PLANT DISMANTLING MANAGEMENT DEVICE, PLANT DISMANTLING MANAGEMENT METHOD, AND PLANT DISMANTLING MANAGEMENT PROGRAM

Abstract

To allow the persons concerned in interests of waste of a nuclear power plant, etc., to efficiently share information.SOLUTION: A plant demolition management device comprises a disposal planning part which plans disposal plan information as a process table up to reuse or final disposal after waste is discharged from a plant based upon design information on the waste discharged from the plant and the radiation dose of the waste, and a storage part which stores the planned disposal plan information, and the disposal planning part determines reuse and final disposal as part of the disposal plan information based upon purchase price information on recycled waste of the wastes and disposal price information on finally disposed waste of the waste.SELECTED DRAWING: Figure 9

Description

[Technical field]

[0001] The present invention relates to a plant dismantling management device, a plant dismantling management method, and a plant dismantling management program. [Background technology]

[0002] Once a nuclear power plant has completed its mission, it is decommissioned in a planned manner over a long period of time. Radioactive waste generated during decommissioning is disposed of in a safe location so as not to affect the human environment. Non-radioactive waste may be disposed of as general industrial waste, or it may be reused in other ways. In either case, it is important to manage the waste accurately and efficiently in the period from the decision to decommission the plant to disposal and reuse.

[0003] The dismantling and packaging method of Patent Document 1 creates a plan to dismantle waste such as piping and equipment discharged from a nuclear power plant and store it in a container, assuming that the waste will be transported to a disposal facility. The radioactive solid waste treatment method of Patent Document 2 divides the radioactive solid waste into multiple parts with different disposal methods based on the results of calculating the radiation dose of each part of the radioactive solid waste.

[0004] The method of managing waste from dismantled nuclear facilities described in Patent Document 3 specifies the radiation dose of the waste before dismantling, attaches a barcode or the like to each piece of waste after dismantling, and manages the information stored in the barcode or the like by computer until final disposal. The barcode or the like stores the waste number, source, radiation dose, record of storage in container, radiation dose on the container surface, etc. [Prior art documents] [Patent documents]

[0005] [Patent Document 1] WO 99 / 39253 [Patent Document 2] JP 2002-207098 A [Patent Document 3] JP 2001-141887 A Summary of the Invention [Problem to be solved by the invention]

[0006] During the period from the decision to decommission to reuse or final disposal, many stakeholders will be involved in the waste, including the reactor manufacturer, nuclear power plant, operators of processing facilities, temporary storage facilities, transport companies, reuse facilities, final disposal facilities, etc. Each stakeholder will need past and future information on the waste they are involved with, depending on their position. This will be the same even after reuse or final disposal is completed.

[0007] However, Patent Document 1 focuses on how to dismantle waste and store it in containers based on constraints such as container size and worker radiation exposure, and does not mention the sharing of waste information by stakeholders. Patent Document 2 focuses on adjusting the radiation dose of the resulting solid (ingot) and again does not mention the sharing of waste information by stakeholders. Patent Document 3 is somewhat aware of waste traceability, but does not specifically mention the shared use of waste information by stakeholders. Therefore, the purpose of this project is to enable stakeholders in waste from nuclear power plants and other facilities to share information efficiently. [Means for solving the problem]

[0008] The plant dismantling management device of the present invention includes a disposal plan creation unit that creates disposal plan information, which is a schedule for the waste from being discharged from a plant until the waste is reused or finally disposed of, based on design information of the waste and the radiation dose of the waste, and a storage unit that stores the planned disposal plan information, wherein the disposal plan creation unit: When receiving purchase price information from the reuse facility terminal device or when receiving disposal price information from the final disposal facility terminal device, the reuse information or final disposal information that is a part of the disposal plan information stored in the storage unit is updated. , characterized by: Other means will be described in the description of the embodiment of the invention. Effect of the Invention

[0009] According to the present invention, stakeholders of waste, such as nuclear power plants, can efficiently share information. [Brief description of the drawings]

[0010] [Figure 1] A diagram explaining the reuse and disposal method of radioactive waste. [Diagram 2] FIG. 1 is a diagram illustrating the flow of waste. [Diagram 3] FIG. 2 is a diagram illustrating a system and a radiation source. [Figure 4] 2 is a diagram illustrating the configuration of a plant dismantling management device. FIG. [Diagram 5] FIG. 2 is a diagram illustrating an example of design information. [Figure 6] FIG. 13 is a diagram showing an example of decontamination information. [Figure 7] FIG. 11 is a diagram showing an example of dismantling information. [Figure 8] FIG. 11 is a diagram illustrating an example of measurement information. [Figure 9] FIG. 11 is a diagram showing an example of disposal plan information. [Figure 10] FIG. 11 is a diagram showing an example of waste history information. [Figure 11] 13 is a flowchart of a plan creation process. [Figure 12] 13 is a flowchart of a measurement process procedure. [Figure 13] 13 is a flowchart of a history creation process; DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0011] Hereinafter, an embodiment of the present invention (referred to as the "present embodiment") will be described in detail with reference to the drawings. The present embodiment is an example of recycling or final disposal of waste generated in conjunction with the decommissioning of a nuclear power plant. The present invention is applicable to both boiling water reactors and pressurized water reactors, and is also applicable to general plants that discharge radioactive waste.

[0012] (Methods of recycling and disposal of radioactive waste) Figure 1 is a diagram explaining the methods of recycling and disposing of radioactive waste. During normal operation of a nuclear power plant, spent fuel is generated. Uranium and plutonium are extracted from the spent fuel. These can be reused as fuel itself (line 51a). The waste liquid remaining after extraction is solidified into glass as "high-level radioactive waste" and stored in metal containers, and finally "geological disposal". Geological disposal means burying it in bedrock more than 300 meters underground (line 51b).

[0013] After the decision to decommission a nuclear power plant, the spent fuel stored at the nuclear power plant will be reused and finally disposed of, just as it was during operation. What is unique about the decommissioning decision is that a large amount of equipment other than the spent fuel (reactors, generators, condensers, piping, etc.) is generated at once as waste. These equipment include "low-level radioactive waste" and other waste that does not emit radiation (lines 52a-52e). The subject of this invention is primarily these equipment.

[0014] Low-level radioactive waste with a high level of radiation (e.g., control rods that are a short distance from the reactor core) is dismantled, placed in containers, and then subjected to "intermediate depth disposal," which means burial at least 70 meters underground (line 52a). Low-level radioactive waste with a medium level of radiation (e.g., pumps that are a medium distance from the reactor core) is dismantled, placed in containers, and then subjected to "pit disposal," which means burial in a concrete pit installed shallow underground (line 52b).

[0015] Among low-level radioactive waste, those with low levels of radiation (such as concrete rubble that is far from the reactor core) are placed in containers and then "trench disposed of." Trench disposal refers to burying the waste shallowly underground without installing artificial structures such as pits (line 52c). Among low-level radioactive waste, those with a very small amount of radiation that does not affect human health (called "clearance material") are specially considered to be general industrial waste. Therefore, clearance material may be disposed of as industrial waste or may be reused (line 52d).

[0016] Non-radioactive waste is naturally reused or disposed of as industrial waste (line 52e). It is estimated that more than 90% by weight of the waste generated by the decommissioning of nuclear power plants is non-radioactive waste.

[0017] (Waste Stream) FIG. 2 is a diagram explaining the flow of waste. FIG. 2 shows an example in which a pipe 68 is reused or finally disposed of as waste generated after a decision to decommission a nuclear power plant. A nuclear power plant 62 (nuclear power plant operator) measures the radiation dose (for example, in units of "mSv / hour") of the pipe 68. This measurement may be an actual measurement using a measuring device, or an estimate (logical calculation) based on design information created by a manufacturer 61. Thereafter, measurements are repeated in various processes. The pipe 68 is a "system" consisting of many parts, for example, as shown in FIG. 3, and the radiation dose differs for each part. Therefore, the measurement here targets each part of the pipe.

[0018] Based on the measurement results, the nuclear power plant 62 decontaminates the piping 68 as necessary. Decontamination is the process of removing radioactive sources from the waste (described in detail later). Thereafter, decontamination may be repeated at any step. The nuclear power plant 62 dismantles the piping 68. Dismantling is the division of the waste into smaller units (parts) to facilitate decontamination, transportation, reuse, final disposal, etc., or to disperse the radioactive sources. Thereafter, dismantling may be repeated at any step. Thereafter, the dismantled piping 68 is transported to the treatment facility 63. Hereinafter, for the sake of simplicity, the part of the piping 68 that is generated as a result of the dismantling will also be referred to as "piping 68".

[0019] The processing facility 63 (processing facility operator) further dismantles the piping 68. Of the dismantled piping 68, the low-level radioactive waste is transported to a temporary storage facility 65. In FIG. 2, the piping 68 leaving the processing facility 63 retains the outline of a piping, but may be broken into small pieces. Cleared materials are transported to other facilities for the purpose of processing for reuse. Examples of reuse are benches in nuclear power plants, containers for storing low-level radioactive waste, etc. The "reuse facility" refers to these users.

[0020] The temporary storage facility 65 (operator of a temporary waste storage facility) stores dismantled pipes 68 transported from many treatment facilities in designated containers 71 and temporarily stores them in a designated location while waiting for a final disposal facility 66 to become available. The final disposal facility 66 (operator of a final waste disposal facility) receives the containers 71 from the temporary storage facility 65 and buries them underground. There may be multiple temporary storage facilities and multiple final disposal facilities. Furthermore, the treatment facilities and temporary storage facilities may be located in the vicinity of a nuclear power plant.

[0021] (Revenue and Mobile Processing Facilities) Generally, revenue management is performed for each nuclear power plant, reactor, or smaller system. Revenue is defined, for example, as "Revenue = Power Generation Revenue - Power Generation Cost - Decommissioning Cost + Revenue from Recycling." If some of the waste can be sold as recycled materials at a high price, the revenue from recycling will increase, and so will revenue. Also, for example, when decontaminating and dismantling waste, if mobile processing equipment (decontamination equipment, cutters, etc.) that can be moved and used jointly between multiple reactors or multiple stakeholders can be shared, decommissioning costs will decrease and revenue will increase.

[0022] (System and Radiation Source) FIG. 3 is a diagram for explaining the system and the radiation source. The system 49 has a pump 41, valves 42 and 43, and individual pipes 44 to 47. These are integrated equipment groups to transport water, for example, from a condenser to a reactor pressure vessel. In the case of a boiling water reactor in which water passes directly through the reactor pressure vessel, the system 49 may be slightly contaminated with radiation. Even if this is not the case, radioactive material 48 may be attached to the inside or outside of some of the pipes 45. In this case, when the radiation dose of each part of the system 49 is measured with a measuring instrument, it is found that only the radiation dose on the surface and periphery of the pipe 45 is significantly higher than the other parts. Such a radioactive material that is a source of radiation is also called a "radiation source."

[0023] (Decontamination methods) If there is no radioactive source attached and every part of system 49 shows a uniformly high radiation dose, it is possible to perform chemical decontamination on the entire system without dismantling the system. Chemical decontamination is a method in which, for example, a decontamination device is directly connected to system 49 and an agent (reducing agent, etc.) is poured into it.

[0024] If the radiation level is high only in the part of system 49 to which the radiation source is attached as a result of a radiation source being attached to a certain part, it is possible to dismantle system 49, remove piping 45, and perform mechanical decontamination on piping 45 or on piping 45 that has been further dismantled in half. Mechanical decontamination is, for example, a method of spraying an abrasive on a part of the piping or rubbing it with a brush.

[0025] Furthermore, if the radiation level in pipe 45 is so high that workers cannot safely dismantle system 49, a robot or the like can be used to chemically decontaminate system 49, and then pipe 45 can be removed and mechanically decontaminated.

[0026] (Configuration of plant dismantling management device, etc.) 4 is a diagram for explaining the configuration of the plant dismantling management device 1. The plant dismantling management device 1 is a general computer, and includes a central control device 11, an input device 12 such as a mouse and a keyboard, an output device 13 such as a display, a main memory device 14, an auxiliary memory device 15, and a communication device 16. These are connected to each other by a bus. The auxiliary memory device 15 stores design information 31, decontamination information 32, dismantling information 33, measurement information 34, disposal plan information 35, and waste history information 36 (all of which will be described in detail later).

[0027] The disposal plan creation unit 21, information collection unit 22, and history provision unit 23 in the main memory device 14 are programs. The central control device 11 realizes the functions of each program (described in detail later) by reading these programs from the auxiliary memory device 15 and loading them into the main memory device 14. The auxiliary memory device 15 may be configured independent of the plant dismantling management device 1. The plant dismantling management device 1 is capable of communicating with each of the following devices via the network 8.

[0028] The power plant terminal device 2 arranged in the nuclear power plant 62 of FIG. The processing facility terminal device 3 disposed in the processing facility 63 of FIG. The temporary storage facility terminal device 4 arranged in the temporary storage facility 65 of FIG. The final disposal facility terminal device 5 disposed in the final disposal facility 66 of FIG. · Reuse facility terminal device 6 located at the reuse facility A carrier terminal device 7 installed at a carrier (not shown)

[0029] (Design information) 5 is a diagram showing an example of the design information 31. The design information 31 is created, for example, for each product shipped from a manufacturer. In the design information 31, the following information is stored in association with each other. The product ID (field 101) is an identifier that uniquely identifies a product that will become waste in the future. The place of manufacture (field 102) is the name of the manufacturer and factory where the product was manufactured. The product type (column 103) is a statement expressing the type of product by its function. Here, the "condenser secondary side piping unit" corresponds to the system 49 in FIG. 3, for example. The shipping date (field 104) is the date the product was shipped.

[0030] The use (column 105) is the type of liquid flowing through the pipe. The material (column 106) is the material that makes up the product. The inner diameter (column 107) is the inner diameter of the pipe. Note that "#" is used to abbreviate different numerical values ​​(hereinafter the same). The inner diameter of the pipe may be stored for each pipe constituting the system (the same applies to the outer diameter). The Outside Diameter (column 108) is the outside diameter of the pipe.

[0031] Length (column 109) is the length of the lineage. The flow rate (column 110) is the maximum volume of liquid flowing through the system per unit time. Design drawings (column 111) are design drawings created by the manufacturer. Design drawings may have the format of three-dimensional CAD data or point cloud data. In addition to a diagram showing the outer shape of the product, design drawings include a table showing the expected radiation dose for each part when used under normal conditions, a graph showing the attenuation characteristics of the radiation dose for each part after operation is stopped, and a graph showing the performance of the product.

[0032] (Decontamination information) 6 is a diagram showing an example of the decontamination information 32. Each time waste is decontaminated, the plant dismantling management device 1 creates a record of the decontamination information 32. In the decontamination information 32, the following information is stored in association with each other. The waste ID (field 121) is an identifier that uniquely identifies the waste. The waste ID before the initial dismantling is the same as the product ID. The waste ID may identify a system before dismantling, or it may identify a part after dismantling. In this embodiment, for ease of understanding, the parts resulting from the dismantling of "P01" are given names such as "P011", "P012", etc. (a hierarchical numbering structure). Each waste is tagged with a waste ID in an arbitrary manner.

[0033] The decontamination date (field 122) is the date on which the waste was decontaminated. The decontaminant ID (field 123) is an identifier that uniquely identifies the stakeholder who decontaminated the waste. The stakeholder is the entity (corporation) that handles the waste, specifically, the nuclear power plant 62, the processing facility 63, the temporary storage facility 65, the final disposal facility 66, and the waste transporter and recycling facility (not shown) in FIG. 2. The decontamination method (field 124) is the method of decontamination that was performed. Methods other than the above-mentioned chemical decontamination and mechanical decontamination (electrochemical decontamination) may be stored. Furthermore, the decontamination method may be further subdivided and stored according to the agent, equipment, etc. used.

[0034] The decontamination coefficient (column 125) is a value obtained by dividing the radiation dose of the waste immediately before the decontamination by the radiation dose immediately after the decontamination. The plant dismantling management device 1 determines whether or not it is necessary to perform decontamination again based on the decontamination coefficient. Secondary waste (column 126) is secondary waste generated by decontamination, and may contain radioactive material removed from the waste to be decontaminated, or may no longer contain radioactive material as a result of chemical changes, etc. If the secondary waste continues to contain radioactive material, it is managed as a separate waste (a new waste ID is assigned) and is subject to treatment such as evaporation and condensation. Secondary waste is also subject to tracing, just like original waste.

[0035] (Demolition information 33) 7 is a diagram showing an example of the dismantling information 33. Each time waste is dismantled, the plant dismantling management device 1 creates a record of the dismantling information 33. In the dismantling information 33, the following information is stored in association with each other. The waste ID (field 131) is the same as the waste ID in Fig. 6. However, the waste ID here is a combination of the waste ID before demolition and the waste ID after demolition in order to clarify what was dismantled before demolition and what was generated after demolition.

[0036] The dismantling date (field 132) is the date on which the waste was dismantled. The dismantler ID (field 133) is an identifier that uniquely identifies the stakeholder (eg, reference numeral 62 in FIG. 2) who dismantled the waste. The dismantling method (field 134) is the method of dismantling that was carried out. Here, in addition to the specific method of dismantling, the heavy machinery, tools, etc. used for the dismantling may be stored. The dismantling method may be, for example, "crush with a hammer until pieces are less than x mm in size." In this case, the dismantling position field 135 may be left blank, and the waste ID after dismantling may be the same as the waste ID before dismantling (no waste ID is assigned to each granular individual). The dismantling location (field 135) is information indicating the location at which the waste before dismantling was dismantled (cut).

[0037] (Measurement information) 8 is a diagram showing an example of the measurement information 34. In this embodiment, before and after decontamination or dismantling of waste, the plant dismantling management device 1 creates a record of the measurement information 34. In the measurement information 34, the following information is stored in association with each other. The waste ID (field 141) is the same as the waste ID in FIG. The measurement date (field 142) is the date on which the radiation dose of the waste was measured. The measurer ID (field 143) is an identifier that uniquely identifies the stakeholder (eg, reference numeral 63 in FIG. 2) who measured the radiation dose of the waste. The measured value (field 144) is the value of the radiation dose. The unit is, for example, mSv / hour. The measured value is the criterion for determining whether or not the waste corresponds to a clearance item. The summary (field 145) is any memorandum about the measurement, in this case the timing of the measurement.

[0038] (Disposal plan information) FIG. 9 is a diagram showing an example of the disposal plan information 35. The disposal plan information 35 is a schedule for each waste (system, etc.) before dismantling, from when the decision to decommission the reactor is made until the waste is reused or finally disposed of. The processes include dismantling, decontamination, temporary storage, reuse, and final disposal. First, the plant dismantling management device 1 initially creates the disposal plan information 35. At this stage, the content of the disposal plan information 35 is a "plan." After that, when the process actually progresses, the process may or may not be executed as planned. Each of the terminal devices 2 to 6 in FIG. 4 transmits an implementation report of the process related to itself to the plant dismantling management device 1. When the received implementation report differs from the plan, the plant dismantling management device 1 overwrites and updates the plan with the content of the received implementation report.

[0039] In the disposal plan information 35, pre-dismantling information (column 161), primary dismantling information (column 162), secondary dismantling information (column 163), temporary storage information (column 164), final disposal information (column 165), reuse information (column 166), and profits (column 167) are stored in mutual association. Primary dismantling is carried out, for example, by the nuclear power plant 62 in Fig. 2, and secondary dismantling is carried out, for example, by the treatment facility 63 in Fig. 2.

[0040] Looking at pre-demolition information column 161, the following can be seen: The waste (system) "P01" is first chemically decontaminated in its entirety before being dismantled at the nuclear power plant "F01". The plant dismantling management device 1 determines whether or not to dismantle the waste "P01" based on the radiation dose of the waste. The plant dismantling management device 1 also determines the decontamination method based on the radiation dose and design information 31 (material, shape, etc.) (same below). The decontamination method is underlined. This indicates that the decontamination will be carried out using the mobile processing equipment mentioned above (the same applies to the dismantling method described below).

[0041] Looking at the primary dismantling information column 162, the following can be seen. · Waste "P01" is then broken down into waste "P011" and waste "P012" in the treatment facility "F01". "F01" is an ID that identifies the nuclear power plant in the pre-dismantling information. In other words, the dismantling will be carried out within the nuclear power plant. The dismantling is performed by "removing the bolt at ○m from the left" of the waste "P01." The plant dismantling management device 1 estimates the radiation source from the distribution of radiation dose in the waste "P01," determines the dismantling position and the number of waste pieces after dismantling, and determines the tools, etc. for dismantling based on the design information 31 (materials, etc.) (same below).

[0042] Looking at the secondary dismantling information column 163, the following can be seen: Next, in the treatment facility “F02”, the waste “P011” is broken down into waste “P0111” and waste “P0112”. The dismantling is carried out by "cutting the waste material "P011" from the left at ●m." In the same treatment facility “F02”, waste “P012” is broken down into waste “P0121” and waste “P0122”. The dismantling is carried out by "cutting the waste "P012" in the middle. The dismantling is carried out by the mobile processing facility mentioned above. The wastes “P0111”, “P0112”, “P0121” and “P0122” after dismantling are mechanically decontaminated. Mechanical decontamination was chosen here because, for example, the system was dismantled in two stages, making mechanical decontamination (e.g., brushing by a robot) possible.

[0043] Looking at the temporary storage information column 164, the following can be seen. Next, in the temporary storage facility "F03," wastes "P0111" and "P0112" are temporarily stored in "Type A containers." Temporary storage is a measure until a final disposal facility or recycling facility is decided. In the same storage facility “F03”, wastes “P0121” and “P0122” are temporarily stored in “Type B containers”. The plant dismantling management device 1 determines the type of container based on the radiation dose of the waste, the design information 31, the size after dismantling, etc.

[0044] Looking at the final disposal information column 165, the following can be seen: Finally, in the final disposal facility "F04", waste "P0111" and waste "P0112" contained in type A containers will be disposed of in a pit.

[0045] Looking at the reuse information column 166, the following can be seen: Meanwhile, in the recycling facility "F05", waste "P0121" and waste "P0122" contained in the B-type container are removed from the container and become materials.

[0046] Revenue (column 167) is the revenue mentioned above. Here, revenue management is performed on a system basis.

[0047] (Waste history information) Fig. 10 is a diagram showing an example of waste history information 36. In response to a request from each of the terminal devices 2 to 7 in Fig. 4, the plant dismantling management device 1 creates waste history information 36 that explains the history of each waste, including waste after dismantling. In the waste history information 36, the following information is stored in association with each other.

[0048] The waste ID (field 171) is the same as the waste ID in Figure 6. However, the waste ID here often identifies the waste after it has been dismantled at least once. Each stakeholder will pay attention to the waste here from their own perspective. The original waste ID (field 172) is an identifier that uniquely identifies the original waste before the waste in the waste ID field 171 was dismantled. In the example of Figure 10, a stakeholder is requesting the history of waste "P0111." Waste "P0111" is the result of the original waste (system, etc.) "P01" being dismantled twice. The design information (column 173) is all the contents of the design information 31 for the product "P01."

[0049] The decontamination history (field 174) indicates, for example, when, at what facility, and by what method the waste "P0111" and its pre-dismantling waste were decontaminated, and what the decontamination factor was for the decontamination. The decontamination date and decontamination factor may be a schedule. The dismantling history (field 175) indicates when, at what facility, and by what method the waste "P0111" and its pre-dismantled waste were dismantled. The dismantling date may be a planned date. The measurement history (column 176) shows when and at what facility the radiation doses of waste "P0111" and the waste before dismantling were measured, and what the values ​​were. The summary column shows the waste before dismantling for which the values ​​were measured.

[0050] The temporary storage information (field 177) indicates when, in which facility, and in what container the waste "P0111" and its pre-dismantling waste were stored. The storage period may be a planned period. The final disposal information (field 178) indicates when, at what facility, and by what method the waste "P0111" was finally disposed of. The disposal date may be a planned date.

[0051] (Processing Procedure) The processing procedures of this embodiment will be described below. There are three processing procedures, namely, a plan creation processing procedure, a measurement processing procedure, and a history creation processing procedure.

[0052] (Planning process) Figure 11 is a flowchart of the plan creation process. Suppose that a decision has been made to decommission a certain nuclear power plant. In step S201, the disposal plan creation unit 21 of the plant dismantling management device 1 identifies waste. Specifically, the disposal plan creation unit 21 receives a waste ID of a certain bundle of waste (e.g., a system) from the power plant terminal device 2. For convenience of explanation, it is assumed here that the waste ID "P01" (condenser secondary side piping unit) has been received.

[0053] In step S202, the disposal plan creation unit 21 acquires the design information 31 (FIG. 5). Specifically, the disposal plan creation unit 21 receives the design information 31 of the waste "P01" from the power plant terminal device 2 or the manufacturer 61. One of the design drawings included in the design information 31 describes the designed radiation dose when the product "P01" is normally operated and the attenuation characteristics after operation is stopped for each part (piping, etc.) of the product "P01".

[0054] In step S203, the disposal plan creation unit 21 acquires the measurement information 34 (FIG. 8). Specifically, the disposal plan creation unit 21 receives the measurement information 34 of the waste "P01" at the most recent past point in time from the power plant terminal device 2. The measurement information here has the format of one record of the measurement information 34 in FIG. 8.

[0055] In step S204, the disposal plan creation unit 21 estimates the radiation dose. Specifically, the disposal plan creation unit 21 estimates the radiation dose using the design information 31 (design value) acquired in step S202 and the measurement information 34 (actual measurement value) acquired in step S203. The radiation dose estimated here is, for example, a time-series radiation dose for each part starting from the current time point. There are cases where a part where the radiation dose should be sufficiently low by design actually exhibits a high radiation dose.

[0056] In step S205, the disposal plan creation unit 21 identifies the radiation source. Specifically, the disposal plan creation unit 21 identifies the part (piping, etc.) that constitutes the waste "P01" that has the highest radiation dose. This part is likely to have a radiation source attached to it. The disposal plan creation unit 21 may identify the radiation source (reference numeral 48 in FIG. 3) based on an image captured by operating a camera by a robot.

[0057] In step S206, the disposal plan preparation unit 21 determines whether decontamination is necessary. Specifically, the disposal plan preparation unit 21 compares the radiation dose identified in step S205 with any of the following threshold values. Threshold 1: The upper limit that can ensure the safety of workers at nuclear power plants Threshold 2: Upper limit for applying the targeted disposal or recycling method

[0058] In step S207, the disposal plan preparation unit 21 judges whether decontamination is necessary. Specifically, if the radiation dose is equal to or greater than the threshold as a result of the comparison in step S206 (step S207 "Yes"), the disposal plan preparation unit 21 proceeds to step S209, otherwise (step S207 "No"), the disposal plan preparation unit 21 proceeds to step S208.

[0059] In step S208, the disposal plan creation unit 21 determines a dismantling method. Specifically, the disposal plan creation unit 21 determines a dismantling method for the waste "P01" based on the design information 31 (materials, etc.) and the size of the container to be stored. If a mobile processing facility is available, the disposal plan creation unit 21 determines to use it (similarly in steps S209 to S211).

[0060] In step S209, the disposal plan preparation unit 21 determines a decontamination method before dismantling. Specifically, the disposal plan preparation unit 21 determines a decontamination method for the waste "P01" based on the design information 31 and the radiation dose estimated in step S204. Since the waste "P01" is a system through which water flows, the disposal plan preparation unit 21 selects chemical decontamination. Furthermore, an agent suitable for the material (heat-resistant steel) and radiation dose of the waste "P01" is selected.

[0061] In step S210, the disposal plan preparation unit 21 determines a dismantling method. Specifically, the disposal plan preparation unit 21 determines a dismantling method for the waste "P01" based on the design information 31, the radiation dose, the size of the container to be stored, etc., on the premise that the waste "P01" has been decontaminated by the decontamination method determined in step S209.

[0062] In step S211, the disposal plan preparation unit 21 determines a decontamination method after dismantling. Specifically, the disposal plan preparation unit 21 determines a decontamination method for each part (piping, etc.) after the waste "P01" is dismantled based on the design information 31 and the radiation dose. At this time, the disposal plan preparation unit 21 determines the dismantling method on the premise that the waste "P01" is decontaminated by the decontamination method determined in step S209 and that the waste "P01" is dismantled by the dismantling method determined in step S210. The decontamination method determined here is, for example, mechanical decontamination of the pipes that are divided in half.

[0063] By repeating the processing of steps S209 to S211, the disposal plan preparation unit 21 may prepare a plan for decontaminating and dismantling the waste "P01" in stages over multiple periods.

[0064] In step S212, the disposal plan creation unit 21 determines reuse and final disposal. Specifically, first, the disposal plan creation unit 21 receives the reuse materials that the reuse facility needs and the timing of needing them together with the purchase price from the reuse facility terminal device 6 of each reuse facility. Secondly, the disposal plan creation unit 21 receives information on the waste that the final disposal facility can accept in the future and the timing of acceptance together with the disposal price from the final disposal facility terminal device 5 of each final disposal facility.

[0065] Third, the disposal plan creation unit 21 determines a reuse facility that can reuse the waste "P01", etc., and / or a final disposal facility that can finally dispose of the waste. "Waste "P01", etc." collectively refers to the waste "P01" and the parts generated after its dismantling (the same applies below). The disposal plan creation unit 21 determines the reuse facility based on, for example, the purchase price presented by each reuse facility, and determines the final disposal facility based on, for example, the acceptance timing presented by each final disposal facility.

[0066] In step S213, the disposal plan creation unit 21 determines the storage method and the transport company. Specifically, first, the disposal plan creation unit 21 transmits the amount of waste "P01" etc. to be temporarily stored and the period until final disposal to the temporary storage facility terminal device 4 of each temporary storage facility. Then, the temporary storage facility terminal device 4 replies to the plant dismantling management device 1 with the possibility of temporary storage and the storage fee.

[0067] Secondly, the disposal plan creation unit 21 transmits the amount of waste "P01" and the like, the radiation dose, etc., transported between the nuclear power plant and each facility and between each facility to the transporter terminal device 7 of each transporter. Then, the transporter terminal device 7 replies to the plant dismantling management device 1 with the possibility of transport and the transport fee. Third, the disposal plan creation unit 21 determines a temporary storage facility capable of temporarily storing the waste "P01" and the like, and a transporter capable of transporting the same. The disposal plan creation unit 21 determines the temporary storage facility based on the storage fee offered by each temporary storage facility, and determines the transporter based on the transport fee offered by each transporter.

[0068] In step S214, the disposal plan preparation unit 21 creates disposal plan information 35 (FIG. 9). Specifically, the disposal plan preparation unit 21 creates disposal plan information 35 based on the contents determined in steps S208 to S213, and stores it in the auxiliary storage device 15. At this stage, each facility (interested party) associated with the waste "P01" in the disposal plan information 35 can access the plant dismantling management device 1 via its own terminal device, and can visually check the records of the disposal plan information 35 related to the waste "P01".

[0069] After that, the stakeholders will carry out decontamination, dismantling, temporary storage, transportation, reuse, and final disposal based on the disposal plan information 35. Each stakeholder will carry out the part of the disposal plan information 35 that they are responsible for. However, there are cases where they cannot carry out the plan as planned.

[0070] In step S215, the disposal plan creation unit 21 receives an implementation report from the terminal device. Specifically, the disposal plan creation unit 21 receives an implementation report on the pre-planned demolition, decontamination, etc. from the terminal devices 2-6 (FIG. 4) of each stakeholder. The implementation report includes information such as, for example, "The demolition of F01 was carried out as planned" and "The decontamination of F0111 was changed to chemical decontamination." The disposal plan creation unit 21 stores the received implementation report in the auxiliary storage device 15.

[0071] In step S216, the disposal plan creation unit 21 stores the changes to the plan. Specifically, if the implementation report received in step S215 indicates a change from the plan, the disposal plan creation unit 21 overwrites the changed content to the disposal plan information 35 and stores it in the auxiliary storage device 15. Thereafter, the plan creation processing procedure is terminated. Steps S215 and S216 are repeated each time each stakeholder carries out dismantling, decontamination, etc., so that the disposal plan information 35 is always kept up to date. Among the processes in steps S201 to S216, the subject of the process of acquiring information from the interested parties may be the information collecting unit 22. In this case, the information collecting unit 22 passes the acquired information to the disposal plan preparation unit 21 and entrusts it with the subsequent processes.

[0072] (Measurement process procedure) Fig. 12 is a flow chart of the measurement process procedure. Each stakeholder can measure the radiation dose of the waste at any time. In this embodiment, each stakeholder other than the transporter measures the radiation dose of the waste before and after dismantling or decontamination of the waste via their own terminal devices 2-6, and transmits the measured radiation dose to the plant dismantling management device 1. For convenience of explanation, a processing facility 63 (Fig. 2) is used as an example of a stakeholder.

[0073] In step S301, the information collecting unit 22 of the plant dismantling management device 1 determines whether or not preparation for dismantling is complete. Specifically, when the information collecting unit 22 receives a notification from the processing facility terminal device 3 of the processing facility 63 that preparation for dismantling of waste is complete (step S301 "Yes"), the information collecting unit 22 proceeds to step S303, and otherwise (step S301 "No"), the information collecting unit 22 proceeds to step S302.

[0074] In step S302, the information collecting unit 22 judges whether or not preparation for decontamination is completed. Specifically, when the information collecting unit 22 receives a notice from the processing facility terminal device 3 of the processing facility 63 that preparation for decontamination of waste is completed (step S302 "Yes"), the information collecting unit 22 proceeds to step S303, and otherwise (step S302 "No"), the information collecting unit 22 returns to step S301.

[0075] In step S303, the information collecting unit 22 acquires the radiation dose. Specifically, first, the information collecting unit 22 receives the radiation dose of the waste from the processing facility terminal device 3 of the processing facility 63. Secondly, the information collecting unit 22 creates a record of the measurement information 34 (FIG. 8) based on the received radiation dose.

[0076] In step S304, the information collecting unit 22 judges whether or not the dismantling is completed. Specifically, when the information collecting unit 22 receives information from the processing facility terminal device 3 of the processing facility 63 that the dismantling of the waste is completed (step S304 "Yes"), the information collecting unit 22 proceeds to step S306, and otherwise (step S304 "No"), the information collecting unit 22 proceeds to step S305.

[0077] In step S305, the information collecting unit 22 judges whether the decontamination is completed. Specifically, when the information collecting unit 22 receives information from the processing facility terminal device 3 of the processing facility 63 that the decontamination of the waste is completed (step S305 "Yes"), the information collecting unit 22 proceeds to step S306, and otherwise (step S305 "No"), the information collecting unit 22 returns to step S304.

[0078] In step S306, the information collecting unit 22 acquires the radiation dose etc. Specifically, first, the information collecting unit 22 receives the radiation dose of the waste from the processing facility terminal device 3 of the processing facility 63. Secondly, the information collecting unit 22 creates a record of the measurement information 34 (FIG. 8) based on the received radiation dose.

[0079] Thirdly, the information collecting unit 22 receives details of the dismantling or decontamination of the waste from the processing facility terminal device 3 of the processing facility 63. The information received here may be the same as the implementation report in step S215 (FIG. 11). Fourth, the information collecting unit 22 creates a record of the dismantling information 33 (FIG. 7) or the decontamination information 32 (FIG. 6) based on the received details of the dismantling or decontamination, and then ends the measurement processing procedure. As is apparent from the above, the plant dismantling management device 1 constantly maintains the decontamination information 32 (FIG. 6), dismantling information 33 (FIG. 7), and measurement information 34 (FIG. 8) in the latest state.

[0080] (History creation process procedure) 13 is a flowchart of the history creation process. Each stakeholder can request the history of the waste that it handles from the plant dismantling management device 1. For ease of explanation, it is assumed that the temporary storage facility 65 (FIG. 2), as an example of a stakeholder, wants to know the history of waste "P0111" in order to accept it.

[0081] In step S401, the history providing unit 23 of the plant dismantling management apparatus 1 receives a history request from a terminal device. Specifically, the history providing unit 23 receives a history request including the waste ID “P0111” from the temporary storage facility terminal device 4 of the temporary storage facility 65.

[0082] In step S402, the history providing unit 23 uses the search key to obtain relevant data from each piece of information. Specifically, the history providing unit 23 uses the waste ID "P0111" as the search key to search for the design information 31 (FIG. 5), decontamination information 32 (FIG. 6), dismantling information 33 (FIG. 7), measurement information 34 (FIG. 8), disposal plan information 35 (FIG. 9), and other information. Then, the history providing unit 23 obtains all data associated with "P0111." The "other information" here refers to the implementation report received by the disposal plan creation unit 21 in step S215 (FIG. 11).

[0083] In step S403, the history providing unit 23 creates the waste history information 36 (FIG. 10). Specifically, the history providing unit 23 creates the waste history information 36 with the waste ID "P0111" based on the data acquired in step S402. Note that, of the waste history information 36 created here, the data in the temporary storage information column 177 and the final disposal information column 178 are in the planning stage.

[0084] In step S404, the history providing unit 23 transmits the waste history information 36 (FIG. 10) to the terminal device. Specifically, the history providing unit 23 transmits the waste history information 36 created in step S403 to the temporary storage facility terminal device 4 of the temporary storage facility 65. Then, the history creation process ends.

[0085] (Effects of this embodiment) The effects of the plant dismantling management device of this embodiment are as follows. (1) The plant dismantling management system plans waste disposal processes and enables stakeholders to share waste history information. Therefore, the plant dismantling management system not only contributes to waste traceability but also significantly reduces the management costs of each stakeholder. (2) The plant dismantling management device can receive information about waste from interested parties. (3) The plant decommissioning management system can manage the dismantling, decontamination and temporary storage of waste leading to its reuse or final disposal. (4) The plant dismantling management device can identify radiation sources and then plan decontamination or dismantling methods accurately and efficiently.

[0086] (5) The plant decommissioning management device may be applied to the decommissioning of nuclear reactors. (6) The plant dismantling management device can determine methods of decontamination and dismantling using waste design information, etc. (7) The plant dismantling management device can manage the profits related to the process. (8) The plant dismantling management system can update the process based on actual results.

[0087] The present invention is not limited to the above-described embodiment, but includes various modified examples. For example, the above-described embodiment has been described in detail to easily explain the present invention, and is not necessarily limited to those including all of the configurations described. It is also possible to replace a part of the configuration of one embodiment with the configuration of another embodiment, and it is also possible to add the configuration of another embodiment to the configuration of one embodiment. It is also possible to add, delete, or replace a part of the configuration of each embodiment with another configuration.

[0088] In addition, the above-mentioned configurations, functions, processing units, processing means, etc. may be realized in part or in whole by hardware, for example, by designing them as integrated circuits. In addition, the above-mentioned configurations, functions, etc. may be realized in software by a processor interpreting and executing a program that realizes each function. Information such as the program, table, file, etc. that realizes each function can be stored in a memory, a recording device such as a hard disk or SSD (Solid State Drive), or a recording medium such as an IC card, SD card, or DVD. In addition, the control lines and information lines shown are those that are considered necessary for the explanation, and not all control lines and information lines in the product are necessarily shown. In reality, it can be considered that almost all components are connected to each other. [Explanation of symbols]

[0089] 1 Plant dismantling management device 2 Power station terminal equipment 3. Processing facility terminal equipment 4. Temporary storage facility terminal equipment 5 Final disposal facility terminal equipment 6 Reuse facility terminal equipment 7. Carrier terminal device 8 Network 11 Central control unit 12 Input Devices 13 Output Devices 14 Main memory 15 Auxiliary storage 16 Communication Equipment 21 Disposal Planning Division 22 Information Gathering Department 23 History Department 31 Design information 32 Decontamination Information 33 Dismantling Information 34 Measurement Information 35 Disposal plan information 36 Waste history information

Claims

1. a disposal plan creation unit that creates disposal plan information, which is a schedule for the waste from being discharged from the plant until it is reused or finally disposed of, based on design information of the waste to be discharged from the plant and the radiation dose of the waste; A storage unit that stores the planned disposal plan information; Equipped with The disposal plan creation unit includes: updating reuse information or final disposal information, which is a part of the disposal plan information stored in the storage unit, when receiving purchase price information from the reuse facility terminal device or receiving disposal price information from the final disposal facility terminal device; A plant dismantling management device comprising:

2. The waste material may include The facility is not intended to be used for the decommissioning of nuclear power plants, and 2. The plant dismantling management device according to claim 1 .

3. The disposal plan creation unit includes: determining a storage method and a transport company, which are part of the disposal plan information, based on storage fee information required for temporary storage of the waste and transport fee information for the waste; 2. The plant dismantling management device according to claim 1 .

4. The disposal plan creation unit includes: When there is a change in the plan based on implementation report information of the disposal plan, updating the storage unit with the changed content as disposal plan information; 2. The plant dismantling management device according to claim 1 .

5. The disposal plan creation section of the plant dismantling management device Based on design information of waste discharged from the plant and the radiation dose of the waste, a disposal plan information is prepared, which is a schedule for the waste from being discharged from the plant until it is reused or finally disposed of; The storage unit of the plant dismantling management device includes: storing the proposed disposal plan information; The disposal plan creation unit further includes: updating reuse information or final disposal information, which is a part of the disposal plan information stored in the storage unit, when receiving purchase price information from the reuse facility terminal device or receiving disposal price information from the final disposal facility terminal device; A plant dismantling management method comprising the steps of:

6. Computer, a disposal plan creation unit that creates disposal plan information, which is a schedule for the waste from being discharged from the plant until it is reused or finally disposed of, based on design information of the waste to be discharged from the plant and the radiation dose of the waste; A storage unit that stores the planned disposal plan information; A plant decommissioning management program for causing the plant to function as a The disposal plan creation unit further executing a process of updating reuse information or final disposal information, which is a part of the disposal plan information stored in the storage unit, when receiving purchase price information from the reuse facility terminal device or receiving disposal price information from the final disposal facility terminal device; A demolition management program featuring:

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