Method for treating radioactive waste glass fiber
The heat treatment of glass fibers in a canister system with monitoring ensures compliance and reduces disposal costs by addressing the volume and contamination issues of glass fiber materials.
Patent Information
- Application Number
- JP2024537086
- Authority / Receiving Office
- JP · JP
- Patent Type
- Patents
- Current Assignee / Owner
- Priority Date
- 2022-01-04
- Filing Date
- 2023-01-02
- Publication Date
- 2025-08-04
- Estimated Expiration
- 2043-01-02
AI Technical Summary
Glass fiber heat insulating materials used in nuclear power plants have a large volume compared to their mass and low contamination, making them unsuitable for disposal without additional processing, and thus require a method to enhance disposability and reduce volume to lower disposal costs.
A method involving heat treatment of radioactive waste glass fibers in a canister, allowing for repeated loading and unloading, volume reduction, and subsequent transfer, with monitoring via laser and thermocouple to ensure compliance with disposal standards.
Enhances disposability of glass fiber materials by reducing volume and lowering disposal costs through effective heat treatment and subsequent processing.
Smart Images

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Abstract
Description
Technical Field
[0001] The present invention relates to a method for treating radioactive waste glass fibers.
Background Art
[0002] In nuclear power plants, heat insulating materials based on glass fibers are used for heat insulation and protection of operators for main pipes, high-temperature equipment, etc. In particular, a large amount of glass fiber heat insulating material is used for heat insulation and blocking of the peripheral pipes and equipment of steam generators. At present, such glass fibers are loaded into drums (e.g., 200 L, etc.) and manually compressed to prepare for disposal. In such a process, the glass fibers are crushed into small particles and do not meet the requirements for dispersibility, making them unsuitable for disposal, and thus there is a problem that additional processing is required.
Summary of the Invention
Problems to be Solved by the Invention
[0003] The problem to be solved by the present invention is to improve the ease of disposal of glass fiber heat insulating materials in consideration of the fact that they have a large volume compared to their mass and a low degree of contamination, and can thus be classified as almost very low-level or self-disposal target waste.
[0004] In particular, it is to be able to greatly contribute to the disposal or deregulation of radioactive waste through a heat treatment process and subsequent treatment processes for glass fiber heat insulating materials.
[0005] Also, it is to be able to reduce the volume reduction cost of such glass fiber heat insulating materials and ultimately enable the reduction of radioactive waste disposal costs.
[0006] The problems of the present invention are not limited to the problems mentioned above, and other problems not mentioned will be clearly understood by those skilled in the art from the following description.
Means for Solving the Problems
[0007] A method for treating radioactive waste glass fibers according to an aspect of the present invention for achieving the above object includes the steps of preparing radioactive waste glass fibers; loading the radioactive waste glass fibers into a canister; heat-treating the canister under set conditions via a heat treatment unit; and transferring the radioactive waste glass fibers with reduced volume by the heat treatment in a reduced state.
[0008] Further, the canister includes a first lower canister at the lower part and a first upper canister that can be attached to and separated from the first lower canister, and based on the attachment and separation, the radioactive waste glass fibers can be repeatedly loaded and the heat treatment can be repeatedly executed.
[0009] Also, the glass fibers with reduced volume are accommodated in a transfer unit for external transfer in a state of being accommodated on the first lower canister, and the first lower canister is arranged inside the transfer unit adjacent to each other together with a second lower canister different from the first lower canister and a third lower canister different from the first lower canister.
[0010] Further, the first lower canister, the second lower canister, and the third lower canister are provided by being stacked in the horizontal or vertical direction with respect to each other, and the first lower canister to the third lower canister are formed with protruding structure parts at the upper or lower part, and fitting parts corresponding to the protruding structure parts are formed at the upper or lower part and are attached and fixed to each other.
[0011] Also, the degree of volume reduction by the heat treatment of the radioactive waste glass fibers on the canister is grasped via a laser water level measurement module, and when the degree of volume reduction satisfies a preset standard, the first lower canister is separated from the first upper canister.
[0012] In addition, the temperature state of the radioactive waste glass fiber with respect to the canister is grasped via a thermocouple, and when the temperature state satisfies a preset standard along with the degree of volume reduction, the first lower canister is separated from the first upper canister.
[0013] In addition, the first lower canister and the first upper canister are provided so as to be attachable and detachable, and the radioactive waste glass fiber can be charged and discharged.
[0014] In addition, the canister and the heat treatment unit are located in a space where an air conditioner is installed, the heat treatment of the radioactive waste is performed in the space, and the product by the heat treatment is discharged via the air conditioner.
Advantages of the Invention
[0015] According to the method for treating radioactive waste glass fiber of the present invention as described above, there is one or more of the following effects.
[0016] In the present invention, since the glass fiber heat insulating material has a much larger volume than its mass and a low contamination degree, its disposability can be enhanced in consideration of the fact that it can be classified as almost extremely low-level or self-disposal target waste.
[0017] In particular, the heat treatment process and subsequent treatment process for the glass fiber heat insulating material can greatly contribute to the disposal or regulatory release of radioactive waste.
[0018] In addition, the volume reduction cost of such a glass fiber heat insulating material can be saved, and ultimately the radioactive waste disposal cost can be reduced.
[0019] The problems of the present invention are not limited to the problems mentioned above, and other problems not mentioned will be clearly understood by those skilled in the art from the following description.
Brief Description of the Drawings
[0020]
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Embodiments for Carrying Out the Invention
[0021] Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings. The advantages and features of the present invention, as well as the methods for achieving them, will become clear by referring to the embodiments described in detail later together with the accompanying drawings. However, the present invention is not limited to the embodiments disclosed below and can be realized in various different forms. This embodiment is merely to complete the disclosure of the present invention and is provided to fully inform those with ordinary knowledge in the technical field to which the present invention belongs of the scope of the invention. The present invention is defined only by the scope of the claims. The same reference numerals throughout the specification refer to the same components.
[0022] Referring to FIG. 1, a method for treating radioactive waste glass fiber O according to an embodiment of the present invention first prepares the radioactive waste glass fiber O. Next, the radioactive waste glass fiber O is loaded into the canister 110.
[0023] Here, the canister 110 is heat-treated under set conditions through a heat treatment unit. By the heat treatment, the radioactive waste glass fiber O is transferred in a state where its volume has decreased.
[0024] Referring to FIGS. 2 to 4, the canister 110 includes a first lower canister 112 and a first upper canister 111. The first upper canister 111 of the canister 110 can be attached to and separated from the first lower canister 112.
[0025] Based on the attachment and separation, the radioactive waste glass fiber O is repeatedly loaded into the first lower canister 112 and the first upper canister 111, and the heat treatment is repeatedly executed.
[0026] The glass fiber O with reduced volume in this way is accommodated in a transfer unit 60 for external transfer while being accommodated on the first lower canister 112. The first lower canister 112 is arranged inside the transfer unit 60 adjacent to a second lower canister 212 different from the first lower canister 112.
[0027] Furthermore, the first lower canister 112 can be arranged inside the transfer unit 60 adjacent to a second lower canister 212 different from the first lower canister 112 and a third lower canister 312 different from the first lower canister 112.
[0028] That is, although it is disclosed that the first lower canister 112 to the third lower canister 312 are all arranged, this is exemplary, and the number can be further increased within the provided limit.
[0029] The first lower canister 112, the second lower canister 212, and the third lower canister 312 are provided by being stacked horizontally or vertically with respect to each other. In the first lower canister 112 to the third lower canister 312, protruding structure parts 1121, 2121, 3121 are formed at the upper part or the lower part.
[0030] Here, in the first lower canister 112 to the third lower canister 312, fitting parts 1122, 2122, 3122 corresponding to the protruding structure parts 1121, 2121, 3121 are formed at the upper part or the lower part, and they can be mounted and fixed to each other.
[0031] The degree of volume reduction by the heat treatment of the radioactive waste glass fiber O is grasped on the canister 110 via a laser water level measurement module (not shown). When the degree of volume reduction satisfies a preset standard, the first lower canister 112 is separated from the first upper canister 111.
[0032] Furthermore, the temperature state of the canister 110 with respect to the radioactive waste glass fiber O is grasped via a thermocouple (not shown). When the radioactive waste glass fiber O satisfies a preset standard together with the degree of volume reduction, the first lower canister 112 is separated from the first upper canister 111.
[0033] Basically, the first lower canister 112 and the first upper canister 111 described above are provided so that they can be mounted and separated, and the radioactive waste glass fiber O can be inserted and discharged.
[0034] The canister 110 and the heat treatment unit are located in a space part where an air conditioner is installed. The heat treatment of the radioactive waste of the canister 110 and the heat treatment unit is performed in the space part. Furthermore, the product generated by the heat treatment is discharged via the air conditioner.
[0035] The glass fiber O was heat-treated under the conditions shown in Table 1 below.
[0036] [Table 1]
[0037] According to Embodiment 1, it can be confirmed that the glass fiber O before processing and the glass fiber O after processing have changed from the state of FIG. 5 before processing to the state of FIG. 6 after processing. According to Embodiment 2, it can be confirmed that the glass fiber O before processing and the glass fiber O after processing have changed from the state of FIG. 7 before processing to the state of FIG. 8 after processing. According to Embodiment 3, it can be confirmed that the glass fiber O before processing and the glass fiber O after processing have changed from the state of FIG. 9 before processing to the state of FIG. 10 after processing. According to Embodiment 4, it can be confirmed that the glass fiber O before processing and the glass fiber O after processing have changed from the state of FIG. 11 before processing to the state of FIG. 12 after processing.
[0038] Although the glass fiber O has the characteristic of being large in volume with respect to mass, the volume can be reduced by the above-described processing, the ease of disposal can be enhanced, and the release of regulations related to radioactive waste treatment can be achieved. Furthermore, the volume reduction cost can be increased, and the radioactive waste disposal cost can be saved.
[0039] The embodiments of the present invention have been described above with reference to the accompanying drawings. However, those having ordinary knowledge in the technical field to which the present invention pertains can understand that the present invention can be implemented in other specific forms without changing its technical idea and essential features. Therefore, it must be understood that the above-described embodiment is illustrative in all respects and not restrictive.
Claims
1. A method for treating radioactive waste glass fibers, comprising: preparing radioactive waste glass fibers; loading the radioactive waste glass fibers into a canister; heat-treating the canister under set conditions through a heat treatment unit; and transferring the radioactive waste glass fibers in a state where their volume has decreased due to the heat treatment, wherein the canister includes a first lower canister at the bottom and a first upper canister that can be attached to and separated from the first lower canister, based on the attachment and separation, the radioactive waste glass fibers can be repeatedly loaded and the heat treatment can be repeatedly performed, the glass fibers with decreased volume are accommodated on the first lower canister and then accommodated in a transfer unit for external transfer, wherein the first lower canister is disposed inside the transfer unit adjacent to each other together with a second lower canister different from the first lower canister and a third lower canister different from the first lower canister, a method for treating radioactive waste glass fibers.
2. The first lower canister, the second lower canister, and the third lower canister are provided by being stacked in a horizontal or vertical direction with respect to each other, wherein the first lower canister to the third lower canister has a protruding structure formed at the upper or lower part, and a fitting part corresponding to the protruding structure is formed at the upper or lower part and is attached and fixed to each other. The method for treating radioactive waste glass fibers according to Claim 1.
3. The degree of volume reduction of the radioactive waste glass fibers due to the heat treatment is grasped on the canister through a laser water level measurement module, when the degree of volume reduction satisfies a preset standard, the first lower canister is separated from the first upper canister. The method for treating radioactive waste glass fibers according to Claim 1.
4. The temperature state of the canister with respect to the radioactive waste glass fibers is grasped through a thermocouple, when the temperature state satisfies a preset standard together with the degree of volume reduction, the first lower canister is separated from the first upper canister. The method for treating radioactive waste glass fibers according to Claim 3.
5. The method for treating radioactive waste glass fibers according to claim 1, wherein the first lower canister and the first upper canister are provided so as to be attachable and detachable, and the radioactive waste glass fibers can be charged and discharged.
6. The canister and the heat treatment unit are located in a space where an air conditioner is installed. The heat treatment of the radioactive waste is performed in the space, and the product by the heat treatment is discharged through the air conditioner. The method for treating radioactive waste glass fibers according to claim 1.
Citation Information
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