Plant demolition management device, plant demolition management method, and plant demolition management program

Abstract

To enable interested parties of waste from nuclear power plants or the like to efficiently share information.SOLUTION: A plant demolition management device includes: a disposal plan generation unit which plans disposal plan information being a schedule covering the process from the discharge of waste from the plant to its reuse or final disposal on the basis of design information of the waste discharged from the plant and the radiation dose of the waste; and a storage unit which stores the planned disposal plan information. The disposal plan generation unit stores, in the storage unit, information on the availability of a processing facility that can be shared among multiple reactors or among multiple entities handling 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 Art

[0002] When a nuclear power plant completes its mission, it is decommissioned systematically over a long period. Among the waste generated during decommissioning, radioactive waste is disposed of in a safe place so as not to affect the human environment. Non-radioactive waste may be disposed of as general industrial waste or may be reused otherwise. In any case, it is important to manage the waste accurately and efficiently during the period from the decommissioning decision to disposal and reuse.

[0003] The dismantling and packing method of Patent Document 1 creates a plan to dismantle waste such as pipes and equipment discharged from a nuclear power plant and store it in a container on the premise of transporting it to a disposal facility. The radioactive solid waste treatment method of Patent Document 2 divides radioactive solid waste into a plurality of parts with different disposal methods based on the result of calculating the radiation dose of each part of the radioactive solid waste.

[0004] The management method of nuclear facility dismantling waste in Patent Document 3 identifies the radiation dose of 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 a waste number, a source, a radiation dose, a storage record in a container, a radiation dose on the surface of the container, and the like.

Prior Art Documents

Patent Documents

[0005]

Patent Document 1

Patent Document 2

Patent Document 3

SUMMARY OF THE INVENTION

PROBLEMS TO BE SOLVED BY THE INVENTION

[0006] During the period from the decision to decommission a nuclear power plant to its reuse or final disposal, many stakeholders, including nuclear power plant manufacturers, nuclear power plants, treatment facilities, temporary storage facilities, transportation companies, reuse facilities, and final disposal facilities, will be involved in the waste. Each stakeholder, from their own perspective, needs past or future information about the waste they are involved in. The same is true even after reuse or final disposal is completed.

[0007] However, Patent Document 1 focuses on how to disassemble waste and store it in containers based on constraints such as the size of the container and the radiation exposure of workers, and does not mention information sharing of waste by stakeholders. Patent Document 2 focuses on adjusting the radiation dose of the resulting solid (ingot), and also does not mention information sharing of waste by stakeholders. Although Patent Document 3 has a general awareness of the traceability of waste, it does not specifically mention the joint use of waste information by stakeholders. Therefore, the object is to enable efficient information sharing among stakeholders of waste such as nuclear power plants.

MEANS FOR SOLVING THE PROBLEMS

[0008] The plant decommissioning management device of the present invention plans disposal plan information, which is a process schedule from when the waste is discharged from the plant until it is reused or finally disposed of, based on the design information of the waste discharged from the plant and the radiation dose of the waste, and includes a disposal plan creation unit and a storage unit for storing the planned disposal plan information. The disposal plan creation unit is characterized by storing in the storage unit information on the availability of processing facilities that can be jointly used between a plurality of nuclear reactors or between a plurality of entities handling the waste. Other means will be described in the mode for carrying out the invention.

Advantages 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

Figure 2

Figure 3

Figure 4

Figure 5

Figure 6

Figure 7

Figure 8

Figure 9

Figure 10

Figure 11

Figure 12

Figure 13

Embodiments for Carrying Out the Invention

[0011] Hereinafter, embodiments for carrying out the present invention (referred to as "the present embodiment") will be described in detail with reference to the drawings and the like. The present embodiment is an example of reusing or finally disposing of waste generated by 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] (Method for Recycling and Disposal of Radioactive Waste) FIG. 1 is a diagram for explaining a method for recycling and disposing of radioactive waste. During the period when a nuclear power plant is operating normally, 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 vitrified into glass and stored in a metal container as "high-level radioactive waste", and finally "stratified disposal" is carried out. Stratified disposal means burying it in the rock formation more than 300 m deep underground (line 51b).

[0013] After the decision to decommission a nuclear power plant, the spent fuel stored in the nuclear power plant is recycled and finally disposed of in the same way as during operation. What is unique after the decommissioning decision is that a large amount of various facilities other than spent fuel (nuclear reactor, generator, condenser, piping, etc.) are generated at once as waste. These various facilities include "low-level radioactive waste" and other waste that does not emit radiation (lines 52a to 52e). The object of the present invention is mainly these various facilities.

[0014] Among the low-level radioactive waste, those with a high radiation dose (for example, control rods with a small distance from the core) are disassembled, stored in a container, and then "medium-depth disposed". Medium-depth disposal means burying it in the ground more than 70 m deep underground (line 52a). Among the low-level radioactive waste, those with a medium radiation dose (for example, pumps with a medium distance from the core) are disassembled, stored in a container, and then "pit disposed". Pit disposal means burying it in a concrete pit installed in shallow ground (line 52b).

[0015] Among low-level radioactive waste, those with a low radiation dose (e.g., concrete blocks far from the reactor core) are stored in containers and then "trench-disposed." Trench-disposal means burying them without installing artificial structures like pits in shallow ground (line 52c). Among low-level radioactive waste, those with a negligible radiation dose that does not affect human health (referred to as "clearance items") are specifically regarded as general industrial waste. Therefore, clearance items are not only disposed of finally as industrial waste but can also be reused (line 52d).

[0016] Waste that does not emit radiation is, of course, reused or disposed of finally as industrial waste (line 52e). It is estimated that more than 90% by weight of the waste associated with the decommissioning of nuclear power plants is waste that does not emit radiation.

[0017] (Waste flow) Figure 2 is a diagram explaining the waste flow. Figure 2 shows an example where piping 68 is reused or disposed of finally as waste generated after the decision to decommission the nuclear power plant. Nuclear power plant 62 (nuclear power operator) measures the radiation dose of piping 68 (the unit is, for example, "mSv / h"). This measurement may be an actual measurement using a measuring instrument or an estimation (logical calculation) based on the design information prepared by manufacturer 61. Thereafter, measurements will be repeated in various processes. Piping 68 is a "system" consisting of many parts as shown in, for example, Figure 3, and the radiation dose varies for each part. Therefore, the measurement here targets each part of the piping.

[0018] Based on the measurement results, the nuclear power plant 62 decontaminates the piping 68 as necessary. Decontamination is the operation of removing the radiation source from the waste (details will be described later). Thereafter, decontamination can be repeated in any process. The nuclear power plant 62 disassembles the piping 68. Disassembly means dividing the waste into smaller units (parts) to facilitate decontamination, transportation, reuse, final disposal, etc., or to disperse the radiation source. Thereafter, disassembly can be repeated in any process. Then, the disassembled piping 68 is transported to the treatment facility 63. Thereafter, for the sake of simplicity of explanation, the parts of the piping 68 generated as a result of disassembly are also referred to as "piping 68".

[0019] The treatment facility 63 (treatment facility operator) further disassembles the piping 68. Among the disassembled piping 68, the low-level radioactive waste is transported to the temporary storage facility 65. In FIG. 2, the piping 68 going out from the treatment facility 63 maintains an outer shape like piping, but may be finely crushed. The clearance items are transported to other facilities for the purpose of treatment for reuse. Examples of reuse are benches inside the nuclear power plant, containers for storing low-level radioactive waste, etc. Note that the "reuse facility" is these users.

[0020] The temporary storage facility 65 (operator of the waste temporary storage facility) stores the disassembled piping 68 transported from many treatment facilities in a predetermined container 71, temporarily stores it at a designated location, and waits for the final disposal facility 66 to become available. The final disposal facility 66 (operator of the waste final disposal facility) accepts the container 71 from the temporary storage facility 65 and buries it underground. There may be a plurality of each of the temporary storage facility and the final disposal facility. Furthermore, the treatment facility and the temporary storage facility may be arranged close to the nuclear power plant.

[0021] (Revenue and Mobile Treatment Equipment) Generally, revenue management is carried out at nuclear power plants, nuclear reactors, or at a finer system unit level. Revenue is defined, for example, as "Revenue = Power generation income - Power generation costs - Decommissioning costs + Recycling income". If a part of the waste can be sold at a high price as recycled materials, the recycling income will increase, and so will the revenue. Also, for example, when decontaminating and dismantling waste, if mobile processing equipment (decontamination devices, cutters, etc.) that can be moved and jointly used among multiple reactors or multiple stakeholders can be shared, the decommissioning costs will decrease and the revenue will increase.

[0022] (System and radiation source) Figure 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 form an integrated group of facilities and, for example, convey water from a condenser to a reactor pressure vessel. In the case of a boiling water reactor where water passes directly through the reactor pressure vessel, the system 49 may be slightly contaminated with radiation. Even if that is not the case, radioactive substances 48 may be attached to the inside or outside of some of the pipes 45. In this case, when measuring the radiation dose of each part of the system 49 with a measuring instrument, it can be seen that only the radiation dose on the surface and around the pipe 45 is significantly higher compared to the others. Such radioactive substances that are the source of radiation are also called "radiation sources".

[0023] (Decontamination method) When there is no attachment of a radiation source or the like and all parts of the system 49 show a uniformly high radiation dose, it is possible to perform chemical decontamination on the entire system without disassembling the system. Chemical decontamination is, for example, a method of directly connecting a decontamination device to the system 49 and flowing a chemical agent (reducing agent, etc.).

[0024] As a result of a radiation source attaching to a certain part, if only the radiation dose of the part of the system 49 where the radiation source is attached is high, it is possible to disassemble the system 49, remove the pipe 45, and perform mechanical decontamination on the pipe 45 or on the pipe 45 that has been further disassembled into half. Mechanical decontamination is, for example, a method of spraying an abrasive on part of the pipe or rubbing it with a brush.

[0025] Furthermore, when the radiation dose of the pipe 45 is so high that the worker cannot safely disassemble the system 49, it is also possible to have the robot or the like perform chemical decontamination of the system 49 and then remove the pipe 45 and perform mechanical decontamination on the pipe 45.

[0026] (Configuration etc. of the plant disassembly management device) FIG. 4 is a diagram for explaining the configuration etc. of the plant disassembly management device 1. The plant disassembly 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 storage device 14, an auxiliary storage device 15, and a communication device 16. These are interconnected by a bus. The auxiliary storage device 15 stores design information 31, decontamination information 32, disassembly 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 providing unit 23 in the main storage device 14 are programs. The central control device 11 realizes the functions of each program (to be described in detail later) by reading these programs from the auxiliary storage device 15 and loading them into the main storage device 14. The auxiliary storage device 15 may have a configuration independent of the plant disassembly management device 1. The plant disassembly management device 1 can communicate with the following devices via the network 8.

[0028] · The power plant terminal device 2 arranged in the nuclear power plant 62 in FIG. 2 · The processing facility terminal device 3 arranged in the processing facility 63 in FIG. 2 · The temporary storage facility terminal device 4 arranged in the temporary storage facility 65 in FIG. 2 · The final disposal facility terminal device 5 arranged in the final disposal facility 66 in FIG. 2 · The reuse facility terminal device 6 arranged in the reuse facility · The transporter terminal device 7 arranged in the transporter (not shown)

[0029] (Design information) FIG. 5 is a diagram showing an example of design information 31. The design information 31 is created for each product shipped from a manufacturer, for example. In the design information 31, the following information is stored in association with each other. The product ID (column 101) is an identifier that uniquely identifies a product that will become future waste. The manufacturing location (column 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 the product in terms of its function. Here, the "condenser secondary side piping unit" corresponds to, for example, line 49 in FIG. 3. The shipping date (column 104) is the date on which 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 constituting the product. The inner diameter (column 107) is the inner diameter of the pipe. Note that "#" indicates different numerical values in an abbreviated manner (the same applies hereinafter). The inner diameter of the pipe may be stored for each pipe constituting the line (the same applies to the outer diameter). The outer diameter (column 108) is the outer diameter of the pipe.

[0031] The length (column 109) is the length of the line. The flow rate (column 110) is the maximum value of the volume of the liquid flowing through the line per unit time. The design drawing (column 111) is a design drawing created by the manufacturer. The design drawing may have a format of 3D CAD data or point cloud data. In addition to the drawing showing the outer shape of the product, the design drawing includes a table showing the radiation dose assumed when used in the normal state for each part, a graph showing the decay characteristics of the radiation dose after the operation stops for each part, a graph showing the performance of the product, etc.

[0032] (Decontamination information) FIG. 6 is a diagram showing an example of decontamination information 32. Each time the waste is decontaminated, it is assumed that the plant disassembly 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 (column 121) is an identifier that uniquely identifies the waste. The waste ID before the first disassembly is the same as the product ID. The waste ID may identify the pre-disassembly lineage, etc., or may identify the parts after disassembly. In this embodiment, for clarity, parts resulting from the disassembly of "P01" are assigned "P011", "P012", etc. (a hierarchical numbering structure). Each individual waste is tagged with a waste ID in an arbitrary manner.

[0033] The decontamination date (column 122) is the year, month, and day on which the waste was decontaminated. The decontaminator ID (column 123) is an identifier that uniquely identifies the stakeholder who decontaminated the waste. A stakeholder is an entity (legal person) that handles the waste, specifically, the nuclear power plant 62, the treatment facility 63, the temporary storage facility 65, the final disposal facility 66 shown in FIG. 2, as well as waste transporters and recycling facilities not shown in the figure. The decontamination method (column 124) is the method of decontamination that was carried out. Methods other than the chemical decontamination and mechanical decontamination described above (electrochemical decontamination) may be recorded. Furthermore, depending on the chemicals, equipment, etc. used, the decontamination method may be recorded in a more subdivided manner.

[0034] The decontamination factor (column 125) is the value obtained by dividing the radiation dose of the waste immediately before decontamination by the radiation dose immediately after decontamination. The plant disassembly management device 1 determines the necessity of performing decontamination again based on the decontamination factor. Secondary waste (column 126) is secondary waste generated by decontamination, and may carry radioactive substances removed from the waste being decontaminated, or may no longer carry radioactive substances as a result of chemical changes, etc. When the secondary waste continues to carry radioactive substances, it is managed as a separate waste (a new waste ID is assigned), and becomes a treatment target such as evaporation and condensation. Secondary waste is also a target for tracing, just like the original waste.

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

[0036] The disassembly date (column 132) is the year, month, and day when the waste was disassembled. The disassembler ID (column 133) is an identifier that uniquely identifies the stakeholder who disassembled the waste (for example, reference numeral 62 in FIG. 2). The disassembly method (column 134) is the method of disassembly that was carried out. Here, in addition to the specific method of disassembly, heavy machinery, tools, etc. used for disassembly may also be stored. Note that the disassembly method may be, for example, "crush with a hammer until it becomes fragments with a size of ○ mm or less". In this case, the disassembly position column 135 may be left blank, and the waste ID after disassembly may be the same as the waste ID before disassembly (without assigning a waste ID to each granular individual). The disassembly position (column 135) is information indicating at which position the waste before disassembly was disassembled (cut).

[0037] (Measurement information) FIG. 8 is a diagram showing an example of the measurement information 34. In this embodiment, before and after the decontamination or disassembly of the waste, the plant disassembly 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 (column 141) is the same as the waste ID in FIG. 6. The measurement date (column 142) is the year, month, and day when the radiation dose of the waste was measured. The measurer ID (column 143) is an identifier that uniquely identifies the stakeholder who measured the radiation dose of the waste (for example, reference numeral 63 in FIG. 2). The measured value (column 144) is the value of the radiation dose. The unit is, for example, mSv / hour. The measured value serves as a criterion for determining whether the waste meets the clearance criteria. The abstract (column 145) is any memorandum information related to the measurement. Here, it is the timing of the measurement.

[0038] (Disposal plan information) Figure 9 is a diagram showing an example of the disposal plan information 35. The disposal plan information 35 is a process table for each waste (system, etc.) before disassembly from after the decision to decommission the nuclear power plant until the waste is reused or finally disposed of. The processes include disassembly, decontamination, temporary storage, reuse, and final disposal. First, the plant disassembly management device 1 initially creates the disposal plan information 35. At this stage, the content of the disposal plan information 35 is "planned". Subsequently, as the process actually progresses, there are cases where the process is executed as planned and cases where it is not. Each of the terminal devices 2 to 6 in Figure 4 transmits an implementation report of the process related to itself to the plant disassembly management device 1. When the received implementation report is different from the plan, the plant disassembly management device 1 overwrites and updates the plan with the content of the received implementation report.

[0039] In the disposal plan information 35, the pre-disassembly information (column 161), primary disassembly information (column 162), secondary disassembly information (column 163), temporary storage information (column 164), final disposal information (column 165), reuse information (column 166), and revenue (column 167) are stored in association with each other. The primary disassembly is performed, for example, at the nuclear power plant 62 in Figure 2, and the secondary disassembly is performed, for example, at the treatment facility 63 in Figure 2.

[0040] Looking at the pre-disassembly information column 161, the following can be understood. · The waste (system) "P01" is first chemically decontaminated as a whole before disassembly at the nuclear power plant "F01". The plant disassembly management device 1 determines whether disassembly is necessary according to the radiation dose of the waste "P01". Also, the plant disassembly management device 1 determines the decontamination method based on the radiation dose and the design information 31 (material, shape, etc.) (the same applies hereinafter). · The decontamination method is underlined. This indicates that the decontamination is performed by the above-described mobile processing facility (the same applies to the disassembly method described later).

[0041] Looking at the primary disassembly information column 162, the following can be understood. · Next, the waste "P01" is disassembled into the waste "P011" and the waste "P012" at the processing facility "F01". · "F01" is the ID that identifies the nuclear power plant in the pre-disassembly information. That is, within the nuclear power plant, the disassembly is performed. · The disassembly is performed by "removing the bolts at ○ m from the left" of the waste "P01". The plant disassembly management device 1 estimates the radiation source from the radiation dose distribution in the waste "P01", determines the disassembly position and the number of wastes after disassembly, and determines tools for disassembly based on the design information 31 (materials, etc.) (the same applies hereinafter).

[0042] Looking at the secondary disassembly information column 163, the following can be understood. · Next, at the processing facility "F02", the waste "P011" is disassembled into the waste "P0111" and the waste "P0112". · The disassembly is performed by "cutting at ● m from the left" of the waste "P011". · At the same processing facility "F02", the waste "P012" is disassembled into the waste "P0121" and the waste "P0122". · The disassembly is performed by "cutting in the center" of the waste "P012". The disassembly is performed by the above-described mobile processing facility. · The wastes "P0111", "P0112", "P0121", and "P0122" after disassembly are mechanically decontaminated. Here, mechanical decontamination is selected because, for example, as a result of the system being disassembled in two stages, mechanical decontamination (such as brushing by a robot) becomes possible.

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

[0044] Looking at the final disposal information column 165, the following can be understood. · Finally, at the final disposal facility "F04", the waste "P0111" and the waste "P0112" stored in the Type A container are pit-disposed.

[0045] Looking at the reuse information column 166, the following can be understood. · On the other hand, at the reuse facility "F05", the waste "P0121" and the waste "P0122" stored in the Type B container are taken out of the container and become materials.

[0046] The profit (column 167) is the profit described above. Here, profit management is performed in system units.

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

[0048] The waste ID (column 171) is the same as the waste ID in Figure 6. However, the waste ID here usually identifies the waste after being disassembled at least once. And each stakeholder pays attention to the waste here from their respective positions. The original waste ID (column 172) is an identifier that uniquely identifies the original waste before the waste in the waste ID column 171 is disassembled. In the example of FIG. 10, a certain stakeholder requests the history of waste "P0111". Waste "P0111" is the result of the original waste (system, etc.) "P01" being disassembled twice. The design information (column 173) is all the content of the design information 31 of the product "P01".

[0049] The decontamination history (column 174) indicates, for example, when, at which facility, and by what method the waste "P0111" and the waste before its disassembly were decontaminated, and what the decontamination coefficient was in that decontamination. The decontamination date and the decontamination coefficient may be estimated. The disassembly history (column 175) indicates when, at which facility, and by what method the waste "P0111" and the waste before its disassembly were disassembled. The disassembly date may be an estimated date. The measurement history (column 176) indicates when, at which facility, the radiation dose of the waste "P0111" and the waste before its disassembly was measured, and what the resulting value was. Note that the summary column indicates the waste before its disassembly for which the value was shown.

[0050] The temporary storage information (column 177) indicates when, at which facility, and in what container the waste "P0111" and the waste before its disassembly were stored. The storage period may be an estimated period. The final disposal information (column 178) indicates when, at which facility, and by what disposal method the waste "P0111" was finally disposed of. The disposal date may be an estimated date.

[0051] (Processing procedure) Hereinafter, the processing procedure of the present embodiment will be described. There are three processing procedures, which are the plan creation processing procedure, the measurement processing procedure, and the history creation processing procedure.

[0052] (Plan creation processing procedure) FIG. 11 is a flowchart of the plan creation processing procedure. Now, assume that the decommissioning of a certain nuclear power plant has been determined. In step S201, the disposal plan creation unit 21 of the plant disassembly management device 1 identifies the waste. Specifically, the disposal plan creation unit 21 receives the waste ID of a batch of waste (for example, a system) from the power plant terminal device 2 among the waste. For the sake of explanation, here it is assumed that the waste ID "P01" (condenser secondary side piping unit) is 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 design radiation dose and the attenuation characteristics after operation stop for each part (such as piping) of the product "P01" when the product "P01" is normally operated.

[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 time point 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 (measured value) acquired in step S203. The radiation dose estimated here is, for example, the time-series radiation dose for each part starting from the current time point. There may be a case where a part that should have a sufficiently low radiation dose in 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 (such as piping) of the waste "P01" that has the highest radiation dose. There is a high possibility that the radiation source is attached to this part. 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 with a robot.

[0057] In step S206, the disposal plan creation unit 21 determines the necessity of decontamination. Specifically, the disposal plan creation unit 21 compares the radiation dose identified in step S205 with any of the following threshold values. ·Threshold value 1: The upper limit for ensuring the safety of nuclear power plant workers ·Threshold value 2: The upper limit for applying the target disposal method or reuse method

[0058] In step S207, the disposal plan creation unit 21 determines whether decontamination is necessary. Specifically, based on the result of the comparison in step S206, if the radiation dose is equal to or higher than the threshold value (step S207 "Yes"), the process proceeds to step S209; otherwise (step S207 "No"), the process proceeds to step S208.

[0059] In step S208, the disposal plan creation unit 21 determines the disassembly method. Specifically, the disposal plan creation unit 21 determines the disassembly method of the waste "P01" based on the design information 31 (such as materials) and the size of the container for housing. If the mobile processing facility is available, the disposal plan creation unit 21 determines to use it (the same applies in steps S209 to S211).

[0060] In step S209, the disposal plan creation unit 21 determines the decontamination method before disassembly. Specifically, the disposal plan creation unit 21 determines the 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 creation unit 21 selects chemical decontamination. Further, a chemical agent suitable for the material (heat-resistant steel) and radiation dose of the waste "P01" is selected.

[0061] In step S210, the disposal plan creation unit 21 determines the disassembly method. Specifically, the disposal plan creation unit 21 determines the disassembly method for the waste "P01" based on the design information 31, the radiation dose, the size of the container for housing, 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 creation unit 21 determines the decontamination method after disassembly. Specifically, the disposal plan creation unit 21 determines the decontamination method for each part (such as piping) after the waste "P01" has been disassembled based on the design information 31 and the radiation dose. At this time, the disposal plan creation unit 21 determines the decontamination method on the premise that the waste "P01" has been decontaminated by the decontamination method determined in step S209 and the waste "P01" has been disassembled by the disassembly method determined in step S210. The decontamination method determined here is, for example, mechanical decontamination for piping that has been divided in half.

[0063] By repeating the processes of steps S209 to S211, the disposal plan creation unit 21 may create a plan to decontaminate and disassemble the waste "P01" step by step in multiple times.

[0064] In step S212, the disposal plan creation unit 21 determines reuse and final disposal. Specifically, first, the disposal plan creation unit 21 receives from the reuse facility terminal device 6 of each reuse facility the reuse materials required by the reuse facility and the timing required, together with their purchase prices. Second, the disposal plan creation unit 21 receives from the final disposal facility terminal device 5 of each final disposal facility the waste that the final disposal facility can accept in the future and the acceptance timing, together with the disposal price thereof.

[0065] Third, the disposal plan creation unit 21 determines a reuse facility where waste such as "P01" can be reused and / or a final disposal facility where these can be finally disposed of. "Waste such as 'P01'" collectively refers to waste "P01" and the parts generated after its disassembly (the same applies hereinafter). The disposal plan creation unit 21 determines the reuse facility, for example, based on the purchase price presented by each reuse facility, and determines the final disposal facility, for example, based on 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 transportation carrier. Specifically, first, the disposal plan creation unit 21 transmits the quantity of waste such as "P01" 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 returns to the plant disassembly management device 1 the possibility of temporary storage and the storage fee.

[0067] Second, the disposal plan creation unit 21 transmits the quantity, radiation dose, etc. of waste such as "P01" transported between the nuclear power plant and each facility and between each facility to the transportation carrier terminal device 7 of each transportation carrier. Then, the transportation carrier terminal device 7 returns to the plant disassembly management device 1 the possibility of transportation and the transportation fee. Third, the disposal plan creation unit 21 determines a temporary storage facility where waste such as "P01" can be temporarily stored and a transportation carrier that can transport these. The disposal plan creation unit 21 determines the temporary storage facility based on the storage fee presented by each temporary storage facility, and determines the transportation carrier based on the transportation fee presented by each transportation carrier.

[0068] In step S214, the disposal plan creation unit 21 creates disposal plan information 35 (Fig. 9). Specifically, based on the content determined in steps S208 to S213, the disposal plan creation unit 21 creates the disposal plan information 35 and stores it in the auxiliary storage device 15. At this stage, each facility (stakeholder) associated with the waste "P01" in the disposal plan information 35 can access the plant disassembly management device 1 via its own terminal device and view the record of the disposal plan information 35 regarding the waste "P01".

[0069] After that, based on the disposal plan information 35, the stakeholders will perform decontamination, disassembly, temporary storage, transportation, reuse, and final disposal. Each stakeholder will execute the part of the disposal plan information 35 that they are in charge of. However, there may be cases where it cannot be executed 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 from the terminal devices 2 to 6 (Fig. 4) of each stakeholder regarding the pre-planned disassembly, decontamination, etc. The implementation report includes information such as "The disassembly of F01 was executed 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 change points to the plan. Specifically, when the implementation report received in step S215 indicates a change from the plan, the disposal plan creation unit 21 overwrites the content after the change in the disposal plan information 35 and stores it in the auxiliary storage device 15. Then, the plan creation processing procedure ends. Note that steps S215 and S216 are repeated each time each stakeholder performs disassembly, decontamination, etc. As a result, the disposal plan information 35 is always maintained in the latest state. Among the processes of steps S201 to S216, the main body of the process of obtaining information from the stakeholders may be the information collection unit 22. In this case, the information collection unit 22 passes the obtained information to the disposal plan creation unit 21 and entrusts the subsequent processes.

[0072] (Measurement processing procedure) FIG. 12 is a flowchart of the measurement processing 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 the dismantling or decontamination of the waste via their own terminal devices 2 to 6 and transmits it to the plant dismantling management device 1. For the sake of explanation, the treatment facility 63 (FIG. 2) is adopted as an example of a stakeholder here.

[0073] In step S301, the information collection unit 22 of the plant dismantling management device 1 determines whether the preparation for dismantling is completed. Specifically, when the information collection unit 22 receives from the treatment facility terminal device 3 of the treatment facility 63 that the preparation for dismantling the waste is completed (step S301 “Yes”), it proceeds to step S303; otherwise (step S301 “No”), it proceeds to step S302.

[0074] In step S302, the information collection unit 22 determines whether the preparation for decontamination is completed. Specifically, when the information collection unit 22 receives from the treatment facility terminal device 3 of the treatment facility 63 that the preparation for decontaminating the waste is completed (step S302 “Yes”), it proceeds to step S303; otherwise (step S302 “No”), it returns to step S301.

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

[0076] In step S304, the information collection unit 22 determines whether the disassembly is completed. Specifically, when the information collection unit 22 receives from the processing facility terminal device 3 of the processing facility 63 that the disassembly of the waste is completed (step S304 “Yes”), it proceeds to step S306; otherwise (step S304 “No”), it proceeds to step S305.

[0077] In step S305, the information collection unit 22 determines whether the decontamination is completed. Specifically, when the information collection unit 22 receives from the processing facility terminal device 3 of the processing facility 63 that the decontamination of the waste is completed (step S305 “Yes”), it proceeds to step S306; otherwise (step S305 “No”), it returns to step S304.

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

[0079] Third, the information collection unit 22 receives the content of the disassembly or decontamination of the waste from the processing facility terminal device 3 of the processing facility 63. Note that the information received here may be the same as the implementation report in step S215 (FIG. 11). Fourth, the information collection unit 22 creates a record of the disassembly information 33 (FIG. 7) or the decontamination information 32 (FIG. 6) based on the received content of the disassembly or decontamination. Then, the measurement processing procedure ends. As is clear from the above, the plant disassembly management device 1 always maintains the decontamination information 32 (FIG. 6), the disassembly information 33 (FIG. 7), and the measurement information 34 (FIG. 8) in the latest state.

[0080] (History creation processing procedure) Figure 13 is a flowchart of the history creation process. Each stakeholder can request the history of the waste they handle from the plant disassembly management device 1. For the sake of convenience in explanation, let's assume that, as an example of a stakeholder, the temporary storage facility 65 (Figure 2) wants to know the history in order to accept the waste "P0111".

[0081] In step S401, the history providing unit 23 of the plant disassembly management device 1 receives a history request from the 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 acquires the corresponding data from each piece of information using the search key. Specifically, the history providing unit 23 searches the design information 31 (Figure 5), decontamination information 32 (Figure 6), disassembly information 33 (Figure 7), measurement information 34 (Figure 8), disposal plan information 35 (Figure 9) and other information using the waste ID "P0111" as the search key. Then, the history providing unit 23 acquires all the data associated with "P0111". The "other information" here is the implementation report received by the disposal plan creation unit 21 in step S215 (Figure 11).

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

[0084] In step S404, the history providing unit 23 transmits the waste history information 36 (Figure 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. After that, the history creation process procedure ends.

[0085] (Effects of this Embodiment) The effects of the plant decommissioning management device of this embodiment are as follows. (1) The plant decommissioning management device plans the waste process and enables stakeholders to share the waste history information. Therefore, the plant decommissioning management device not only contributes to the traceability of waste but also can significantly reduce the management costs of each stakeholder. (2) The plant decommissioning management device can receive information regarding waste from stakeholders. (3) The plant decommissioning management device can manage dismantling, decontamination, and temporary storage leading to the reuse or final disposal of waste. (4) After identifying the radiation source, the plant decommissioning management device can accurately and efficiently plan decontamination or dismantling methods.

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

[0087] Note that the present invention is not limited to the above-described embodiments and includes various modifications. For example, the above-described embodiments have been described in detail for easy understanding of the present invention and are not necessarily limited to those having all the configurations described. Also, part of the configuration of one embodiment can be replaced with the configuration of another embodiment, and the configuration of another embodiment can be added to the configuration of one embodiment. Further, for part of the configuration of each embodiment, addition, deletion, or replacement with other configurations is possible.

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

Explanation of Signs

[0089] 1 Plant Disassembly Management Device 2 Power Plant Terminal Device 3 Processing Facility Terminal Device 4 Temporary Storage Facility Terminal Device 5 Final Disposal Facility Terminal Device 6 Reuse Facility Terminal Device 7 Carrier Terminal Device 8 Network 11 Central Control Device 12 Input Device 13 Output Device 14 Main Memory Device 15 Auxiliary Memory Device 16 Communication Device 21 Disposal Plan Creation Unit 22 Information Collection Unit 23 History Provision Unit 31 Design Information 32 Decontamination Information 33 Disassembly Information 34 Measurement Information 35 Disposal Plan Information 36 Waste History Information

Claims

1. A disposal plan creation unit that plans disposal plan information, which is a process schedule from when the waste is discharged from the plant until it is reused or finally disposed of, based on the design information of the waste discharged from the plant and the radiation dose of the waste; A storage unit that stores the planned disposal plan information; comprising: The disposal plan creation unit: stores in the storage unit information on whether processing facilities that can be shared among a plurality of reactors or a plurality of entities handling the waste can be used; A plant decommissioning management device characterized by the above.

2. The waste is: equipment other than spent fuel generated when an atomic power plant is decommissioned; The plant decommissioning management device according to claim 1, characterized by the above.

3. The disposal plan creation unit: determines a storage method and a transportation carrier, which are part of the disposal plan information, based on storage fee information required for temporary storage of the waste and transportation fee information of the waste; The plant decommissioning management device according to claim 1, characterized by the above.

4. The disposal plan creation unit: when there is a change in the plan based on the implementation report information on the implemented disposal plan, overwrites the storage unit with the changed content as the disposal plan information; The plant decommissioning management device according to claim 1, characterized by the above.

5. The disposal plan creation unit of the plant decommissioning management device: plans disposal plan information, which is a process schedule from when the waste is discharged from the plant until it is reused or finally disposed of, based on the design information of the waste discharged from the plant and the radiation dose of the waste; The storage unit of the plant decommissioning management device: stores the planned disposal plan information; The disposal plan creation unit further: stores in the storage unit information on whether processing facilities that can be shared among a plurality of reactors or a plurality of entities handling the waste can be used; A plant decommissioning management method of a plant decommissioning management device characterized by the above.

6. A computer: is made to function as a disposal plan creation unit that plans disposal plan information, which is a process schedule from when the waste is discharged from the plant until it is reused or finally disposed of, based on the design information of the waste 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 this purpose, and further for the disposal plan creation unit: Causing the storage unit to execute a process of storing information on the availability of use of processing facilities that can be shared among a plurality of nuclear reactors or among a plurality of entities handling the waste. A plant decommissioning management program characterized by the above.

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