Process for disposing of composite structure containing radioactive waste

Abstract

The present invention provides a process for disposing of a composite structure containing radioactive waste, the process being for containing and solidifying a high-dose concentrated waste liquid in a drum, and disposing of a composite structure, which is a large concrete loading container in which the drum is contained. The process for disposing of a composite structure containing radioactive waste, of the present invention, comprises the steps of: providing a support structure at the lower portion of the composite structure in which radioactive waste is contained; forming a penetration part by perforating the lower portion of a concrete container forming the composite structure after the step of providing the support structure; performing a separation process of separating out the radioactive waste contained therein through the penetration part after the step of forming the penetration part; and cutting and disassembling the composite structure after the step of performing the separation process.

Description

Treatment process of complex structures containing radioactive waste

[0001] The present invention relates to a process for treating a composite structure containing radioactive waste, wherein high-dose concentrated waste liquid is contained in a drum and solidified, and the composite structure, which is a large concrete loading container containing the drum, is disposed of.

[0002] Radioactive waste, a byproduct of nuclear power, is radioactive waste discharged from nuclear power plants and research laboratories. This radioactive waste is divided into high-level radioactive waste, low-level radioactive waste, which refers to the residue remaining after liquid waste disposal, and various parts, including clothing and gloves used by operators and maintenance personnel.

[0003] Radioactive waste storage facilities house large, rectangular concrete containers, called composite structures, containing high-dose concentrated waste liquid. These structures consist of drums containing solidified concentrated waste liquid, which are then placed within a large concrete container, and the drums and containers are then cement-grouted. Disposing of these composite structures requires assessing the radionuclide inventory and characterizing the waste contained within. However, the methods and processes for doing so are inadequate.

[0004] Additionally, there is a problem that the radiation exposure of workers may increase during the process of cutting and dismantling composite structures.

[0005] Accordingly, the present invention has been proposed to solve the above-mentioned problems, and the purpose of the present invention is to provide a process for processing a composite structure containing radioactive waste, which removes radioactive waste from the composite structure and facilitates cutting and dismantling operations while reducing radiation exposure of workers.

[0006] Another object of the present invention is to provide a treatment process for a composite structure containing radioactive waste, which can easily perform physical and chemical decontamination and separation processes for radioactive waste in the composite structure.

[0007] In order to achieve the above object of the present invention, the present invention provides a process for treating a composite structure containing radioactive waste, comprising the steps of: installing a support structure at the bottom of a composite structure containing radioactive waste; forming a penetration portion by penetrating the bottom of a concrete container forming the composite structure after the step of installing the support structure; performing a separation process for separating radioactive waste contained therein through the penetration portion after the step of forming the penetration portion; and cutting and dismantling the composite structure after the step of performing the separation process.

[0008] It is preferable that the step of performing the above-mentioned radioactive waste separation process includes a step of separating non-solidified internal waste of the radioactive waste and a step of removing radioactive waste attached to the wall surface of the drum forming the composite structure.

[0009] It is preferable to include a step of collecting a sample of the built-in waste after the step of forming a penetration by penetrating the lower part of the concrete container to evaluate the radioactive material inventory and radioactivity characteristics.

[0010] It is preferable to include a step of decontaminating internal waste by injecting a decontaminating solution through the above-mentioned penetration after the step of forming the above-mentioned penetration.

[0011] The present invention can reduce radiation exposure of workers cutting and dismantling composite structures by forming a penetrating portion in the lower part of the composite structure, removing decontamination and radioactive waste through the penetrating portion, and then cutting and dismantling the composite structure.

[0012] The present invention can prevent the spread of secondary waste that may occur during the cutting and dismantling process by first removing radioactive waste contained in a composite structure, and can prevent additional contamination by radioactive materials in advance.

[0013] FIG. 1 is a flowchart illustrating a processing process of a composite structure containing radioactive waste to explain an embodiment of the present invention.

[0014] FIG. 2 is a schematic diagram showing an example of installing a support structure in a composite structure to explain an embodiment of the present invention.

[0015] FIG. 3 is a schematic diagram showing an example of a penetration formed at the bottom of a composite structure to explain an embodiment of the present invention.

[0016] FIG. 4 is a schematic diagram illustrating an expanded penetration section for physical decontamination and separation of radioactive waste to explain an embodiment of the present invention.

[0017] FIG. 5 is a schematic diagram showing a composite structure in a state where the physical and chemical decontamination and separation process of radioactive waste has been completed to explain an embodiment of the present invention.

[0018] FIG. 6 is a conceptual diagram for performing a process of cutting and dismantling a composite structure after completing a decontamination and separation process to explain an embodiment of the present invention.

[0019] Hereinafter, embodiments of the present invention will be described in detail with reference to the attached drawings so that those skilled in the art can easily implement the present invention. However, the present invention may be implemented in various other forms and is not limited to the embodiments described herein. In the drawings, parts irrelevant to the description have been omitted for clarity of description, and the same reference numerals will be assigned to identical or similar components throughout the specification.

[0020] Figure 1 is a schematic diagram for explaining an embodiment of the present invention, showing a processing process or processing method for a composite structure containing radioactive waste.

[0021] The processing process of a composite structure containing radioactive waste according to an embodiment of the present invention includes a step (S101) of installing a support structure (103) at the bottom of the composite structure (100), a step (S103) of forming a penetration portion (120a) at the bottom of the composite structure (100), a step (S105) of collecting a sample, a step (S107) of evaluating the nuclide inventory and radioactive properties, a step (S109) of separating the built-in waste, and a step (S111) of cutting and dismantling the composite structure (100).

[0022] The composite structure (100) comprises a drum (110) containing high-dose concentrated waste liquid and a concrete container (120) containing the drum (110) and is cement grouted. The concentrated waste liquid contained in the drum (110) can be maintained in a solidified state.

[0023] The step (S101) of installing a support structure (103) at the bottom of the composite structure (100) is to install a support structure (103) capable of supporting the composite structure (100) at the bottom of the composite structure (100), as illustrated in FIG. 2. At this time, it is preferable that the support structure (103) be installed so that sufficient working space is maintained at the bottom of the composite structure (100). That is, it is preferable that the space at the bottom of the composite structure (100) be maintained to a degree where workers and equipment can be installed to create a penetration portion (120a) or collect samples.

[0024] After the step (S101) of installing a support structure (103) at the bottom of the composite structure (100), a penetration portion (120a) is formed at the bottom of the composite structure (100) (S103). It is preferable that the penetration portion (120a) be formed by penetrating the bottom surface of the concrete container (120) (see FIG. 3). In this way, the structure in which the penetration portion (120a) penetrates the bottom surface of the concrete container (120) is intended to facilitate separation of the internal waste by using its own weight or gravity in a subsequent process.

[0025] After the step (S103) of forming a penetration portion (120a) at the bottom of the composite structure (100), the process of collecting a sample (S105) is performed. The step of collecting a sample (S105) can collect a sample of radioactive waste contained inside the drum (110) through the penetration portion (120a). Then, after the step of collecting a sample (S105), the process of evaluating the radioactive waste inventory and radioactive properties (S107) is performed. This is to evaluate the radioactive waste inventory and radioactive properties, etc. in order to dispose of the composite structure (100).

[0026] After the nuclide inventory and radioactivity characteristic evaluation step (S107), the process of the built-in waste separation step (S109) is performed. In the built-in waste separation step, the process of the step of separating unsolidified built-in waste can be performed first (see FIG. 4). And after the process of the step of separating unsolidified built-in waste is performed, the process of the step of removing radioactive waste attached to the wall surface of the drum (110) forming the composite structure (100) can be performed (see FIG. 4). At this time, the built-in waste accommodated inside the drum (110) is separated using a physical decontamination and separation device (113) (see FIG. 4). Therefore, after the built-in waste separation step (S109), only the drum (110) and the concrete container (120) remain, as shown in FIG. 5. Of course, the process of the additional decontamination step can be performed after the built-in waste separation step (S109).

[0027] After performing the process of the internal waste separation step (S109), the step of cutting and dismantling the composite structure (100) (S111) is performed (see FIG. 6).

[0028] Meanwhile, after the step (S103) of forming a penetrating portion (120a) at the bottom of the composite structure (100), a process of decontaminating internal waste by injecting a decontaminating solution through the penetrating portion (120a) can be performed.

[0029] The present invention can effectively separate radioactive waste by gravity when internal waste is first separated through the penetration portion (120a) at the bottom of the concrete container (120). Furthermore, when internal waste separation is performed through subsequent physical / chemical decontamination, etc., radiation exposure to workers can be reduced when cutting and dismantling the large concrete container (120).

[0030] In addition, the present invention has the effect of preventing the spread of secondary waste that may occur during the cutting and dismantling process and blocking additional contamination by radioactive materials in advance, since the internal waste of a large concrete container (120) is separated first.

[0031] Although the preferred embodiments of the present invention have been described above, the present invention is not limited thereto, and various modifications can be made within the scope of the claims, the detailed description of the invention, and the attached drawings, and it is obvious that this also falls within the scope of the present invention.

Claims

1. A step of installing a support structure at the bottom of a complex structure containing radioactive waste. A step of forming a penetration portion by penetrating the lower part of the concrete container forming the composite structure after the step of installing the above support structure, A step of performing a separation process for separating radioactive waste contained inside through the penetration part after the step of forming the penetration part, and A step of cutting and dismantling the composite structure after performing the above separation process. Process for treating a complex structure containing radioactive waste.

2. In claim 1, The step of performing the above radioactive waste separation process is A step of separating the non-solidified internal waste of the above radioactive waste, and A step for removing radioactive waste attached to the wall surface of the drum forming the above composite structure. Process for treating a complex structure containing radioactive waste.

3. In claim 1, A step of collecting samples of the built-in waste after the step of forming a penetration by penetrating the lower part of the above concrete container to evaluate the nuclide inventory and radioactivity characteristics. Process for treating a complex structure containing radioactive waste.

4. In claim 1, A step of decontaminating internal waste by injecting a decontaminating solution through the above-mentioned penetration after the step of forming the above-mentioned penetration. Process for treating a complex structure containing radioactive waste, including:

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