WO2022075429A1 - Plant demolition management device, plant demolition management method, and plant demolition management program - Google Patents

Abstract

A plant demolition management device (1) according to the present invention is characterized by being provided with: a disposal plan creation unit (21) that plans, on the basis of design information of waste discharged from a plant and the radiation dose of the waste, processes to be performed until the waste is reused or finally disposed of after the waste is discharged from the plant; and a history providing unit (23) that transmits history information of the waste to a terminal device of a person concerned in response to a request from the person concerned during the processes.

Description

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

The present invention relates to a plant dismantling management device, a plant dismantling management method, and a plant dismantling management program.

Nuclear power plants will be decommissioned systematically for a long period of time after completing their mission. Of the waste generated by 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 reused. In any case, it is important to manage waste accurately and efficiently during the period from decommissioning decision to disposal and reuse.

The dismantling and packing method of Patent Document 1 creates a plan to dismantle the waste and store it in a container on the premise that the waste such as pipes and equipment discharged from the nuclear power plant is transported to the disposal facility. In the radioactive solid waste treatment method of Patent Document 2, the radioactive solid waste is divided into a plurality of parts having different disposal methods based on the result of calculating the radiation amount of each part of the radioactive solid waste.

In the method for managing dismantled waste of nuclear facilities in Patent Document 3, the radiation amount of the waste is specified before dismantling, a barcode or the like is attached to each waste after dismantling, and the information stored in the barcode or the like is used. It is managed by a computer until the final disposal. The waste number, the source, the radiation dose, the storage record in the container, the radiation dose on the surface of the container, etc. are stored in the barcode or the like.

International Publication No. 99/39253 Japanese Unexamined Patent Publication No. 2002-207098 Japanese Unexamined Patent Publication No. 2001-141887

During the period from decommissioning decision to reuse or final disposal, many interests including reactor manufacturers, nuclear power plants, processing facilities, temporary storage facilities, carriers, reuse facilities, final disposal facilities, etc. The parties involved will be involved in the waste. Stakeholders, in their respective positions, need past or future information about the waste they are involved with. The same applies even when the reuse or final disposal is completed thereafter.

However, Patent Document 1 focuses on how to dismantle waste and store it in a container based on constraints such as container size and worker exposure dose, and waste by stakeholders. No mention is made of information sharing. 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 conscious of waste traceability for the time being, but does not specifically mention that stakeholders share waste information.
Therefore, the purpose is to efficiently share information among stakeholders of waste such as nuclear power plants.

The plant dismantling management device of the present invention plans a process from the waste discharged from the plant to reuse or final disposal based on the design information of the waste discharged from the plant and the radiation amount of the waste. It is characterized by including a disposal plan creation unit and a history providing unit that transmits waste history information to the terminal device of the interested party in response to a request from an interested party in the process.
Other means will be described in the embodiment for carrying out the invention.

According to the present invention, stakeholders of waste such as nuclear power plants can efficiently share information.

It is a figure explaining the reuse and disposal method of radioactive waste. It is a figure explaining the flow of waste. It is a figure explaining a system and a radiation source. It is a figure explaining the structure of a plant dismantling management apparatus. It is a figure which shows an example of the design information. It is a figure which shows an example of decontamination information. It is a figure which shows an example of dismantling information. It is a figure which shows an example of the measurement information. It is a figure which shows an example of disposal plan information. It is a figure which shows an example of waste history information. It is a flowchart of a plan making process procedure. It is a flowchart of the measurement processing procedure. It is a flowchart of a history creation processing procedure.

Hereinafter, a mode for carrying out the present invention (referred to as “the present embodiment”) will be described in detail with reference to figures and the like. This embodiment is an example of reusing or final disposal of waste generated by the decommissioning of a nuclear power plant. The present invention is applicable to both boiling water reactors and pressure water reactors, and is also applicable to general plants that discharge radioactive waste.

(Reuse and disposal method of radioactive waste)
FIG. 1 is a diagram illustrating a method for reusing and disposing of radioactive waste. Spent fuel is generated during the normal operation of a nuclear power plant. Uranium and plutonium are extracted from the spent fuel. These can be reused as fuel itself (row 51a). The waste liquid remaining after extraction is vitrified as "high-level radioactive waste", stored in a metal container, and finally "geological disposal". Geological disposal is to bury it in rock at a depth of 300 m or deeper (row 51b).

After the decision to decommission the nuclear power plant, the spent fuel stored in the nuclear power plant will be reused and finally disposed of in the same way as during operation. What is unique after the decision to decommission is that various facilities (reactors, generators, condensers, pipes, etc.) other than spent fuel are generated as waste in large quantities at one time. These facilities include "low level radiation waste" and other non-radiating waste (rows 52a-52e). The object of the present invention is mainly these facilities.

Of 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 "disposed at a medium depth". Medium-depth disposal means burying in the ground 70 m or deeper underground (row 52a). Low-level radioactive waste with a medium radiation dose (eg, pumps with a medium distance from the core) is dismantled, stored in a container, and then "pitted". .. Pit disposal is to bury in a concrete pit installed in shallow ground (row 52b).

Of the low-level radioactive waste, those with a low radiation dose (for example, concrete waste that is far from the core) are stored in a container and then "trenched". Trench disposal is to bury an artificial structure such as a pit in shallow ground without installing it (row 52c). Low-level radioactive waste whose radiation dose is so small that it does not affect human health (called "clearance waste") is specifically considered to be general industrial waste. Therefore, the clearance material can be finally disposed of as industrial waste and can be reused (row 52d).

Naturally, waste that does not emit radiation is reused or finally disposed of as industrial waste (line 52e). It is estimated that more than 90% of the waste from the decommissioning of nuclear power plants is waste that does not emit radiation.

(Flow of waste)
FIG. 2 is a diagram illustrating the flow of waste. FIG. 2 shows an example in which the pipe 68 is reused or finally disposed of as waste generated after the decommissioning is decided. The nuclear power plant 62 (nuclear power generation company) measures the radiation dose (unit is, for example, "mSv / hour") of the pipe 68. This measurement may be an actual measurement using a measuring instrument, or may be an estimation (logical calculation) based on design information created by the manufacturer 61. After that, the measurement will be repeated in various processes. The pipe 68 is, for example, a “system” composed of many parts as shown in FIG. 3, and the radiation dose is different for each part. Therefore, the measurement here targets each part of the pipe.

The nuclear power plant 62 decontaminates the pipe 68 as necessary based on the measurement results. Decontamination is the work of removing the radiation source from the waste (details below). After that, decontamination can be repeated in any step. The nuclear power plant 62 dismantles the pipe 68. Dismantling is the division of waste into smaller units (parts) to facilitate decontamination, transport, reuse, final disposal, etc., or to disperse radiation sources. After that, dismantling can be repeated in any step. After that, the disassembled pipe 68 is transported to the processing facility 63. Hereinafter, for the sake of simplification of the description, the portion of the pipe 68 generated as a result of dismantling is also referred to as “pipe 68”.

The treatment facility 63 (treatment facility operator) further dismantles the pipe 68. Of the dismantled pipe 68, low-level radioactive waste is transported to the temporary storage facility 65. In FIG. 2, the pipe 68 exiting from the processing facility 63 maintains the outer shape of the pipe, but may be finely crushed. Clearances are transported to other facilities for disposal for reuse. Examples of reuse are benches in nuclear power plants, containers for storing low-level radioactive waste, and so on. The "reuse facility" is these users.

The temporary storage facility 65 (temporary storage facility operator of waste) stores the dismantled pipes 68 transported from many treatment facilities in a predetermined container 71, and temporarily stores them in a designated place. Wait for the final disposal facility 66 to become available. The final disposal facility 66 (the final disposal facility operator of waste) receives the container 71 from the temporary storage facility 65 and burys it in the ground. There may be multiple temporary storage facilities and multiple final disposal facilities. In addition, the treatment facility and temporary storage facility may be located in close proximity to the nuclear power plant.

(Revenue and mobile processing equipment)
Generally, profit management is carried out in nuclear power plants, reactors or finer grid units. Revenue is defined as, for example, "revenue = power generation income-power generation cost-decommissioning cost + reuse income". If a part of the waste can be sold as a reuse material at a high price, the reuse income will be improved and the profit will be improved. In addition, for example, when decontaminating and dismantling waste, if mobile processing equipment (decontamination equipment, cutters, etc.) that can be moved and shared between multiple reactors or multiple stakeholders can be shared, decommissioning costs will be incurred. Will fall and profits will improve.

(System and radiation source)
FIG. 3 is a diagram illustrating a system and a radiation source. The system 49 has a pump 41, valves 42 and 43, and individual pipes 44-47. These form an integrated set of equipment, for example, transporting water from the condenser to the reactor pressure vessel. In the case of a boiling water reactor where water passes directly through the reactor pressure vessel, system 49 may be slightly contaminated with radiation. Even if this is not the case, the radioactive substance 48 may be attached to the inside or the 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 can be seen that only the radiation dose on the surface and the periphery of the pipe 45 is significantly larger than the others. The radioactive material that is the source of radiation in this way is also called a "radioactive source".

(Decontamination method)
When there is no adhesion of a radiation source and all parts of the system 49 show a uniformly high radiation dose, it is possible to perform chemical decontamination of the entire system without disassembling the system. Chemical decontamination is, for example, a method in which a decontamination device is directly connected to the system 49 and a drug (reducing agent or the like) is flowed.

If only the radiation dose of the part of the system 49 to which the radiation source is attached is high as a result of the radiation source adhering to a certain part, the system 49 is disassembled, the pipe 45 is removed, and the pipe 45 or the pipe 45 is further halved. It is possible to perform mechanical decontamination on the disassembled material. Mechanical decontamination is, for example, a method of spraying an abrasive or rubbing with a brush on a portion of a pipe.

Further, when the radiation dose of the pipe 45 is so high that the worker cannot safely disassemble the system 49, the robot or the like is made to chemically decontaminate the system 49, and then the pipe 45 is removed, and the pipe 45 is mechanically removed. It can also be dyed.

(Configuration of plant dismantling management equipment, etc.)
FIG. 4 is a diagram illustrating a configuration and the like 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 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, dismantling information 33, measurement information 34, disposal plan information 35, and waste history information 36 (all of which are described in detail later).

The disposal plan creation unit 21, the information collection unit 22, and the history provision unit 23 in the main storage device 14 are programs. The central control device 11 reads these programs from the auxiliary storage device 15 and loads them into the main storage device 14, thereby realizing the functions of each program (details will be described later). The auxiliary storage device 15 may have a configuration independent of the plant dismantling management device 1. The plant dismantling management device 1 can communicate with the following devices via the network 8.

-Power plant terminal device 2 arranged at the nuclear power plant 62 in FIG.
-Processing facility terminal device 3 arranged in the processing facility 63 of FIG.
-Temporary storage facility terminal device 4 arranged in the temporary storage facility 65 in FIG.
-Final disposal facility terminal device 5 arranged at the final disposal facility 66 in FIG.
・ Reuse facility terminal device 6 placed in the reuse facility
-Carrier terminal device 7 placed in a carrier (not shown)

(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 the 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 waste in the future.
The manufacturing location (column 102) is the name of the manufacturer and factory from which the product was manufactured.
The product type (column 103) is a wording expressing the product type by its function. The “condenser secondary piping unit” here corresponds to, for example, the system 49 in FIG.
The shipping date (column 104) is the date when the product was shipped.

The application (column 105) is a type of liquid flowing in the pipe.
The material (column 106) is a material constituting the product.
The inner diameter (column 107) is the inner diameter of the pipe. In addition, "#" indicates a different numerical value abbreviated (the same applies hereinafter). The inner diameter of the pipe may be stored for each pipe constituting the system (the same applies to the outer diameter).
The outer diameter (column 108) is the outer diameter of the pipe.

The length (column 109) is the length of the system.
The flow rate (column 110) is the maximum value of the volume of liquid flowing through the system per unit time.
The design drawing (column 111) is a design drawing created by the manufacturer. The design drawing may have a type of three-dimensional CAD data or point cloud data. In addition to the figure showing the outer shape of the product, the design drawing is a table showing the radiation dose expected when used under normal conditions for each part, and a graph showing the attenuation characteristics of the radiation dose after the operation is stopped for each part. , Includes graphs showing product performance, etc.

(Decontamination information)
FIG. 6 is a diagram showing an example of decontamination information 32. Each time the waste is decontaminated, the plant demolition management device 1 shall create a record of 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 dismantling is the same as the product ID. The waste ID may specify the system before dismantling, or may specify the part after dismantling. In the present embodiment, for the sake of clarity, "P011", "P012", etc. are added to the portion generated as a result of dismantling "P01" (hierarchical structure of numbers). Each waste is tagged with a waste ID in any way.

The decontamination date (column 122) is the date when the waste was decontaminated.
The decontamination person ID (column 123) is an identifier that uniquely identifies the stakeholder who decontaminated the waste. Stakeholders are the entities (corporations) that handle waste, specifically, the nuclear power plant 62, treatment facility 63, temporary storage facility 65, final disposal facility 66, and waste (not shown) in FIG. It is a carrier and a reuse facility.
The decontamination method (column 124) is the method of decontamination carried out. Methods other than the above-mentioned chemical decontamination and mechanical decontamination (electrochemical decontamination) may be stored. Further, the decontamination method may be further subdivided and stored according to the chemicals, equipment, etc. used.

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

(Dismantling information 33)
FIG. 7 is a diagram showing an example of disassembly information 33. Each time the waste is dismantled, the plant dismantling management device 1 shall create a record of dismantling information 33. In the dismantling 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. However, the waste ID here is a combination of the waste ID before dismantling and the waste ID after dismantling in order to clarify what occurred before dismantling and what occurred after dismantling. ing.

The dismantling date (column 132) is the date when the waste was dismantled.
The dismantling person ID (column 133) is an identifier that uniquely identifies a stakeholder who dismantled the waste (for example, reference numeral 62 in FIG. 2).
The dismantling method (column 134) is a dismantling method carried out. Here, in addition to the specific method of dismantling, heavy machinery, tools, etc. used for dismantling may be stored. The dismantling method may be "crushing with a hammer until the pieces have a size of ○ mm or less". In this case, the dismantling position column 135 may be left blank, and the waste ID after dismantling may be the same as the waste ID before dismantling (the waste ID is not assigned to each of the granular individuals).
The dismantling position (column 135) is information indicating at which position the waste before dismantling was dismantled (cut).

(Measurement information)
FIG. 8 is a diagram showing an example of the measurement information 34. In the present embodiment, before and after decontamination or dismantling of waste, the plant dismantling management device 1 shall create a record of 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.
The measurement date (column 142) is the date on which the radiation dose of the waste was measured.
The measurer ID (column 143) is an identifier that uniquely identifies an interested party (for example, reference numeral 63 in FIG. 2) who has measured the radiation dose of waste.
The measured value (column 144) is the value of the radiation dose. The unit is, for example, mSv / hour. The measured value is a standard for judging whether or not the waste is a clearance material.
The abstract (column 145) is arbitrary reminder information related to the measurement, and here, it is the timing of the measurement.

(Disposal plan information)
FIG. 9 is a diagram showing an example of disposal plan information 35. The disposal plan information 35 is a process chart for each waste (system, etc.) before dismantling until the waste is reused or finally disposed of after the decommissioning is decided. The process includes 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 "plan". After that, when the process actually progresses, there are cases where the process is executed as planned and cases where it is not. Each terminal device 2 to 6 in FIG. 4 transmits an implementation report of a process related to the terminal device 2 to 6 to the plant dismantling management device 1. When the received implementation report is different from the plan, the plant dismantling management device 1 overwrites and updates the plan with the contents of the received implementation report.

In the disposal plan information 35, pre-disassembly 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 revenue (column 167) are stored in association with each other. The primary dismantling is performed, for example, at the nuclear power plant 62 in FIG. 2, and the secondary dismantling is performed, for example, at the processing facility 63 in FIG.

Looking at the information column 161 before dismantling, the following can be seen.
-First, the entire waste (system) "P01" before dismantling is chemically decontaminated at the nuclear power plant "F01". The plant dismantling management device 1 determines whether or not dismantling is necessary according to the radiation dose of the waste “P01”. Further, the plant dismantling 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 mobile processing equipment described above (the same applies to the dismantling method described later).

Looking at the primary dismantling information column 162, the following can be seen.
-The waste "P01" is then disassembled into the waste "P011" and the waste "P012" at the treatment facility "F01".
-"F01" is an ID that identifies the nuclear power plant in the pre-demolition information. That is, the dismantling is carried out in 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 the radiation dose in the waste "P01", determines the dismantling position and the number of wastes after dismantling, and dismantles based on the design information 31 (materials, etc.). Determine the tools, etc. for this (same below).

Looking at the secondary dismantling information column 163, the following can be seen.
Next, in the treatment facility “F02”, the waste “P011” is disassembled into the waste “P0111” and the waste “P0112”.
-The dismantling is performed by "cutting the waste" P011 "from the left at ● m".
-In the same treatment facility "F02", the waste "P012" is disassembled into the waste "P0121" and the waste "P0122".
-The dismantling is performed by "cutting at the center" of the waste "P012". The dismantling is performed by the mobile processing equipment described above.
-The dismantled wastes "P0111", "P0112", "P0121" and "P0122" are mechanically decontaminated. Mechanical decontamination was selected here because, for example, as a result of dismantling the system in two stages, mechanical decontamination (brushing by a robot, etc.) became possible.

Looking at the temporary storage information column 164, the following can be seen.
-Next, in the temporary storage facility "F03", "P0111" and "P0112" of the waste are "contained in the A-type container" and temporarily stored. Temporary storage is a measure until the final disposal facility or reuse facility is decided.
-In the same storage facility "F03", "P0121" and "P0122" of the waste are "contained in a B-type container" and temporarily stored.
-The plant dismantling management device 1 determines the type of container based on the radiation amount of waste, design information 31, size after dismantling, and the like.

Looking at the final disposal information column 165, we can see the following.
-Finally, at the final disposal facility "F04", the waste "P0111" and the waste "P0112" contained in the A-type container are disposed of in the pit.

Looking at the reuse information column 166, we can see the following.
-On the other hand, in the reuse facility "F05", the waste "P0121" and the waste "P0122" contained in the B-type container are taken out from the container and used as materials.

Revenue (column 167) is the above-mentioned revenue. Here, profit management is performed on a system-by-system basis.

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

The waste ID (column 171) is the same as the waste ID in FIG. However, the waste ID here often identifies the waste after being dismantled at least once. And each stakeholder pays attention to the waste here from his or her own standpoint.
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 dismantled. In the example of FIG. 10, a stakeholder requests a history of waste “P0111”. The waste "P0111" is generated as a result of the original waste (system, etc.) "P01" being disassembled twice.
The design information (column 173) is all the contents of the design information 31 of the product “P01”.

The decontamination history (column 174) shows, for example, when, at what facility, and by what method the waste "P0111" and the waste before its dismantling were decontaminated, and what was the decontamination coefficient in the decontamination. Is shown. The decontamination date and decontamination coefficient may be planned.
The dismantling history (column 175) indicates when, at what facility, and by what method the waste “P0111” and the waste before the dismantling were dismantled. The dismantling date may be a scheduled date.
The measurement history (column 176) indicates when and at what facility the radiation doses of the waste “P0111” and the waste before dismantling were measured and what the values were. In addition, the summary column shows the waste before dismantling showing the value.

The temporary storage information (column 177) indicates when, in what facility, and in what container the waste “P0111” and the waste before dismantling were stored. The storage period may be a planned period.
The final disposal information (column 178) indicates when, at what facility, and by what disposal method the waste "P0111" was finally disposed of. The disposal date may be the scheduled date.

(Processing procedure)
Hereinafter, the processing procedure of the present embodiment will be described. There are three processing procedures, which are a planning processing procedure, a measurement processing procedure, and a history creating processing procedure.

(Planning process procedure)
FIG. 11 is a flowchart of the plan creation processing procedure. Now, suppose that the decommissioning of a nuclear power plant has been decided.
In step S201, the disposal plan creation unit 21 of the plant dismantling management device 1 identifies the waste. Specifically, the disposal plan creation unit 21 receives the waste ID of a group of wastes (for example, 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) is received.

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 shows the design radiation dose when the product "P01" is normally operated and the damping characteristics after the operation is stopped for each part (piping, etc.) of the product "P01". It is described in.

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 latest past time point from the power plant terminal device 2. The measurement information here has the type of one record of the measurement information 34 in FIG.

In step S204, the disposal plan creation unit 21 estimates the radiation dose. Specifically, the disposal plan creation unit 21 estimates the radiation amount 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 portion starting from the present time. The part where the radiation dose should be sufficiently low by design may actually exhibit a high radiation dose.

In step S205, the disposal plan creation unit 21 specifies the radiation source. Specifically, the disposal plan creation unit 21 identifies the portion (piping, etc.) constituting the waste “P01” having the highest radiation dose. There is a high possibility that a radiation source has adhered to this part. The disposal plan creation unit 21 may specify the radiation source (reference numeral 48 in FIG. 3) based on the image captured by operating the camera by the robot.

In step S206, the disposal plan creation unit 21 determines whether or not decontamination is necessary. Specifically, the disposal plan creation unit 21 compares the radiation dose specified in step S205 with any of the following threshold values.
・ Threshold 1: Upper limit for ensuring the safety of workers at nuclear power plants ・ Threshold 2: Upper limit for applying the target disposal method or reuse method

In step S207, the disposal plan creation unit 21 determines whether or not decontamination is necessary. Specifically, the disposal plan creation unit 21 proceeds to step S209 when the radiation amount is equal to or higher than the threshold value as a result of comparison in step S206 (step S207 “Yes”), and proceeds to other cases (step S207 “No”). ) Proceed to step S208.

In step S208, the disposal plan creation unit 21 determines the dismantling method. Specifically, the disposal plan creation unit 21 determines the dismantling method of the waste “P01” based on the design information 31 (materials and the like), the size of the container to be accommodated, and the like. If the mobile processing equipment is available, the disposal plan creation unit 21 decides to use it (the same applies to steps S209 to S211).

In step S209, the disposal plan creation unit 21 determines the decontamination method before dismantling. 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 preparation unit 21 selects chemical decontamination. Further, a chemical suitable for the material (heat resistant steel) of the waste “P01” and the radiation dose is selected.

In step S210, the disposal plan creation unit 21 determines the dismantling method. Specifically, the disposal plan creation unit 21 assumes that the waste “P01” has been decontaminated by the decontamination method determined in step S209, and has design information 31, radiation dose, and the size of the container to be accommodated. The method of dismantling the waste "P01" is determined based on the above.

In step S211 the disposal plan creation unit 21 determines the decontamination method after dismantling. Specifically, the disposal plan creation unit 21 determines a decontamination method for each part (piping, etc.) after the waste “P01” is disassembled based on the design information 31 and the radiation dose. At this time, the disposal plan creation unit 21 assumes that the waste “P01” is decontaminated by the decontamination method determined in step S209 and the waste “P01” is dismantled by the dismantling method determined in step S210. , Determine the dismantling method. The decontamination method determined here is, for example, mechanical decontamination of a pipe divided in half.

By repeating the processes of steps S209 to S211, the disposal plan creation unit 21 may create a plan for stepwise decontaminating / disassembling the waste “P01” in a plurality of times.

In step S212, the disposal plan preparation unit 21 decides reuse and final disposal. Specifically, first, the disposal plan creation unit 21 receives the reuse material required by the reuse facility and the required timing together with the purchase price from the reuse facility terminal device 6 of each reuse facility. ..
Second, the disposal plan preparation unit 21 receives the waste that the final disposal facility can accept in the future and the acceptance timing together with the disposal price from the final disposal facility terminal device 5 of each final disposal facility.

Thirdly, the disposal plan preparation unit 21 determines a reusable facility in which the waste "P01" and the like can be reused, and / or a final disposal facility in which these can be finally disposed of. "Waste" P01 "etc." is a general term for the waste "P01" and the parts generated after its dismantling (the same shall apply hereinafter). 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.

In step S213, the disposal plan creation unit 21 determines the storage method and the carrier. Specifically, first, the disposal plan creation unit 21 determines the amount of waste “P01” or the like to be temporarily stored and the period until final disposal, in the temporary storage facility terminal device of each temporary storage facility. Send to 4. Then, the temporary storage facility terminal device 4 returns the possibility of temporary storage and the storage fee to the plant dismantling management device 1.

Secondly, the disposal plan creation unit 21 transfers the amount, radiation amount, etc. of the waste “P01” etc. transported between the nuclear power plant and each facility and between each facility to the carrier terminal of each carrier. It is transmitted to the device 7. Then, the carrier terminal device 7 returns the possibility of transport and the transport fee to the plant dismantling management device 1.
Thirdly, 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 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 carrier based on the transport fee presented by each carrier.

In step S214, the disposal plan creation unit 21 creates the disposal plan information 35 (FIG. 9). Specifically, the disposal plan creation unit 21 creates the 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 accesses the plant dismantling management device 1 via its own terminal device, and disposes of the waste “P01”. The record of the plan information 35 can be visually recognized.

After that, interested parties will perform decontamination, dismantling, temporary storage, transportation, reuse and final disposal based on the disposal plan information 35. Each stakeholder executes the part of the disposal plan information 35 that he / she is in charge of. However, it may not be possible to carry out as planned.

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 implementation reports on pre-planned dismantling, decontamination, etc. from the terminal devices 2 to 6 (FIG. 4) of each stakeholder. The implementation report includes information such as "the dismantling 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.

In step S216, the disposal plan creation unit 21 stores the changes 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 changed content with the disposal plan information 35 and stores it in the auxiliary storage device 15. After that, the planning process procedure is terminated.
It should be noted that steps S215 and S216 are repeated each time each stakeholder dismantles, decontaminates, etc., and 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 acquiring information from 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 creating unit 21 and entrusts the subsequent processing.

(Measurement processing procedure)
FIG. 12 is a flowchart of the measurement processing procedure. Each stakeholder can measure the radiation dose of waste at any time. In the present embodiment, each stakeholder other than the carrier measures the radiation amount of the waste before and after the dismantling or decontamination of the waste via its own terminal devices 2 to 6, and the plant dismantling management device 1 Shall be sent to. Now, for convenience of explanation, the processing facility 63 (FIG. 2) is adopted as an example of interested parties.

In step S301, the information collecting unit 22 of the plant dismantling management device 1 determines whether or not the preparation for dismantling is completed. Specifically, when the information collecting unit 22 receives from the processing facility terminal device 3 of the processing facility 63 that the preparation for dismantling the waste is completed (step S301 “Yes”), the information collecting unit 22 proceeds to step S303, and otherwise proceeds to step S303. (Step S301 “No”), the process proceeds to step S302.

In step S302, the information collecting unit 22 determines whether or not the preparation for decontamination is completed. Specifically, when the information collecting unit 22 receives from the processing facility terminal device 3 of the processing facility 63 that the preparation for decontamination of waste is completed (step S302 “Yes”), the information collecting unit 22 proceeds to step S303, and the process proceeds to the process. In other cases (step S302 “No”), the process returns to step S301.

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.
Second, the information collecting unit 22 creates a record of measurement information 34 (FIG. 8) based on the received radiation dose.

In step S304, the information collecting unit 22 determines whether or not the dismantling is completed. Specifically, when the information collecting unit 22 receives 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 in other cases. (Step S304 “No”), the process proceeds to step S305.

In step S305, the information collecting unit 22 determines whether or not the decontamination is completed. Specifically, when the information collecting 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”), the information collecting unit 22 proceeds to step S306, and other than that. In the case (step S305 “No”), the process returns to step S304.

In step S306, the information collecting unit 22 acquires the radiation dose and the like. 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.
Second, the information collecting unit 22 creates a record of measurement information 34 (FIG. 8) based on the received radiation dose.

Thirdly, the information collecting unit 22 receives the contents of 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 dismantling information 33 (FIG. 7) or decontamination information 32 (FIG. 6) based on the received dismantling or decontamination content. After that, the measurement processing procedure is terminated.
As is clear from the above, the plant dismantling management device 1 always maintains the decontamination information 32 (FIG. 6), the dismantling information 33 (FIG. 7), and the measurement information 34 (FIG. 8) in the latest state.

(History creation processing procedure)
FIG. 13 is a flowchart of the history creation processing procedure. Each stakeholder can request the plant demolition management device 1 for the history of the waste it handles. For convenience of explanation, it is now assumed that, as an example of a stakeholder, the temporary storage facility 65 (FIG. 2) is trying to know its history in order to receive the waste “P0111”.

In step S401, the history providing unit 23 of the plant dismantling 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.

In step S402, the history providing unit 23 acquires the corresponding data from each information by using the search key. Specifically, the history providing unit 23 uses the waste ID “P0111” as a search key to design information 31 (FIG. 5), decontamination information 32 (FIG. 6), dismantling information 33 (FIG. 7), and measurement information 34. (FIG. 8), disposal plan information 35 (FIG. 9) and other information are searched. 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 (FIG. 11).

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 having the waste ID “P0111” based on the data acquired in step S402. 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 at the planning stage.

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.
After that, the history creation processing procedure is terminated.

(Effect of this embodiment)
The effects of the plant dismantling management device of this embodiment are as follows.
(1) The plant demolition management device plans the waste process and enables stakeholders to share the waste history information. Therefore, the plant demolition management device not only contributes to the traceability of waste, but also can significantly reduce the management cost of each stakeholder.
(2) The plant demolition management device can receive information on waste from interested parties.
(3) The plant dismantling management device can manage dismantling, decontamination and temporary storage leading to the reuse or final disposal of waste.
(4) The plant dismantling management device can plan the decontamination or dismantling method accurately and efficiently after specifying the radiation source.

(5) The plant demolition management device can be applied to the decommissioning of a nuclear reactor.
(6) The plant dismantling management device can determine the decontamination and dismantling method, etc. by using the waste design information and the like.
(7) The plant dismantling management device can manage the profit related to the process.
(8) The plant dismantling management device can update the process according to the actual results.

The present invention is not limited to the above-described embodiment, but includes various modifications. For example, the above-described embodiment has been described in detail in order to explain the present invention in an easy-to-understand manner, and is not necessarily limited to the one including all the configurations described. Further, it is 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. Further, it is possible to add / delete / replace a part of the configuration of each embodiment with another configuration.

Further, each of the above-mentioned configurations, functions, processing units, processing means and the like may be realized by hardware by designing a part or all of them by, for example, an integrated circuit. Further, each of the above configurations, functions, and the like may be realized by software by the processor interpreting and executing a program that realizes each function. Information such as programs, tables, and files that realize each function can be placed 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 indicate what is considered necessary for explanation, and do not necessarily indicate all the control lines and information lines in the product. In practice, it can be considered that almost all configurations are interconnected.

1 Plant dismantling 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 storage device 15 Auxiliary storage device 16 Communication device 21 Disposal plan creation department 22 Information collection department 23 History provision department 31 Design information 32 Decontamination information 33 Dismantling information 34 Measurement information 35 Disposal plan information 36 Waste history information

Claims (10)

1. Based on the design information of the waste discharged from the plant and the radiation dose of the waste, the disposal plan creation unit that plans the process from the discharge of the waste to the reuse or final disposal of the waste,
   A history providing unit that transmits the history information of the waste to the terminal device of the stakeholder in response to a request from the stakeholder in the process.
   A plant demolition management device characterized by being equipped with.
2. To have an information gathering unit that receives information about the waste handled by the interested parties.
   The plant dismantling management device according to claim 1.
3. The step is
   Includes at least one of the dismantling, decontamination and temporary storage of the waste.
   The history information is
   Includes at least one of the waste design information and information on the radiation dose, decontamination, dismantling, temporary storage and final disposal of the waste.
   2. The plant dismantling management device according to claim 2.
4. The disposal planning department
   To plan the decontamination or dismantling method after identifying the part of the waste that will be the radiation source.
   The plant dismantling management device according to claim 3.
5. The interested parties are
   Include at least one of a nuclear power plant, said waste treatment facility, said waste temporary storage facility, said waste reuse facility and said waste final disposal facility.
   The plant dismantling management device according to claim 4.
6. The disposal planning department
   At least one of the necessity of decontaminating the waste, the method of decontaminating the waste, and the method of dismantling the waste based on the design information of the waste and the radiation dose of the waste. To decide,
   The plant dismantling management device according to claim 5.
7. The disposal planning department
   Manage the profit of the process and
   The step is
   Including a process in which equipment that can be shared among the stakeholders can be used,
   The plant dismantling management device according to claim 6.
8. The disposal planning department
   Updating the process based on the information received from the interested parties,
   7. The plant dismantling management device according to claim 7.
9. The disposal plan creation department of the plant dismantling management device
   Based on the design information of the waste discharged from the plant and the radiation dose of the waste, the process from the discharge of the waste to the reuse or final disposal is planned.
   The history providing unit of the plant dismantling management device
   To transmit the history information of the waste to the terminal device of the stakeholder in response to the request from the stakeholder in the process.
   A plant demolition management method for plant demolition management equipment.
10. Computer,
    Based on the design information of the waste discharged from the plant and the radiation dose of the waste, the disposal plan creation unit that plans the process from the discharge of the waste to the reuse or final disposal of the waste,
    A history providing unit that transmits the history information of the waste to the terminal device of the stakeholder in response to a request from the stakeholder in the process.
    A plant demolition management program characterized by its ability to function.

Images