Integrated treatment method for liquid radioactive waste generated during decommissioning of nuclear power plant

Abstract

The present invention relates to an integrated treatment method for liquid radioactive waste generated during decommissioning of a nuclear power plant. The objective of the present invention is to classify a large amount of liquid radioactive waste generated during decommissioning of a nuclear power plant into low-concentration liquid radioactive waste in a solution state of a water system, high-concentration liquid radioactive waste in suspension and slurry states of a water system, and organic liquid radioactive waste of an organic solvent system according to properties and conditions thereof, and to safely and reliably treat each of the classified low-concentration, high-concentration, and organic liquid radioactive wastes according to respective designated treatment processes, thereby greatly reducing the amount of radioactive waste, which is a treatment result of the liquid radioactive waste, and secondary radioactive waste generated during the treatment process of the liquid radioactive waste, significantly improving work productivity for the treatment of the liquid radioactive waste, and greatly reducing treatment costs. The integrated treatment method for liquid radioactive waste generated during decommissioning of a nuclear power plant comprises: a liquid radioactive waste classification and storage step of classifying and storing the liquid radioactive waste in respective storage tanks; a pre-treatment step of decomposing organic material; a main treatment step of generating exhaust gas and discharge liquid; and a post-treatment step of discharging the purified exhaust gas and discharge liquid to an exhaust and drainage system of a building.

Description

Integrated treatment method for liquid radioactive waste generated during the decommissioning of nuclear power plants

[0001] The present invention relates to an integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, and more specifically, to an integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant that allows the large amount of liquid radioactive waste generated during the decommissioning of a nuclear power plant to be treated by a suitable treatment method according to each property and condition, thereby significantly improving the treatment efficiency of the liquid radioactive waste and reducing treatment costs, as well as significantly reducing the amount of secondary radioactive waste generated during the treatment process, such as radioactive waste resulting from the treatment of liquid radioactive waste and radioactive waste resin generated during the treatment process of liquid radioactive waste.

[0002]

[0003] Generally, during the decommissioning of nuclear power plants, decontamination processes are performed to remove radioactive materials from systems and equipment contaminated by blast materials. Various physical and chemical methods exist for decontamination, and the execution of these processes generates large quantities of liquid radioactive waste with diverse properties and conditions.

[0004] Referring to the attached drawing Fig. 1, conventionally, liquid radioactive waste of various properties and conditions is treated using an ion exchange resin or by evaporating the liquid radioactive waste using a waste liquid evaporator, and the resulting radioactive concentrated waste liquid is treated by solidification.

[0005] The details regarding the conventional method for treating liquid radioactive waste as described above are specifically disclosed in the publications of Korean Published Patent No. 10-1999-0017159 (March 15, 1999) and Korean Registered Patent No. 10-1224725 (January 15, 2013).

[0006] These conventional methods for treating liquid radioactive waste involve treating liquid radioactive waste in the form of suspensions, slurries, and solutions containing chelate compounds using ion exchange resins, or treating the radioactive concentrated waste liquid generated after evaporation using an evaporator by solidifying it.

[0007] However, the above-mentioned conventional method for treating liquid radioactive waste has the problem that when using ion exchange resin, a large amount of filtrate adheres to the surface of the ion exchange resin, significantly reducing the ion exchange rate within a short period and shortening the replacement cycle of the ion exchange resin, thereby greatly increasing the amount of secondary radioactive waste, radioactive waste resin, and when using an evaporator, it takes a long time to concentrate a large amount of liquid radioactive waste, which not only significantly reduces work productivity but also generates a large amount of solidified radioactive waste liquid and incurs high treatment costs for processing the solidified radioactive waste liquid.

[0008]

[0009] The present invention has been devised in consideration of the aforementioned conventional problems, and its purpose is to provide an integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, which can significantly reduce the amount of radioactive waste resulting from the treatment of liquid radioactive waste and secondary radioactive waste generated during the treatment of liquid radioactive waste, while significantly improving work productivity and greatly reducing treatment costs. This is achieved by classifying the large amount of liquid radioactive waste generated during the decommissioning of an operating nuclear power plant and a nuclear power plant subject to decommissioning into low-concentration liquid radioactive waste in a water-based solution state, high-concentration liquid radioactive waste in a water-based suspension and slurry state, and organic liquid radioactive waste in an organic solvent system according to their properties and conditions, and ensuring that each of the classified low-concentration, high-concentration, and organic liquid radioactive wastes is safely and reliably treated according to a designated treatment process.

[0010]

[0011] The objective of the present invention can be achieved by an integrated treatment method for high-concentration and low-concentration liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising: a liquid radioactive waste sorting and storage step in which liquid radioactive waste generated during the hatching of a nuclear power plant is sorted and stored in separate storage tanks as low-concentration liquid radioactive waste, high-concentration liquid radioactive waste, and organic liquid radioactive waste; a pretreatment step in which foreign substances, oil, impurities, precipitates, and solids contained in the liquid radioactive waste stored in each storage tank are separated and collected, and organic matter is decomposed; a main treatment step in which radioactive contaminants contained in the liquid radioactive waste that has passed through the pretreatment step are removed, the condensate from which radioactive contaminants have been removed is gas-liquid separated, and exhaust gas and effluent are generated; and a posttreatment step in which the exhaust gas and effluent discharged after gas-liquid separation in the main treatment step are purified, and the purified exhaust gas and effluent are discharged into the exhaust and drainage system of a building.

[0012]

[0013] The integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention classifies the liquid radioactive waste generated during the decommissioning of a nuclear power plant into low-concentration, high-concentration, and organic liquid radioactive waste, and sequentially performs a suitable pretreatment process according to the properties and conditions of each liquid radioactive waste, a main treatment process for removing radioactive contaminants contained in the liquid radioactive waste after the pretreatment process is completed, and a post-treatment process for purifying the exhaust gas and discharge liquid generated through the main treatment process, and then discharges the purified exhaust gas and purified water, thereby having the effect of significantly improving the treatment efficiency of liquid radioactive waste while reducing treatment costs, as well as significantly reducing the amount of radioactive waste resin and secondary radioactive waste generated.

[0014]

[0015] FIG. 1 is a schematic process diagram illustrating a conventional liquid radioactive waste treatment process for liquid radioactive waste generated at a nuclear power plant, and

[0016] FIG. 2 is a flowchart illustrating the configuration of an integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention, and

[0017] FIG. 3 is a flowchart illustrating the configuration of a pretreatment step among the configurations of an integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention as exemplified in FIG. 2, and

[0018] FIG. 4 is a flowchart illustrating the configuration of the main treatment step among the configurations of the integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention as exemplified in FIG. 2, and

[0019] FIG. 5 is a flowchart illustrating the configuration of a post-treatment step among the configurations of an integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention as exemplified in FIG. 2, and

[0020] FIG. 6 is a flowchart illustrating the configuration of the exhaust gas pretreatment stage among the post-treatment stages exemplified in FIG. 5, and

[0021] Figure 7 is a flowchart illustrating the configuration of the condensate purification step among the post-processing steps exemplified in Figure 5.

[0022]

[0023] The advantages and features of the present invention and the methods for achieving them will become clear by referring to the embodiments described below in detail together with the accompanying drawings. However, the present invention is not limited to the embodiments disclosed below but can be implemented in various different forms. These embodiments are provided merely to ensure that the disclosure of the present invention is complete and to fully inform those skilled in the art of the invention of the scope and nature of the invention, and are limited by the claims of the present invention.

[0024] In describing the embodiments of the present invention, if it is determined that a detailed description of already known functions or configurations could unnecessarily obscure the essence of the invention, such detailed description will be omitted. Furthermore, the terms described below are defined considering the functions in the embodiments of the present invention, and these may vary depending on the intentions or conventions of the user or operator. Therefore, their definitions should be based on the content throughout this specification.

[0025] Hereinafter, a preferred embodiment of the integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention will be described in detail with reference to the attached drawings, FIGS. 2 to 7.

[0026] Referring to the attached drawings Figs. 2 to 7, the integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention consists of a liquid radioactive waste sorting and storage step (S100), a pretreatment step (S200), a main treatment step (S300), and a posttreatment step (S400).

[0027] The above liquid radioactive waste classification storage step (S100) classifies and stores the liquid radioactive waste generated during the hatching of a nuclear power plant into low-concentration liquid radioactive waste, high-concentration liquid radioactive waste, and organic liquid radioactive waste, respectively, in separate storage tanks.

[0028] The above pretreatment step (S200) separates and collects foreign substances, oil, impurities, precipitates, and solids contained in the liquid radioactive waste stored in each storage tank in the above liquid radioactive waste separation and storage step (S100), and decomposes organic matter.

[0029] The above main treatment step (S300) removes radioactive contaminants contained in the liquid radioactive waste that has passed through the above pretreatment step (S200), separates the condensate from which radioactive contaminants have been removed into gas and liquid, and generates exhaust gas and discharge liquid.

[0030] The above post-treatment step (S400) purifies the exhaust gas and discharge liquid that are separated and discharged in the above main treatment step (S300), and discharges the purified exhaust gas and discharge liquid into the exhaust and drainage system of the building.

[0031]

[0032] Referring again to the attached drawings, Figs. 2 to 7, the pretreatment step (S200) for separating and collecting foreign substances, oil, impurities, precipitates, and solids contained in the liquid radioactive waste stored in each storage tank in the liquid radioactive waste classification storage step (S100), and for decomposing organic matter, is composed of a low-concentration liquid radioactive waste filtration step (S210), a high-concentration liquid radioactive waste filtration step (S220), an organic liquid radioactive waste filtration step (S230), a high-concentration liquid radioactive waste coagulation and precipitation step (S240), an organic liquid radioactive waste coagulation and precipitation step (S250), a miscellaneous solid radioactive waste classification and treatment step (S260), and an organic compound decomposition step (S270), as clearly shown in Fig. 3.

[0033] The above low-concentration liquid radioactive waste filtration step (S210) separates foreign substances and oil contained in the low-concentration liquid radioactive waste using a foreign substance separator and an oil separator.

[0034] The above high-concentration liquid radioactive waste filtration step (S220) separates foreign substances and oil contained in the high-concentration liquid radioactive waste using a foreign substance separator and an oil separator.

[0035] The above organic liquid radioactive waste filtration step (S230) separates foreign substances and oil contained in the organic liquid radioactive waste using a foreign substance separator and an oil separator.

[0036] The above high-concentration liquid radioactive waste coagulation and sedimentation step (S240) coagulates and sediments the high-concentration liquid radioactive waste from which foreign substances and oil have been removed in the above high-concentration liquid radioactive waste filtration step (S220), and performs solid-liquid separation.

[0037] The above organic liquid radioactive waste coagulation and sedimentation step (S250) coagulates and sediments the organic liquid radioactive waste from which foreign substances and oil have been removed in the above organic liquid radioactive waste filtration step (S230), and performs solid-liquid separation.

[0038] The above miscellaneous solid radioactive waste classification and treatment step (S260) collects solid radioactive waste, such as foreign substances and oil separated in the low-concentration, high-concentration, and organic liquid radioactive waste filtration steps (S210)(S220)(S230) and precipitates separated from high-concentration and organic liquid radioactive waste in the high-concentration and organic liquid radioactive waste coagulation and precipitation steps (S240)(S250), classifies the collected foreign substances, oil, and solid radioactive waste as miscellaneous solid radioactive waste, and treats them as miscellaneous solid radioactive waste.

[0039] The above organic compound decomposition step (S270) decomposes organic compounds contained in the organic liquid radioactive waste from which solid radioactive waste has been removed in the above organic liquid radioactive waste aggregation and sedimentation step (S250) using underwater plasma.

[0040] Referring to the attached drawings Figs. 2 and 4, the main treatment step (S300), which removes radioactive contaminants contained in the liquid radioactive waste that has passed through the pretreatment step (S200), separates the condensate from which radioactive contaminants have been removed into gas and liquid, and generates exhaust gas and discharge liquid, is composed of a centrifugal thin film separation and evaporation drying step (S310) of the liquid radioactive waste, a radioactive dried powder packaging treatment step (S320), a first condensation step (S330), a second condensation step (S340), and a condensate storage step (S350).

[0041] The above-mentioned centrifugal thin film separation and evaporation drying step (S310)) of the liquid radioactive waste separates fine radioactive particles through centrifugal thin film separation using a thin film cyclone dryer equipment from low-concentration inorganic liquid radioactive waste from which foreign substances and oil have been removed in the low-concentration inorganic liquid radioactive waste filtration step (S210) of the pretreatment step (S200), high-concentration liquid radioactive waste from which solid radioactive waste such as precipitates has been removed, and organic liquid radioactive waste from which organic compounds have been decomposed in the organic compound decomposition step, and then evaporates and dries the separated radioactive fine particles to produce radioactive dried powder.

[0042] The above radioactive dry powder packaging treatment step (S320) processes the radioactive dry powder generated in the centrifugal thin film separation and evaporation drying step (S310) of the liquid radioactive waste by packaging it in a high-integrity container.

[0043] The above first condensation step (S330) condenses the liquid vapor in the exhaust gas containing the liquid vapor evaporated in the centrifugal thin film separation and evaporation drying step (S310) of the liquid radioactive waste using a condenser.

[0044] The above second condensation step (S340) condenses the liquid vapor in the exhaust gas containing liquid vapor that has passed through the above first condensation step (S330) using a gas-liquid dual-flow centrifuge.

[0045] The above condensate storage step (S350) collects the condensate condensed in the above first and second condensation steps (S330) (S340) and stores it in a storage tank.

[0046] Referring to the attached drawings, Figs. 2 and 5 to 7, the post-treatment step (S400), which purifies the exhaust gas and discharge liquid that are separated and discharged in the main treatment step (S300) and discharges the purified exhaust gas and discharge liquid to the exhaust and drainage system of a building, is composed of an exhaust gas filtration step (S410), a condensate purification step (S420), and an environmental discharge monitoring step (S430).

[0047] The exhaust gas filtration step (S410) above filters the exhaust gas from which liquid vapor has been removed by passing through the secondary condensation step (S330) of the main treatment step (S300) and then exhausts it, and its composition consists of a dust collection step (S410a), a preliminary filtration step (S410b), a main filtration step (S410c), and a final filtration step (S410d).

[0048] The above dust collection step (S410a) removes dust contained in the exhaust gas from which liquid vapor has been removed by passing through the secondary condensation step (S320) of the main treatment step (S300) using a dust collection means, and it is preferable to use a cyclone equipment combining a cyclone and a bag filter or a dust scrubber as the dust collection means.

[0049] The above preliminary filtration step (S410b) removes dust that may be contained in the exhaust gas from which dust has been removed by passing through the above dust collection step (S410a) using a preliminary filter.

[0050] The above filtration step (S410c) removes fine particles that may be contained in the exhaust gas that has passed through the above preliminary filtration step (S410b) using a high-performance filter, and it is preferable to use a HEPA filter as the high-performance filter.

[0051] The above final filtration step (S410d) removes iodine (I) that may be contained in the exhaust gas that has passed through the above filtration step (S410c) using an activated carbon filter.

[0052] The above condensate purification step (S420) purifies and discharges the condensate stored in the condensate tank during the condensate storage step (S340) of the above main treatment step (S300), and is composed of a first purification step (S420a), a second purification step (S420b), and a purified water storage step (S420c).

[0053] The above first purification step (S420a) is to produce purified water by passing the condensate through a membrane separation means, and it is preferable to use microfiltration (MF) and reverse osmosis (RO) equipment as the membrane separation means.

[0054] The above second purification step (S420b) removes ionic compounds contained in the purified water using an ion exchange resin in the purified water generated in the above first purification step (S420a).

[0055] The above purified water storage step (S420c) stores the purified water that has passed through the above secondary purification step (S420b) in a purified water storage tank and drains it when necessary.

[0056] The above environmental emission monitoring step (S430) monitors the air quality where the exhaust gas is exhausted after passing through the exhaust gas filtration step (S410) and the water quality where the condensate is discharged after passing through the condensate purification step (S420).

[0057]

[0058] The integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant according to the present invention, having the above-described configuration, classifies liquid radioactive waste of various properties and conditions generated during the decommissioning of a nuclear power plant into low-concentration, high-concentration, and organic liquid radioactive waste, and sequentially performs a suitable pretreatment process according to the properties and conditions of each liquid radioactive waste, a main treatment process for removing radioactive contaminants contained in the liquid radioactive waste after the pretreatment process is completed, and a post-treatment process for purifying the exhaust gas and discharge liquid generated through the main treatment process, and then discharges the purified exhaust gas and purified water. This has the advantage of significantly improving the treatment efficiency of liquid radioactive waste while reducing treatment costs, as well as significantly reducing the amount of radioactive waste resin and secondary radioactive waste generated.

[0059]

[0060] As such, parties to the art to which the present invention pertains will understand that the technical configuration of the present invention described above may be implemented in other specific forms without altering the technical concept or essential features of the present invention.

[0061] Therefore, the embodiments described above should be understood as illustrative in all respects and not limiting, and the scope of the invention is defined by the claims set forth below rather than by the detailed description above, and all modifications or variations derived from the meaning and scope of the claims and equivalent concepts thereof should be interpreted as being included within the scope of the invention.

[0062]

[0063] The present invention has the potential to be applied to constructing an integrated treatment system for liquid radioactive waste generated during the decommissioning of a nuclear power plant, which can significantly improve the treatment efficiency of liquid radioactive waste and reduce treatment costs, as well as greatly reduce the amount of radioactive waste generated, such as radioactive waste resin, and secondary radioactive waste, by classifying the liquid radioactive waste generated during the decommissioning of a nuclear power plant into low-concentration, high-concentration, and organic liquid radioactive waste, sequentially carrying out a suitable pretreatment process according to the properties and conditions of each liquid radioactive waste, a main treatment process to remove radioactive contaminants contained in the liquid radioactive waste after the pretreatment process is completed, and a post-treatment process to purify the exhaust gas and discharge liquid generated through the main treatment process, and then discharging the purified exhaust gas and purified water.

Claims

1. A liquid radioactive waste classification storage step (S100) in which liquid radioactive waste generated at the hatch of a nuclear power plant is classified into low-concentration liquid radioactive waste, high-concentration liquid radioactive waste, and organic liquid radioactive waste and stored in separate storage tanks; In the above liquid radioactive waste separation and storage step (S100), a pretreatment step (S200) for separating and collecting foreign substances, oil, impurities, precipitates, and solids contained in the liquid radioactive waste stored in each storage tank, and decomposing organic matter; A main treatment step (S300) for removing radioactive contaminants contained in the liquid radioactive waste that has passed through the above pretreatment step (S200), separating the condensate from which radioactive contaminants have been removed into gas and liquid, and generating exhaust gas and discharge liquid; An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising a post-treatment step (S400) for purifying the exhaust gas and discharge liquid that are separated and discharged in the above main treatment step (S300), and discharging the purified exhaust gas and discharge liquid into the exhaust and drainage system of a building.

2. In Paragraph 1, The above preprocessing step (S200) is, A low-concentration liquid radioactive waste filtration step (S210) for separating foreign substances and oil contained in low-concentration liquid radioactive waste using a foreign substance separator and an oil separator; A high-concentration liquid radioactive waste filtration step (S220) for separating foreign substances and oil contained in the high-concentration liquid radioactive waste using a foreign substance separator and an oil separator; An organic liquid radioactive waste filtration step (S230) for separating foreign substances and oil contained within the organic liquid radioactive waste using a foreign substance separator and an oil separator; A high-concentration liquid radioactive waste coagulation and sedimentation step (S240) in which foreign substances and oil have been removed in a high-concentration liquid radioactive waste filtration step (S220) and a solid-liquid separation is performed; An organic liquid radioactive waste coagulation and sedimentation step (S250) in which foreign substances and oil have been removed in the above organic liquid radioactive waste filtration step (S230) and an organic liquid radioactive waste coagulation and sedimentation step (S250) are performed, and solid-liquid separation is carried out; A solid radioactive waste classification and treatment step (S260) for collecting foreign substances and oil separated in the low-concentration, high-concentration, and organic liquid radioactive waste filtration steps (S210)(S220)(S230) and precipitates separated from the high-concentration and organic liquid radioactive waste in the high-concentration and organic liquid radioactive waste coagulation and precipitation steps (S240)(S250), classifying the collected foreign substances, oil, and solid radioactive waste as miscellaneous solid radioactive waste, and treating them as miscellaneous solid radioactive waste; An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising an organic compound decomposition step (S270) in which organic compounds contained in organic liquid radioactive waste from which solid radioactive waste has been removed in the organic liquid radioactive waste coagulation and sedimentation step (S250) are decomposed using underwater plasma.

3. In Paragraph 1, The above main processing step (S300) is, A centrifugal thin-film separation and evaporation drying step (S310) of liquid radioactive waste in which fine radioactive particles are separated by centrifugal thin-film separation using a thin-film cyclone dryer equipment, and the separated radioactive fine particles are evaporated to produce radioactive dried powder; the low-concentration liquid radioactive waste from which foreign substances and oil have been removed in the low-concentration liquid radioactive waste filtration step (S210) of the pretreatment step (S200), the high-concentration liquid radioactive waste from which solid radioactive waste such as precipitates has been removed, and the organic liquid radioactive waste from which organic compounds have been decomposed in the organic compound decomposition step; and; A radioactive dry powder packaging treatment step (S320) in which the radioactive dry powder generated in the centrifugal thin film separation and evaporation drying step (S310) of the above liquid radioactive waste is packaged in a high-integrity container for treatment; A first condensation step (S330) in which the liquid vapor in the exhaust gas containing the liquid vapor evaporated in the centrifugal thin film separation and evaporation drying step (S310) of the above liquid radioactive waste is condensed using a condenser; A second condensation step (S340) for condensing the liquid vapor in the exhaust gas containing liquid vapor that has passed through the first condensation step (S330) using a gas-liquid dual-flow centrifugal separator; An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising a condensate storage step (S350) in which the condensate condensed in the above first and second condensation steps (S330) (S340) is collected and stored in a storage tank.

4. In Paragraph 1, The above post-processing step (S400) is, An exhaust gas filtration step (S410) for filtering and exhausting the exhaust gas from which liquid vapor has been removed by passing through the secondary condensation step (S330) of the main treatment step (S300); A condensate purification step (S420) for purifying and discharging the condensate stored in the condensate tank during the condensate storage step (S340) of the above main processing step (S300); An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising an environment discharge monitoring step (S430) for monitoring the water quality of the condensate discharged after passing through the exhaust gas filtration step (S410) and passing through the condensate purification step (S420).

5. In Paragraph 4, The above exhaust gas filtration step (S410) is, A dust collection step (S410a) for removing dust contained in the exhaust gas from which liquid vapor has been removed by passing through the secondary condensation step (S320) of the main treatment step (S300) using a dust collection means; A preliminary filtration step (S410b) for removing dust that may be contained in the exhaust gas from which dust has been removed by passing through the dust collection step (S410a) using a preliminary filter; A main filtration step (S410c) for removing fine particles that may be contained in the exhaust gas that has passed through the above preliminary filtration step (S410b) using a high-performance filter; An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising a final filtration step (S410d) that removes iodine (I) that may be contained in the exhaust gas passing through the above-mentioned filtration step (S410c) using a charcoal filter.

6. In Paragraph 4, The above condensate purification step (S420) is, A first purification step (S420a) for generating purified water by passing the condensate through a membrane separation means; A second purification step (S420b) for removing ionic compounds contained in the purified water using an ion exchange resin in the purified water generated in the first purification step (S420a); An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by comprising a purified water storage step (S420c) in which purified water that has passed through the above second purification step (S420b) is stored in a purified water storage tank and drained when necessary.

7. In Paragraph 5, The dust collection means of the dust collection step (S410a) above is, An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by a cyclone device combining a cyclone and a bag filter.

8. In Paragraph 5, The dust collection means of the dust collection step (S410a) above is, An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by being a dust scrubber.

9. In Paragraph 5, The high-performance filter of the above filtration step (S410c) is, An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by being a HEPA filter.

10. In Paragraph 6, The membrane separation treatment means of the above first water purification step (S420a) is, An integrated treatment method for liquid radioactive waste generated during the decommissioning of a nuclear power plant, characterized by being a microfiltration (MF) and reverse osmosis (RO) device.

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