JP7473441B2 - PLANT DISMANTLING MANAGEMENT DEVICE, PLANT DISMANTLING MANAGEMENT METHOD, AND - Google Patents

Description

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

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

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

The method for managing waste from dismantled nuclear facilities described in Patent Document 3 identifies the radiation level of the waste before dismantling, attaches a barcode or similar to each waste item after dismantling, and manages the information stored in the barcode or similar by computer until final disposal. The barcode or similar stores the waste number, source, radiation level, record of storage in container, radiation level on the container surface, etc.

WO 99/39253 JP 2002-207098 A JP 2001-141887 A

During the period from the decision to decommission to reuse or final disposal, many stakeholders will be involved in the waste, including the reactor manufacturer, nuclear power plant, operators of processing facilities, temporary storage facilities, transport companies, reuse facilities, final disposal facilities, etc. Each stakeholder will need past and future information about the waste they are involved with, from their respective standpoints. The same applies even after reuse or final disposal has been completed.

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

The plant dismantling management device of the present invention is characterized by comprising: a disposal plan creation unit that plans a process from when waste is discharged from a plant to when it is reused or finally disposed of, based on design information of the waste and the radiation dose of the waste, and a history providing unit that transmits history information of the waste to a terminal device of an operator of the terminal device in response to a request from the operator of the terminal device during the process.
Other means will be described in the description of the embodiment of the invention.

The present invention allows stakeholders in waste, such as nuclear power plants, to share information efficiently.

A diagram explaining the reuse and disposal method of radioactive waste. FIG. 1 is a diagram illustrating the flow of waste. FIG. 2 is a diagram illustrating a system and a radiation source. 2 is a diagram illustrating the configuration of a plant dismantling management device. FIG. FIG. 2 is a diagram illustrating an example of design information. FIG. 13 is a diagram showing an example of decontamination information. FIG. 11 is a diagram illustrating an example of dismantling information. FIG. 11 is a diagram illustrating an example of measurement information. FIG. 11 is a diagram showing an example of disposal plan information. FIG. 11 is a diagram showing an example of waste history information. 13 is a flowchart of a plan creation process. 13 is a flowchart of a measurement process procedure. 13 is a flowchart of a history creation process;

Hereinafter, a form for implementing the present invention (referred to as the "present embodiment") will be described in detail with reference to the drawings, etc. This embodiment is an example of recycling or final disposal of waste generated from 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.

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

After the decision to decommission a nuclear power plant, the spent fuel stored at the nuclear power plant is reused and ultimately disposed of, just as it was while the plant was in operation. What is unique about decommissioning a nuclear power plant is that a large amount of equipment other than the spent fuel (reactors, generators, condensers, piping, etc.) is generated at once as waste. These equipment include "low-level radioactive waste" and other waste that does not emit radiation (lines 52a-52e). This invention is primarily concerned with these equipment.

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

Low-level radioactive waste with low levels of radiation (for example, concrete rubble located a long distance from the reactor core) is placed in containers and "trench disposed." Trench disposal involves burying the waste shallowly underground without installing artificial structures such as pits (line 52c). Low-level radioactive waste with such a small amount of radiation that it does not affect human health (called "clearance material") is considered specially as general industrial waste. Clearance material can therefore be disposed of as industrial waste or can be reused (line 52d).

Waste that does not emit radiation is naturally reused or disposed of as industrial waste (line 52e). It is estimated that more than 90% by weight of the waste generated by the decommissioning of nuclear power plants is non-radioactive waste.

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

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

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

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

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

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

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

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

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

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

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

A power plant terminal device 2 disposed in the nuclear power plant 62 of FIG.
A processing facility terminal device 3 disposed in the processing facility 63 of FIG.
A temporary storage facility terminal device 4 arranged in the temporary storage facility 65 of FIG.
Final disposal facility terminal device 5 arranged in the final disposal facility 66 of FIG.
A reuse facility terminal device 6 arranged at the reuse facility
A transporter terminal device 7 arranged at a transport company (not shown)

(Design information)
5 is a diagram showing an example of the 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 (field 101) is an identifier that uniquely identifies a product that will become waste in the future.
The place of manufacture (field 102) is the name of the manufacturer and factory where the product was manufactured.
The product type (column 103) is a statement expressing the type of product by its function. In this case, the "condenser secondary side piping unit" corresponds to the system 49 in FIG.
The shipping date (field 104) is the date on which the product was shipped.

The use (column 105) is the type of liquid flowing through the pipe.
The material (column 106) is the material that constitutes the product.
The inner diameter (column 107) is the inner diameter of the pipe. Note that "#" is used to abbreviate different numerical values (the same applies below). 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.

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

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

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

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

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

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

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

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

In the disposal plan information 35, pre-dismantling information (column 161), primary dismantling information (column 162), secondary dismantling information (column 163), temporary storage information (column 164), final disposal information (column 165), reuse information (column 166), and revenue (column 167) are stored in association with one another. Primary dismantling is carried out, for example, by the nuclear power plant 62 in FIG. 2, and secondary dismantling is carried out, for example, by the processing facility 63 in FIG. 2.

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

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

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

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 temporarily stored in "Type A containers". Temporary storage is a measure until a final disposal facility or recycling facility is decided.
- In the same storage facility "F03", wastes "P0121" and "P0122" are temporarily stored in "Type B containers".
The plant dismantling management device 1 determines the type of container based on the radiation dose of the waste, the design information 31, the size after dismantling, etc.

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

Looking at the reuse information column 166, the following can be seen.
Meanwhile, in the recycling facility "F05", the waste "P0121" and waste "P0122" contained in the B-type containers are removed from the containers and turned into materials.

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

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

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

The decontamination history (column 174) indicates, for example, when, at which facility, and by what method the waste "P0111" and the waste before dismantling were decontaminated, and the decontamination factor for the decontamination. The decontamination date and the decontamination factor may be a schedule.
The dismantling history (column 175) indicates when, at what facility, and by what method the waste "P0111" and the waste before dismantling were dismantled. The dismantling date may be a scheduled date.
The measurement history (column 176) indicates when and at what facility the radiation dose of waste "P0111" and the waste before dismantling was measured, and what the value was. The summary column indicates the waste before dismantling that showed the value.

The temporary storage information (field 177) indicates when, in which 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 (field 178) indicates when, at which facility, and by what disposal method the waste "P0111" was finally disposed of. The disposal date may be a scheduled date.

(Processing Procedure)
The processing procedures of this embodiment will be described below. There are three processing procedures, namely, a planning processing procedure, a measurement processing procedure, and a history creating processing procedure.

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

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

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

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

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

In step S206, the disposal plan preparation unit 21 determines whether decontamination is necessary. Specifically, the disposal plan preparation unit 21 compares the radiation dose determined in step S205 with any of the following threshold values.
- Threshold 1: The upper limit for ensuring the safety of workers at nuclear power plants - Threshold 2: The upper limit for applying the targeted disposal or reuse method

In step S207, the disposal plan creation unit 21 determines whether decontamination is necessary. Specifically, if the result of the comparison in step S206 indicates that the radiation dose is equal to or greater than the threshold (step S207 "Yes"), the disposal plan creation unit 21 proceeds to step S209, and otherwise (step S207 "No"), the disposal plan creation unit 21 proceeds 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 for the waste "P01" based on the design information 31 (materials, etc.) and the size of the container to be stored. If mobile processing equipment is available, the disposal plan creation unit 21 determines 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 creation unit 21 selects chemical decontamination. Furthermore, an agent appropriate for the material (heat-resistant steel) and radiation dose of the waste "P01" is selected.

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

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

By repeating the processing of steps S209 to S211, the disposal plan creation unit 21 may create a plan to decontaminate and dismantle the waste "P01" in stages over multiple periods.

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

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

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

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

In step S214, the disposal plan creation unit 21 creates disposal plan information 35 (Figure 9). Specifically, the disposal plan creation unit 21 creates disposal plan information 35 based on the contents determined in steps S208 to S213, and stores it in the auxiliary storage device 15. At this stage, each facility (stakeholder) associated with waste "P01" in the disposal plan information 35 can access the plant dismantling management device 1 via their own terminal device, and can view the records of the disposal plan information 35 related to waste "P01".

Then, based on the disposal plan information 35, the stakeholders will carry out decontamination, dismantling, temporary storage, transportation, reuse, and final disposal. Each stakeholder will carry out the part of the disposal plan information 35 that they are responsible for. However, there are cases where they are unable to carry out the plan 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 demolition, decontamination, etc. from each stakeholder's terminal device 2-6 (Figure 4). The implementation report includes information such as "Demolition of F01 was carried out as planned" and "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, if the implementation report received in step S215 indicates a change from the plan, the disposal plan creation unit 21 overwrites the changed content to the disposal plan information 35 and stores it in the auxiliary storage device 15. Thereafter, the plan creation process procedure is terminated.
Steps S215 and S216 are repeated each time each stakeholder carries out dismantling, decontamination, etc., so that the disposal plan information 35 is always kept up to date.
Among the processes in steps S201 to S216, the main body of the process of acquiring information from the interested parties may be the information collecting unit 22. In this case, the information collecting unit 22 passes the acquired information to the disposal plan creating unit 21 and entrusts it with the subsequent processes.

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

In step S301, the information collection unit 22 of the plant dismantling management device 1 determines whether preparation for dismantling is complete. Specifically, if the information collection unit 22 receives from the processing facility terminal device 3 of the processing facility 63 a notification that preparation for waste dismantling is complete (step S301 "Yes"), the information collection unit 22 proceeds to step S303, and otherwise (step S301 "No"), the information collection unit 22 proceeds to step S302.

In step S302, the information collecting unit 22 determines whether preparations for decontamination have been completed. Specifically, if the information collecting unit 22 receives a notification from the processing facility terminal device 3 of the processing facility 63 that preparations for decontamination of waste have been completed (step S302 "Yes"), the information collecting unit 22 proceeds to step S303; otherwise (step S302 "No"), the information collecting unit 22 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.
Secondly, the information collecting unit 22 creates a record of the measurement information 34 (FIG. 8) based on the received radiation dose.

In step S304, the information collecting unit 22 determines whether or not dismantling has been completed. Specifically, if the information collecting unit 22 receives information from the processing facility terminal device 3 of the processing facility 63 that the waste dismantling has been completed (step S304 "Yes"), the information collecting unit 22 proceeds to step S306, and otherwise (step S304 "No"), the information collecting unit 22 proceeds to step S305.

In step S305, the information collecting unit 22 determines whether or not decontamination has been completed. Specifically, if the information collecting unit 22 receives information from the processing facility terminal device 3 of the processing facility 63 that decontamination of the waste has been completed (step S305 "Yes"), the information collecting unit 22 proceeds to step S306, and otherwise (step S305 "No"), the information collecting unit 22 returns to step S304.

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

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

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

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

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

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

The present invention is not limited to the above-described embodiments, but includes various modified examples. For example, the above-described embodiments have been described in detail to make the present invention easier to understand, and are not necessarily limited to those having all of the configurations described. It is also possible to replace part of the configuration of one embodiment with the configuration of another embodiment, and it is also possible to add the configuration of another embodiment to the configuration of one embodiment. It is also possible to add, delete, or replace part of the configuration of each embodiment with other configurations.

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

REFERENCE SIGNS LIST 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 Transporter 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 Dismantling information 34 Measurement information 35 Disposal plan information 36 Waste history information

Claims (10)

a disposal plan creation unit that plans a process for the waste to be discharged from the plant, based on design information of the waste and the radiation dose of the waste; and
a history providing unit that transmits history information of the waste to a terminal device of the operator in response to a request from the operator of the terminal device in the process;
A plant dismantling management device comprising: an information collecting unit that receives information about the waste handled by an operator of the terminal device ;
2. The plant dismantling management device according to claim 1 . The process comprises:
At least one of dismantling, decontaminating and temporarily storing the waste;
The history information includes:
including at least one of design information of the waste and information regarding the radiation dose, decontamination, dismantling, temporary storage and final disposal of the waste;
3. The plant dismantling management device according to claim 2, The disposal plan creation unit includes:
Identifying the radioactive source portions of said waste and planning methods for decontamination or dismantling;
4. The plant dismantling management device according to claim 3, The operator of the terminal device
at least one of a nuclear power plant, a treatment facility for the waste, a temporary storage facility for the waste, a recycling facility for the waste, and a final disposal facility for the waste;
5. The plant dismantling management device according to claim 4, The disposal plan creation unit includes:
determining at least one of the necessity to decontaminate the waste, a method for decontaminating the waste, and a method for dismantling the waste based on the design information of the waste and the radiation dose of the waste;
6. The plant dismantling management device according to claim 5, The disposal plan creation unit includes:
Manage the profitability of said process;
The process comprises:
a step of allowing operators of the terminal devices to use facilities that can be shared;
7. The plant dismantling management device according to claim 6, The disposal plan creation unit includes:
updating the process based on information received from an operator of the terminal device ;
8. The plant dismantling management device according to claim 7, The disposal plan creation section of the plant dismantling management device is
Based on design information of waste discharged from the plant and the radiation dose of the waste, a process is planned for the waste to be reused or finally disposed of after it is discharged from the plant;
The history providing unit of the plant dismantling management apparatus includes:
In response to a request from an operator of a terminal device in the process, transmitting history information of the waste to the terminal device of the operator ;
A plant dismantling management method comprising the steps of: Computer,
a disposal plan creation unit that plans a process for the waste to be discharged from the plant, based on design information of the waste and the radiation dose of the waste; and
a history providing unit that transmits history information of the waste to a terminal device of the operator in response to a request from the operator of the terminal device in the process;
A plant dismantling management program characterized by functioning as a

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