two or more selected from glass fiber, aramid fiber, and carbon fiber.

[0185] The above functional fiber can use fiber chips having a length ranging from about 2 to 10 mm.

[0186] In the present invention, it is preferable that the functional fiber is additionally included in an amount of about 1 to 20 parts by weight based on 100 parts by weight of the main resin component.

[0187] The structure constructed in the present invention is a structure installed using a mortar composition using resin, unlike existing concrete structures.

[0188] Next, in the composition of the resin component forming the structure using the above resin mortar composition, various thermosetting resins and thermoplastic resins can be further added as a means to achieve a specific functional purpose, and a modified type liquid using a single or compound that does not contain volatile organic compounds can be used.

[0189] For other components not specifically exemplified in the present invention, reference may be made to the inventor's prior registered patents No. 10-0989942 and No. 10-1811350, which may be interpreted as being included within the scope of the present invention by reference.

[0190] The resin mortar formed according to the present invention can secure excellent performance in integrity even in long-span structures when applied to structures, and has the advantage of being able to completely solve and replace the problems of existing concrete, such as waterproofing / crack stability, shrinkage / expansion stability, etc. Accordingly, it can be used not only for general buildings, but also for structures requiring special functions under harsh conditions, such as radiation shielding, bulletproofing, protection, marine structures, and underwater structures. In addition, it has an advantage in that it can be used for earthquake-resistant structures because it has earthquake-resistant functions.

[0191] In addition, the resin mortar according to the present invention is a mortar using resin that can replace concrete structures, and the rigidity of the framework that is basically required can be continuously maintained from the composition having an ultra-high strength function, and accordingly, a module using a mold of a desired shape can be manufactured with the stability, eco-friendliness, and convenience of work of the structure, and the structure can be freely manufactured, constructed, and installed. In addition, in the production of a spent nuclear fuel rod storage container, a storage container of a desired shape can be obtained by filling and hardening the resin mortar in the mold during the production process, and then using vibrating or centrifugal force before hardening after filling the resin mortar in the mold.

[0192] The method for constructing a nuclear waste storage facility using the resin mortar according to the present invention as described above can be performed in the following order.

[0193] The first step is to excavate a tunnel, install waterproof non-woven fabric on the wall of the excavated tunnel, and pour and harden shotcrete on the outside;

[0194] A second step of forming a storage facility in the shape of an overall circular dome by spreading the first resin mortar along the excavated surface on the outside of the above-mentioned hardened shotcrete layer;

[0195] A method for constructing a nuclear waste storage facility, characterized in that a bottom is formed by pouring a third resin mortar or compacting aggregate in the middle lower part of the storage facility, and a nuclear waste landfill facility is installed in the bottom part.

[0196] The above nuclear waste landfill facility is formed by installing nuclear waste storage tanks at regular intervals on the floor, directly storing nuclear waste in each storage tank or burying and storing nuclear waste storage containers, and resealing the upper part of the floor using a fourth resin mortar, thereby forming a nuclear waste landfill facility.

[0197] The bottom and side of the above nuclear waste disposal facility are connected to the second resin mortar above, so that the interior is sealed.

[0198] The above first resin mortar and second resin mortar are characterized in that they are installed so as to be fixed to the ground joint surface of the excavated tunnel wall using a fixing member.

[0199] The above construction method is the same as that described in the nuclear waste storage facility described above, so a duplicate description is omitted.

[0200] The present invention will be described in more detail below through specific examples. However, the examples presented below are merely illustrative examples for specifically explaining the present invention, and the present invention is not limited to the examples presented below.

[0201] 1. Manufacturing Example 1

[0202] 100 parts by weight of a resin liquid main component containing 80 wt% of a resin main component composed of polyglycidyl ether, 10 wt% of an epoxy resin auxiliary component (a copolymer of epichlorohydrin and bisphenol (Kukdo Chemical)), 2 wt% of a coagulant (silicone dioxide aerosol), and 10 wt% of a phosphorus-based flame retardant, and 30 parts by weight of a curing component containing 50 wt% of polyoxypropylene diamine, 30 wt% of polyamide amine, 15 wt% of triethylenetetramine, and 5 wt% of a curing accelerator were mixed, and then silica sand was mixed in an amount 6 times that of the above-mentioned mixed components, and mixed with aggregate having a WC-1 particle size distribution of pre-prepared SPS-KAI0002-F2349-5687 (heated asphalt mixture), and then molded in a test mold. The molded specimen was removed from the mold after 24 hours at room temperature and cured for 7 days before being tested.

[0203] 2. Evaluation items and evaluation methods / results

[0204] The following items were evaluated using the test specimen obtained in Manufacturing Example 1 using the following method.

[0205] Test Item Unit Test Method Ratio High specific gravity (main material / hardener) KS M ISO 2811-1: 2016 Mortar resin viscosity (main material / hardener) mPa sKS M ISO 2555: 2002 Workable time minKS F 4043: 2008 Bending strength N / mm 2 Compressive strengthStandard alkali immersion post-bonding strength60℃20℃5℃After repeated hot and cold water permeabilitygChloride ion penetration resistanceCoulombsLength change rate%Dropping ball impact test-KS F 2221:2009Full support on sandResistance to freezing and thawing (B-Type, 300 Cycle)N / mm 2 KS F 2456: 2013, KS F 4043: 2008 After conditions, flexural strength and compressive strength, resistance to salt damage (3% NaCl, 168 hours) N / mm 2 KS M ISO 2812-1: 2012, KS F 4043: 2008 Acid resistance (3% HCl, 168 hours)

[0206] A. Specific gravity

[0207] 1) Test equipment: Metal pycnometer

[0208] 2) Test method: Measure the specific gravity of the main material and hardener of the resin mortar according to the test method of KS M ISO 2811-1: 2016 (Paints and varnishes - Density measurement method - Part 1: Pycnometer method).

[0209] - Test conditions: (23 ± 1) ℃

[0210] 3) Test Results: The specific gravity test results are as follows.

[0211] Test Item Classification Unit Result Value Remarks X1 X2 Average Specific Gravity Base Material -1.17 1.16 1.17 Hardener 1.0 11.0 11.01

[0212] B. Viscosity

[0213] 1) Testing equipment: Brookfield Viscometer

[0214] 2) Test method: Measure the viscosity of the main ingredient and hardener of the mortar resin according to the test method of KS M ISO 2555: 2002 (Plastics - Measurement of apparent viscosity by the Brookfield method in liquid, suspended or dispersed resins).

[0215] - Test conditions

[0216] Host: (25 ± 1) ℃ (Brookfield Viscometer, LV 3, 60 r / min)

[0217] Hardener: (25 ± 1) ℃ (Brookfield Viscometer, LV 2, 100 r / min)

[0218] 3) Test results: The viscosity test results are as follows.

[0219] Test Item Classification Unit Result Value Remarks X1 X2 Average Viscosity CPS at 25℃ 1200 1250 1223 Hardener 353736

[0220] A. Available working hours

[0221] 1) Test device: Polyethylene bag (400 mL)

[0222] 2) Test method: Measure the time from the time the hardener is added to the epoxy resin material to the end point by the touch method according to the test method of KS F 4043: 2008.

[0223] 3) Test Results: The test results for available working hours are as follows.

[0224] Test Item Unit Result Value Note X1 X2 Average available working hours 606060

[0225] a. Bending strength

[0226] 1) Test equipment: Bending strength tester (Toni Technik 20 kN: GERMANY)

[0227] 2) Test method: According to the test method of KS F 4043: 2008, three test specimens with a size of 40×40×160 mm are manufactured with a support distance of 100 mm, and the center of the test specimen is loaded at a speed of (50 ± 10) N per second to measure the maximum load, and then the flexural strength is calculated using the following formula.

[0228]

[0229] 3) Test results: The test results for bending strength are as follows.

[0230] Test Item Unit Result Value Remarks X1 X2 X3 Average Bending Strength N / ㎟ 27.9 28.1 28.0 28.0

[0231] Ma. Compressive strength

[0232] 1) Test device: Compressive strength tester (Toni Technik 300 kN: GERMANY)

[0233] 2) Test method: According to the test method of KS F 4043: 2008, the bending strength test is conducted immediately after the test on 6 cut specimens of 3 specimens. Using a 40×40×40mm loading plate, apply a load at a rate of (800 ± 50) N per second to the center of the specimen, measure the maximum compressive load, and then calculate the compressive strength using the following equation.

[0234]

[0235] For the alkaline resistance test, a test piece made of 40×40×160 mm is immersed in a saturated calcium hydroxide (CaOH2) solution at (20 ± 2) ℃ for 168 hours, then taken out and carefully divided into two parts to perform a compressive strength test.

[0236] 3) Test results: The test results for compressive strength are as follows.

[0237] Test Item Unit Result Value Remarks X1 X2 X3 Average Compressive Strength Standard N / ㎟ 127.5 127.0 127.6 127.4 128.0 127.0 127.2

[0238] Bar. Adhesion strength

[0239] 1) Testing equipment: Universal material testing machine (INSTRON 100 kN: USA)

[0240] 2) Test method: According to the test method of KS F 4043: 2008, a 70 mm x 70 mm x 20 mm test base is placed on the mortar, a 40 mm x 40 mm x 10 mm metal frame is placed on the mortar, the prepared sample is filled, and then cured. After curing, the test piece is bonded to a 40 x 40 mm tensile jig using an adhesive, and after conditioning as in [Table 3-6], a tensile force is applied at a load rate of 1,500 to 2,000 N / min to measure the maximum tensile load. The bond strength is calculated by the following equation.

[0241]

[0242] Classification test conditions: 60℃ 6 hours of standing, 20℃ 5℃ repeated heating and cooling, then immersed in water, 18 hours → (-20 ± 3) ℃, 3 hours of cooling → (50 ± 3) ℃ 3 hours of heating: repeated 10 times

[0243] 3) Test results: The test results for bonding strength are as follows.

[0244] Test Item Unit Result Value Note X1 X2 X3 Average bond strength 60 ℃ N / ㎟ 2.2 12 2.10 3 2.34 12.220 ℃ 2.98 6 3.10 2 3.24 13.15 ℃ 2.88 4 2.95 8 2.93 12.9 After repeated hot and cold 2.5 14 2.29 6 2.37 5 2.4

[0245] 4. Pitching amount

[0246] 1) Test device: Permeability test device

[0247] 2) Test method: According to the test method of KS F 4043: 2008, a test specimen with dimensions of Φ150×40 mm is manufactured, dried at a temperature of (80 ± 2) ℃ for 48 hours, cooled to room temperature in a desiccator, and then a surface with a diameter of 5 cm or more is lightly cleaned with a brush and the mass (W0) of the test specimen is measured.

[0248] Next, as shown in [Figure 3-9], a water pressure of 0.1 N / ㎟ is applied to the surface of the test body for 1 hour using a water permeability test device, and then the mass (W1) is measured to calculate the water permeability according to the following equation.

[0249]

[0250] 3) Test results: The results of the water permeability test are as follows.

[0251] Test Item Unit Result Value Note X1 X2 X3 Average Transmittance g 0.10.10.10.1

[0252] Ah. Resistance to chloride ion penetration

[0253] 1) Test device: Chloride ion penetration resistance measuring device

[0254] 2) Test method: Measure the change in current (A) over time on a test specimen manufactured and cured with dimensions of Φ100×50mm according to the test method of KS F 2711, and calculate the amount of charge passed according to the following formula.

[0255]

[0256] 3) Test results: The test results for chloride ion penetration resistance are as follows.

[0257] Test Item Unit Result Value Note X1 X2 X3 Average Chloride Ion Penetration Resistance Coulombs 0000* No penetration

[0258] Okay. Rate of change of length

[0259] 1) Test device: Length change rate measuring device

[0260] 2) Test method: Measure the base length of the test piece manufactured with dimensions of 40×40×160mm according to the test method of KS F 4043: 2008 immediately after demolding, and measure the length after curing for 7 days at a temperature of (20 ± 2) ℃ and a relative humidity of (65 ± 10)% to calculate the length change rate.

[0261]

[0262] 3) Test results: The test results for length change rate are as follows.

[0263] Test Item Unit Result Value Note X1 X2 X3 Average Length Change Rate % -0.06 - 0.04 - 0.07 - 0.06

[0264] Car. Drop impact test

[0265] 1) Test device: Spherical weight (W2 1 000)

[0266] 2) Test method: A test specimen manufactured and cured to dimensions of 300×300×50 mm is subjected to a free fall of a 1,042 g spherical weight from a height of 1,000 mm on the surface of the specimen using the full-face support method on sand as shown in [Figure 3-11] in accordance with the test method of KS F 2221: 2009 (impact test method for building boards), and then the presence of cracks and peeling on the surface is visually checked.

[0267] 3) Test results: The results of the falling ball impact test are as follows.

[0268] Test Item Unit Result Value Remarks Dropping impact test (presence of cracks and peeling) - No abnormalities -

[0269] Car. Resistance to freezing and thawing

[0270] 1) Test equipment: Freeze-thaw test equipment (B-Type) Compression strength tester (Toni Technik 300 kN: GERMANY)

[0271] 2) Test method: A test specimen manufactured with dimensions of 40×40×160 mm is conditioned for 300 cycles using Method B (air-dried freezing and thawing in water) in accordance with KS F 2456: 2013 (Test method for concrete resistance to rapid freezing and thawing), and then the flexural strength and compressive strength are measured in accordance with the test method of KS F 4043.

[0272] 3) Test results: The results of the freeze-thaw resistance test are as follows.

[0273] Test Item Unit Result Value Remarks X1 X2 X3 Average Resistance to freezing and thawing Bending strength N / ㎟ 27.9 28.1 27.9 27.9 B-Type, 300 Cycle Compressive strength N / ㎟ 95.8 96.1 96.0 95.8 96.5 95.6 95.8

[0274] T. Resistance to salt damage

[0275] 1) Test device: Compressive strength tester (Toni Technik 300 kN: GERMANY)

[0276] 2) Test method: A test piece manufactured with dimensions of 40×40×160 mm is immersed in a 3% NaCl aqueous solution for 168 hours in accordance with KS M ISO 2812-1: 2012 (Paints and varnishes - Measurement of liquid resistance - Part 1: Immersion method for liquids other than water), and then the flexural strength and compressive strength are measured in accordance with the test method of KS F 4043.

[0277] 3) Test results: The results of the salt damage resistance test are as follows.

[0278] Test Item Unit Result Value Remarks X1 X2 X3 Average Resistance to salt damage Bending strength N / ㎟ 23.4 22.5 20.9 22.3 3 % NaCl, 168 hours immersion Compressive strength N / ㎟ 94.7 96.9 95.1 95.2 96.3 93.9 94.1

[0279] Pa. Acid resistance

[0280] 1) Test device: Compressive strength tester (Toni Technik 300 kN: GERMANY)

[0281] 2) Test method: A test piece manufactured with dimensions of 40×40×160 mm is immersed in a 3% HCl aqueous solution for 168 hours in accordance with KS M ISO 2812-1: 2012 (Paints and varnishes - Measurement of liquid resistance - Part 1: Immersion method for liquids other than water), and then the flexural strength and compressive strength are measured in accordance with the test method of KS F 4043.

[0282] 3) Test results: The acid resistance test results are as follows.

[0283] Test Item Unit Result Value Remarks X1 X2 X3 Average Acid Resistance Bending Strength N / ㎟ 19.2 20.2 17.8 19.13 % HCl, 168 hours immersion Compression Strength N / ㎟ 86.3 83.186.184.5 84.8 82.4 84.3

[0284] From the above results, the resin mortar composition according to the present invention is composed of a main component and an amine-based hardener component, and has ultra-high strength properties such as compressive strength and tensile strength, and has the advantage of being capable of rapid processing, so that by using it to construct a nuclear waste storage facility, it can be used alone or together with concrete to replace existing concrete, and it can also have an earthquake-resistant function, so it can be used as an earthquake-resistant structure. In addition, it is expected to be very useful when applied to a nuclear waste storage facility that requires high self-weight, pressure, or impact, as it does not cause cracks due to shrinkage stability and has excellent waterproofing function.

[0285] [Explanation of symbols]

[0286] 10: Wall of the excavated tunnel 20: Waterproof non-woven fabric

[0287] 30: Shotcrete 40: First resin mortar

[0288] 50: Second resin mortar 60: Third resin mortar

[0289] 70: Nuclear waste landfill facility 71: Nuclear waste storage tank

[0290] 72: Nuclear waste storage container 72-1: Cap

[0291] 73: Bentonite 80, 72-5: Fourth resin mortar

[0292] 100: Management passage 120: Fixed member

[0293] 130: Work statement

Claims

1. Waterproof non-woven fabric installed on the excavated tunnel wall and shotcrete poured on the outside; First resin mortar poured along the excavated surface on the outside of the shotcrete layer; and A second resin mortar is poured along the excavated surface on the outer surface of the first resin mortar; a storage space is formed in the shape of an overall circular dome. A nuclear waste storage facility characterized in that a floor is formed by pouring a third resin mortar or compacting aggregate into the middle lower part of the storage facility, and a nuclear waste landfill facility is installed in the floor. The above nuclear waste landfill facility is formed by installing nuclear waste storage tanks at regular intervals on the floor, directly storing nuclear waste in each storage tank or burying a nuclear waste storage container, and sealing the upper part of the floor using a fourth resin mortar, thereby forming a nuclear waste landfill facility. The bottom and side of the above nuclear waste disposal facility are connected to the second resin mortar on top so that the interior is sealed. A nuclear waste storage facility characterized in that the first resin mortar and the second resin mortar are installed to be fixed to the ground joint surface of the excavated tunnel wall using a fixing member.

2. In claim 1, The above nuclear waste landfill facility is a nuclear waste storage facility characterized in that it is formed by pre-filling the lower part of each nuclear waste storage tank with bentonite, storing nuclear waste therein, then filling the upper part with bentonite, inserting and fixing a sealed storage container, and sealing the surface of the nuclear waste storage tank with resin mortar or a separate resin mortar cap.

3. In claim 1, The above nuclear waste landfill facility is a nuclear waste storage facility characterized in that the above nuclear waste storage facility is formed by pre-inserting and fixing a sealed storage container in each nuclear waste storage tank without pre-filling with bentonite, injecting the first resin mortar around the storage container, and sealing the surface of the nuclear waste storage tank with resin mortar or a separate resin mortar cap.

4. In claim 1, A nuclear waste storage facility characterized in that each of the above nuclear waste storage tanks is formed in a circular or square shape, and its periphery is surrounded by the fourth resin mortar.

5. In claim 1, A nuclear waste storage facility, characterized in that the first, third, and fourth resin mortars are oil-based or water-based resin mortars, and the second resin mortar layer is water-based resin mortar.

6. In claim 1, A nuclear waste storage facility characterized in that high-level nuclear waste is stored in the above nuclear waste storage container.

7. In claim 1, The above nuclear waste storage container is a nuclear waste storage facility characterized in that it is manufactured by using a mold on the inner surface of a container made of a circular or square copper pipe and is manufactured by installing a quaternary resin mortar on the inner surface of the container in a non-detachable manner.

8. In claim 1, A nuclear waste storage facility characterized by loading a container containing low- and intermediate-level nuclear waste on the upper part of the formed floor.

9. In claim 1, A nuclear waste storage facility, characterized in that a space for burying a storage container for storing high-level nuclear waste is formed inside the nuclear waste storage facility.

10. In claim 1, The above nuclear waste storage facility is a nuclear waste storage facility characterized by being formed in an overall I shape.

11. In claim 1, The above nuclear waste storage facility is a nuclear waste storage facility characterized by being formed overall in a T-shape or a cross shape.

12. In claim 1, A nuclear waste storage facility characterized in that a management passage is formed between the wall surface of the storage and the square-shaped sealing facility in the formed dome-shaped storage facility.

13. In claim 12, A nuclear waste storage facility characterized in that the above management passage is formed so that a vehicle can move in one direction or two directions, and an inspection window is formed so that the internal condition can be visually inspected.

14. In claim 1, A nuclear waste storage facility characterized by having a radiation detection sensor installed inside the square shape and a surveillance camera (CCTV) installed to monitor and manage the internal status from the outside through wired and wireless communication.

15. In claim 5, The above-mentioned oil-based resin mortar comprises a resin liquid-based component including 70 to 90 wt% of one or more resin main components selected from polyglycidyl ether and trimethylolpropane triglycidyl ether, 5 to 20 wt% of an epoxy resin auxiliary component, 1 to 5 wt% of a coagulant, and 1 to 20 wt% of a flame retardant; and A resin mortar is manufactured, characterized by comprising a curing component including 40 to 60 wt% of polyoxypropylene diamine, 20 to 40 wt% of polyamide amine, 1 to 10 wt% of at least one amine selected from triethylene tetraamine and diethylene triamine, and 1 to 10 wt% of a curing accelerator. A nuclear waste storage facility characterized in that it is composed by mixing 5 to 50 parts by weight of a cement component and 500 to 750 parts by weight of silica based on 100 parts by weight of the above-mentioned manufactured resin mortar.

16. In claim 5, A nuclear waste storage facility, characterized in that the above-mentioned water-based resin mortar is obtained by post-adding 10 to 100 parts by weight of water based on 100 parts by weight of the above-mentioned oil-based resin mortar composition.

17. The first step is to excavate a tunnel, install waterproof non-woven fabric on the wall of the excavated tunnel, and pour shotcrete on the outside and harden it; A second step of forming a storage facility in the shape of an overall circular dome by spreading the first resin mortar along the excavated surface on the outside of the above-mentioned hardened shotcrete layer; A method for constructing a nuclear waste storage facility, characterized in that a floor is formed by pouring a third resin mortar or compacting aggregate into the middle lower part of the storage facility, and a nuclear waste landfill facility is installed in the floor. The above nuclear waste landfill facility is formed by installing nuclear waste storage tanks at regular intervals on the floor, directly storing nuclear waste in each storage tank or burying and storing nuclear waste storage containers, and resealing the upper part of the floor using a fourth resin mortar, thereby forming a nuclear waste landfill facility. The bottom and side of the above nuclear waste disposal facility are connected to the second resin mortar on top so that the interior is sealed. A method for constructing a nuclear waste storage facility, characterized in that the first resin mortar and the second resin mortar are installed so as to be fixed to the ground joint surface of the excavated tunnel wall using a fixing member.

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