TWI834067B - Power plant dismantling management device, power plant dismantling management method and power plant dismantling management program - Google Patents

Abstract

An object of the present invention is to effectively share information among waste stakeholders of nuclear power plants and the like. The power plant dismantling management device of the present invention is characterized by having a disposal plan creation unit that, based on the design information of the waste discharged from the power plant and the amount of radiation of the waste, plans the waste from the discharge of the power plant until reuse or final disposal. The steps up to the step; and the process providing unit, which sends the process information of the waste to the terminal device of the stakeholder according to the request from the stakeholder in the step.

Description

Power plant dismantling management device, power plant dismantling management method and power plant dismantling management program

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

When the mission of the atomic power plant is over, it will be decommissioned in a planned manner over a long period of time. Radioactive waste among the waste generated with the abandoned furnace shall be disposed of in a safe place so as not to affect the human environment. Non-radioactive waste is sometimes disposed of as general industrial waste, and is sometimes reused. In either case, it is important to manage waste accurately and effectively from the time the furnace is scrapped until it is disposed of and reused.

The dismantling and packaging method of Patent Document 1 creates a plan to store the dismantled waste in a tank, and based on this, wastes such as pipes and machines discharged from a nuclear power plant are transported to a disposal facility. The radioactive solid waste treatment method of Patent Document 2 calculates the radiation dose of each part of the radioactive solid waste, and based on the calculation results, divides the radioactive solid waste into a plurality of parts with different disposal methods.

Patent Document 3 discloses a method for managing dismantling waste from atomic energy facilities. The radiation dose of the waste is specified before dismantling, a barcode is attached to each waste after dismantling, and the code is managed and stored in the code by a computer. The information is stored until final disposal. The waste number, generation source, radiation dose, storage record of the container, radiation dose on the surface of the container, etc. are memorized in the barcode.

[Prior technical literature] [Patent Document]

[Patent Document 1] International Publication No. 99/39253

[Patent Document 2] Japanese Patent Application Laid-Open No. 2002-207098

[Patent Document 3] Japanese Patent Application Laid-Open No. 2001-141887

From the decision to decommission the furnace to reuse or final disposal, the waste involves multiple stakeholders, including reactor manufacturers, nuclear power plants, processing facilities, temporary storage facilities, transport operators, and recyclers. Operators of facilities, final disposal facilities, etc. Stakeholders, from their respective standpoints, need information about the past or future of the wastes they are involved in. Thereafter, the same applies even to the end of reuse or final disposal.

However, Patent Document 1 focuses on how to dismantle the waste and store it in the tank based on constraints such as the size of the tank and the exposure of the operator, and does not mention information on sharing the waste with stakeholders. Patent Document 2 focuses on adjusting the radiation dose of the resulting solid (ingot), but still does not mention information on the sharing of waste by stakeholders. Although Patent Document 3 is generally aware of the traceability of waste, it does not specifically mention information on the joint use of waste by stakeholders.

Therefore, an object of the present invention is to effectively share information with stakeholders of wastes from nuclear power plants and the like.

The power plant dismantling management device of the present invention is characterized by having a disposal plan creation unit that, based on the design information of the waste discharged from the power plant and the amount of radiation of the waste, plans the waste from the discharge of the power plant until reuse or final disposal. The steps up to the step; and the process providing unit, which sends the process information of the waste to the terminal device of the stakeholder according to the request from the stakeholder in the step.

Other methods will be described in the form for implementing the invention.

According to the present invention, information can be effectively shared by stakeholders of wastes from nuclear power plants and the like.

1: Power plant dismantling management device

2: Power station terminal device

3: Treatment facility terminal device

4: Temporary storage facility terminal device

5: Final disposal facility terminal device

6: Recycling facility terminal device

7: Carrier terminal device

8:Internet

11: Central control device

12:Input device

13:Output device

14: Main memory device

15: Auxiliary memory device

16: Communication device

21: Disposal Plan Production Department

22:Information Collection Department

23:Process Provider Department

31:Design information

32: Decontamination information

33: Disassembly information

34: Measurement information

35: Disposal plan information

36:Waste process information

41:Pump

42:Valve

43:Valve

44:Piping

45:Piping

46:Piping

47:Piping

48:Radioactive materials

49:System

51a:column

51b: column

52a: column

52b: column

52c: column

52d: column

52e: column

61:Manufacturer

62:Atomic power station

63:Processing facilities

65:Temporary storage facility

66: Final disposal facilities

68:Piping

71:Container

101: Product ID column

102: Manufacturing site column

103: Product type column

104: Shipment year, month and day column

105:Purpose column

106:Material column

107:Inner diameter column

108:Outer diameter column

109: Length column

110: Traffic column

111: Design diagram bar

121: Waste ID column

122: Decontamination day column

123:Decontamination person ID column

124: Decontamination method column

125: Decontamination coefficient column

126:Secondary waste column

131: Waste ID column

132:Dismantle the daily column

133: Dismantler ID column

134: Disassembly method column

135: Disassemble the location bar

141: Waste ID column

142:Measuring the day column

143: Measurer ID column

144: Measurement value column

145:Summary column

161: Information column before disassembly

162: Disassemble the information column at once

163:Second dismantling information column

164: Temporary storage information column

165: Final disposal information column

166:Reuse information column

167:Income column

171: Waste ID column

172: Original waste ID column

173:Design information column

174: Decontamination process column

175: Disassembly process bar

176: Measurement process column

177: Temporary storage information column

178: Final disposal information column

S201~S216: steps

S301~S306: steps

S401~S404: steps

Figure 1 is a diagram illustrating the reuse and disposal methods of radioactive waste.

Figure 2 is a diagram illustrating the flow of waste.

Figure 3 is a diagram illustrating the system and radiation source.

Fig. 4 is a diagram explaining the structure of the power plant disassembly management device and the like.

Figure 5 is a diagram showing an example of design information.

Figure 6 is a diagram showing an example of decontamination information.

Figure 7 is a diagram showing an example of disassembly information.

FIG. 8 is a diagram showing an example of measurement information.

FIG. 9 is a diagram showing an example of disposal plan information.

Figure 10 is a diagram showing an example of waste history information.

Figure 11 is a flow chart of the plan creation processing sequence.

Figure 12 is a flow chart of the measurement processing sequence.

Figure 13 is a flow chart of the procedure of process creation.

Hereinafter, a mode for implementing the present invention (referred to as "this embodiment") will be described in detail with reference to the drawings and the like. This embodiment is an example of reusing or finally disposing of waste generated by decommissioning a nuclear power plant. The invention can be applied to boiling water type reactors and pressurized water type reactors, and can also be applied to ordinary power plants that discharge radioactive waste.

(Reuse and disposal methods of radioactive waste)

Figure 1 is a diagram illustrating the reuse and disposal methods of radioactive waste. During the normal operation of the nuclear power plant, used fuel is generated. Uranium and plutonium are extracted from the fuel after use. They can be reused as fuel itself (column 51a). The waste liquid remaining after extraction is vitrified as "high-level radioactive waste" and stored in metal containers, and finally undergoes "geological disposal." The geological disposal is buried in the rock plate at a depth of more than 300m underground (column 51b).

After the decision is made to decommission the nuclear power plant, the used fuel stored in the nuclear power plant will be reused and finally disposed of in the same manner as during operation. The unique feature of the decision to scrap the furnace is that a large amount of equipment (reactors, generators, condensation equipment, etc.) equipment, piping, etc.) as waste. Such equipment includes "low-level radioactive waste" and other waste that does not emit radioactive rays (columns 52a~52e). The object of the present invention is mainly such equipment.

Among low-level radioactive wastes, those with higher radiation levels (such as control rods with a small distance from the furnace core, etc.) are disassembled and stored in containers for "medium-depth disposal." Medium-depth disposal is buried at a depth of more than 70m underground (column 52a). Low-level radioactive waste with a moderate amount of radiation (e.g., pumps with a moderate distance from the furnace core, etc.) is disassembled and stored in containers, and then "pit disposal" is performed. The pit disposal refers to the concrete pit buried in shallow ground (column 52b).

Among the low-level radioactive wastes, those with lower radiation levels (such as concrete wastes that are far away from the furnace core, etc.) are stored in containers and then "trenched". Trench disposal refers to burying in shallow ground without setting up artificial structures such as pits (column 52c). The amount of radioactive rays in low-level radioactive waste is so small that it will not affect human health (called "clean waste") is particularly regarded as general industrial waste. Therefore, in addition to final disposal as industrial waste, cleaning materials can also be reused (column 52d).

Of course, waste that does not emit radiation is reused or ultimately disposed of as industrial waste (column 52e). Trial calculations show that more than 90% by weight of the waste accompanying abandoned furnaces of nuclear power plants is waste that does not emit radioactive rays.

(Waste flow)

Figure 2 is a diagram illustrating the flow of waste. FIG. 2 shows an example of reusing or final disposal of the piping 68 as waste generated after the furnace is abandoned. The nuclear power plant 62 (nuclear power generation operator) measures the amount of radiation in the pipe 68 (the unit is, for example, “mSv/hour”). The measurement may be an actual measurement using a measuring instrument, or it may be an inference (logical calculation) based on the design information produced by the manufacturer 61. In the following, measurements are repeated in various steps. The piping 68 is a "system" including a plurality of parts as shown in FIG. 3 , for example, and the amount of radiation is different in each part. Therefore, the measurement here is based on each part of the piping.

The nuclear power plant 62 decontaminates the piping 68 as necessary based on the measurement results. Decontamination is the removal of radioactive sources from waste (details described later). Below, you can repeat the decontamination in any step. The atomic power plant 62 disassembles the piping 68 . Dismantling means dividing waste into smaller units (parts) for easy decontamination, transportation, reuse, final disposal, etc., or for dispersing radioactive sources. The disassembly can be repeated in any step below. Thereafter, the disassembled piping 68 is transported to the processing facility 63 . Hereinafter, in order to simplify the description, the portion of the pipe 68 produced as a result of disassembly will also be referred to as the “pipe 68”.

The treatment facility 63 (the treatment facility operator) further disassembles the piping 68 . The low-level radioactive waste in the dismantled piping 68 is moved to the temporary storage facility 65 . In FIG. 2 , the pipe 68 removed from the treatment facility 63 maintains a similar shape to the pipe, but may be broken into finer pieces. Cleaned materials are transported to other facilities for processing for reuse. Examples of reuse are workbenches in nuclear power plants, containers for storing low-level radioactive waste, etc. In addition, "recycling facilities" refer to these users.

The temporary storage facility 65 (the operator of the temporary storage facility for waste) stores the disassembled pipes 68 transported from multiple treatment facilities in a specific container 71 and temporarily stores them in a designated place until the final disposal facility 66 becomes available. The final disposal facility 66 (the operator of the final disposal facility for waste) receives the container 71 from the temporary storage facility 65 and buries it in the ground. A plurality of temporary storage facilities and a plurality of final disposal facilities may each exist. Furthermore, processing facilities and temporary storage facilities can also be located close to nuclear power plants.

(Revenue and Mobile Processing Equipment)

Generally speaking, revenue management is performed on atomic power plants, reactors or smaller system units. Profit is defined by, for example, "Profit = power generation revenue - power generation cost - scrap furnace cost + reuse revenue". If part of the waste can be sold at a high price as reuse materials, the reuse income will increase and the profit will also increase. Also, for example, during the decontamination and dismantling of waste, if mobile/commonly used mobile treatment equipment (decontamination devices, milling cutters, etc.) can be shared between multiple reactors or multiple stakeholders, the waste Furnace costs are reduced and profits are increased.

(system and radioactive source)

Figure 3 is a diagram illustrating the system and radiation source. The system 49 includes a pump 41, valves 42 and 43, and respective pipes 44 to 47. These integrated equipment groups, for example, transport water from the condenser to the reactor pressure vessel. In the case of a boiling water type reactor where water is passed directly through the reactor pressure vessel, there is a possibility that the system 49 will be slightly contaminated with radiation. Even if this is not the case, radioactive material 48 may adhere to the inside or outside of part of the pipes 45 . In this case, if the amount of radiation in each part of the system 49 is measured with a measuring device, it can be seen that only the surface and periphery of the pipe 45 have a significantly larger amount of radiation than other places. Radiation which thus becomes the source of radiation Sexual substances are also called "radioactive sources".

(Decontamination method)

In situations where any part of the system 49 exhibits a uniformly high dose of radiation without the attachment of a radioactive source, etc., the entire system can be chemically decontaminated without dismantling the system. Chemical decontamination is, for example, a method in which a decontamination device is directly connected to the system 49 to flow chemicals (reducing agents, etc.).

As a result of the radioactive source being attached to a certain part, only when the amount of radiation in the part of the system 49 to which the radioactive source is attached is high, the system 49 can be disassembled and the pipe 45 removed, and the pipe 45 or the pipe 45 further Those that are disassembled into half are mechanically decontaminated. Mechanical decontamination is a method such as spraying abrasives on the piping part or wiping it with a brush.

Furthermore, when the amount of radiation in the piping 45 is so high that the operator cannot safely disassemble the system 49 , a robot or the like can be used to chemically decontaminate the system 49 and then remove the piping 45 and perform mechanical decontamination on the piping 45 .

(Construction of power plant disassembly management equipment, etc.)

FIG. 4 is a diagram explaining the structure of the power plant disassembly management device 1 and the like. The power plant dismantling management device 1 is an ordinary computer, equipped with 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 interconnected by busbars. 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 (the details of each will be described later).

The solution plan creation part 21, the information collection part 22, and the history providing part 23 of the main memory device 14 are programs. The central control device 11 realizes the functions of each program by loading the programs from the auxiliary memory device 15 to the main memory device 14 (details will be described later). The auxiliary memory device 15 may also be configured independently from the power plant disassembly management device 1 . The power plant dismantling management device 1 can communicate with each of the following devices via the network 8 .

‧Power station terminal device 2 arranged in the atomic energy power station 62 in Figure 2

‧The processing facility terminal device 3 arranged in the processing facility 63 in Figure 2

‧Temporary storage facility terminal device 4 arranged in the temporary storage facility 65 in Figure 2

‧Final disposal facility terminal device 5 arranged in the final disposal facility 66 in Figure 2

‧Recycling facility terminal device 6 installed in the recycling facility

‧Conveyor terminal device 7 installed at the carrier (not shown)

(Design Information)

FIG. 5 is a diagram showing an example of the design information 31. Design information 31 is produced for each product shipped from a manufacturer, for example. In the design information 31, the following information is related to each other and memorized.

Product ID (column 101) is the unique identification code for products that will become waste in the future.

The manufacturing site (column 102) is the name of the manufacturer and factory where the product is manufactured.

Product type (column 103) is a term used to express the type of product based on its function. The "condenser secondary side piping unit" here corresponds to the system 49 in FIG. 3 , for example.

The year, month and day of shipment (column 104) is the year, month and day when the product is shipped.

The purpose (column 105) is the type of liquid flowing in the pipe.

Materials (column 106) are the materials that make up the product.

The inner diameter (column 107) is the inner diameter of the pipe. In addition, "#" elliptically displays different numerical values (the same applies below). The inner diameter of the pipe can also be memorized for each pipe that makes up the system (the same goes for the outer diameter).

The outer diameter (column 108) is the outer diameter of the pipe.

Length (column 109) is the length of the system.

Flow (column 110) is the maximum volume of liquid flowing in the system per unit time.

The design drawing (column 111) is the design drawing produced by the manufacturer. The design drawing may also be in the form of 3D CAD (Computer-Aided Design) data or point group data. In addition to a diagram showing the appearance of the product, the design drawing also includes a table showing the expected radiation dose for each part during normal use, a graph showing the attenuation characteristics of the radiation dose after operation is stopped for each part, and a display Product performance charts, etc.

(Contamination removal information)

FIG. 6 is a diagram showing an example of decontamination information 32. Each time the waste is decontaminated, the power plant disassembly management device 1 creates a record of the decontamination information 32 . In the decontamination information 32, the following information is associated with each other and memorized.

Waste ID (column 121) is the unique identification code of a specific waste. The waste ID before initial disassembly is the same as the product ID. The waste ID may specify the system before disassembly, and may also specify the parts after disassembly. In this embodiment, for ease of understanding, "P011" and "P012" (hierarchical structure of numbers) are appended to the parts resulting from the disassembly of "P01". in every waste For waste, tag the waste ID by any method.

The decontamination date (column 122) is the year, month and day when the waste was decontaminated.

The decontaminator ID (column 123) is the identification code that uniquely specifies the stakeholder who decontaminates the waste. Stakeholders are the entities (legal persons) that process waste, specifically the nuclear power plant 62, processing facility 63, temporary storage facility 65, final disposal facility 66 in Figure 2, and waste transporters and recyclers not shown in the figure. Take advantage of the facilities.

Decontamination method (column 124) refers to the method of decontamination performed. Methods other than chemical decontamination and mechanical decontamination mentioned above (electrochemical decontamination) can be memorized. Furthermore, the decontamination methods can be further subdivided and memorized based on the chemicals, equipment, etc. used.

The decontamination coefficient (column 125) is the value of the amount of radiation immediately before decontamination of the waste divided by the amount of radiation immediately before decontamination. The power plant disassembly management device 1 determines whether it is necessary to perform decontamination again based on the decontamination coefficient.

Secondary waste (column 126) is secondary waste generated by decontamination. It may carry radioactive substances removed from the waste targeted for decontamination, or it may no longer carry radioactive substances as a result of chemical changes, etc. situation. If secondary waste continues to carry radioactive materials, it will be treated as other waste (waste ID re-attached) and become the subject of evaporation, condensation, etc. Secondary waste is also subject to traceability like original waste.

(Teardown information 33)

FIG. 7 is a diagram showing an example of the disassembly information 33. Each time waste is dismantled, the power plant dismantling management device 1 creates a record of the dismantling information 33 . In Teardown Information 33, combine the following information Establish associations and remember each other.

The waste ID (column 131) is the same as the waste ID in Figure 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 disassembly and what was produced after disassembly.

The dismantling date (column 132) is the year, month and day when the waste was dismantled.

The dismantler ID (column 133) is an identification code that uniquely specifies the stakeholder (for example, symbol 62 in Figure 2) who dismantles the waste.

Disassembly method (column 134) refers to the method of disassembly carried out. Here, in addition to the specific methods of disassembly, you can also memorize the heavy machinery, props, etc. used for disassembly. In addition, the dismantling method may be "crushing with a heavy hammer until fragments are ○mm or less in size", etc. In this case, the disassembly position column 135 can also be set to a blank column so that the waste ID after disassembly is the same as the waste ID before disassembly (the waste ID number is not created for each granular individual).

The dismantling position (column 135) is information showing where the waste before dismantling will be dismantled (cut off).

(Measurement information)

FIG. 8 is a diagram showing an example of measurement information 34. In this embodiment, the power plant disassembly management device 1 creates a record of the measurement information 34 before and after the waste is decontaminated or dismantled. In the measurement information 34, the following information is associated with each other and memorized.

The waste ID (column 141) is the same as the waste ID in Figure 6.

The measurement date (column 142) is the year, month and day when the radiation dose of the waste was measured.

The measurer ID (column 143) is the only person who specifies the stakeholder in measuring the radiation dose of the waste (e.g. The identification code is shown as symbol 63 in Figure 2.

The measured value (column 144) is the value of the radiation dose. The unit is e.g. mSv/hour. The measured value becomes the basis for judging whether the waste qualifies as clean material.

The summary (column 145) is any memo information of the measurement, here is the time series of the measurement.

(Resolution plan information)

FIG. 9 is a diagram showing an example of the resolution plan information 35. The disposal plan information 35 is a table of steps to determine the steps for each waste (system, etc.) after the furnace is decommissioned and before disassembly until reuse or final disposal of the waste. The steps include dismantling, decontamination, temporary storage, reuse, and final disposal. First, the power plant dismantling management device 1 initially creates disposal plan information 35 . In this stage, the content of the disposal plan information 35 is “plan”. Later, when the steps actually progress, there will be situations where the steps are performed as planned and situations where they are not. Each terminal device 2 to 6 in Figure 4 sends an implementation report of its associated step to the power plant disassembly management device 1. When the received implementation report is different from the plan, the power plant disassembly management device 1 overwrites the update plan with the contents of the received implementation report.

In the disposal plan information 35, the information before dismantling (column 161), primary dismantling information (column 162), secondary dismantling information (column 163), temporary storage information (column 164), and final disposal information (column 165) are included. ), reuse information (column 166) and income (column 167) are related and memorized. The system that performs primary disassembly is such as the atomic power plant 62 in Figure 2 , and the system that performs secondary disassembly is such as the processing facility 63 in Figure 2 .

If you look at the pre-disassembly information column 161, you can find out the following.

‧Waste (system) "P01" is first chemically decontaminated in the atomic power plant "F01" before being dismantled. The power plant dismantling management device 1 determines whether it needs to be dismantled based on the amount of radiation in the waste "P01". Furthermore, the power 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 below).

‧Underline decontamination methods. This shows decontamination by the above-mentioned mobile processing equipment (the same applies to the disassembly method described later).

If the disassembly information column 162 is observed once, the following situation can be known.

‧Then, waste "P01" is disassembled into waste "P011" and waste "P012" in the processing facility "F01".

, "F01" is the ID of the specific atomic power plant in the information before dismantling. That is, the disassembly is carried out in the atomic energy electronic station.

‧This disassembly is carried out by "removing the bolt at ○m from the left" of waste "P01". The power plant dismantling management device 1 estimates the radiation source from the distribution of the radiation dose of the waste "P01", determines the dismantling position and the number of dismantled wastes, and determines the use based on the design information 31 (materials, etc.) Disassembly tools, etc. (the same below).

If you look at the secondary disassembly information column 163, you can find out the following.

‧Next, in the processing facility "F02", waste "P011" is disassembled into waste "P0111" and waste "P0112".

‧The disassembly is carried out by "cutting off" the waste "P011" m from the left.

‧In the same treatment facility "F02", waste "P012" is disassembled into waste "P0121" and waste "P0122".

‧The disassembly is carried out by "cutting" the waste "P012" in the center. The dismantling is carried out by the above-mentioned mobile processing equipment.

‧The dismantled waste “P0111”, “P0112”, “P0121” and “P0122” are subjected to mechanical decontamination. Mechanical decontamination is chosen here because, for example, dismantling the system in two stages can result in mechanical decontamination (scrubbing with a robot, etc.).

If you look at the temporary storage information column 164, you will find the following.

‧Next, in the temporary storage facility "F03", "P0111" and "P0112" among the wastes were "stored in A-type containers" and temporarily stored. Temporary storage is a measure before final disposal or reuse facilities are decided.

‧In the same storage facility "F03", "P0121" and "P0122" among the wastes were "stored in B-type containers" and temporarily stored.

‧The power plant disassembly management device 1 determines the type of container based on the amount of radiation of the waste, design information 31, size after disassembly, etc.

If we look at the final disposal information column 165, we can see the following.

‧Finally, in the final disposal facility "F04", the waste "P0111" and waste "P0112" stored in the A-type container will be pit-disposed.

Looking at the reuse information column 166, the following is known.

‧On the other hand, in the recycling facility "F05", the waste "P0121" and the waste "P0122" contained in the B-type container become materials taken out from the container.

Income (column 167) represents the income stated above. Here, revenue management is performed in system units.

(Waste History Information)

FIG. 10 is a diagram showing an example of waste history information 36. In response to requests from each of the terminal devices 2 to 7 in FIG. 4 , the power plant disassembly management device 1 creates waste history information 36 describing the history of each waste including dismantled waste. In the waste process information 36, the following information is related to each other and memorized.

The waste ID (column 171) is the same as the waste ID in Figure 6. However, in most cases, the waste ID here specifies waste that has been dismantled at least once. Moreover, all stakeholders are concerned about the waste here from their own standpoints.

The original waste ID (column 172) is the unique identification code that uniquely identifies the original waste before dismantling the waste in waste ID column 171. In the example in Figure 10, the process of a stakeholder requesting waste "P0111" is shown. Waste "P0111" is generated as a result of secondary disassembly of the original waste (system, etc.) "P01".

Design information (column 173) is all the content of design information 31 of product "P01".

The decontamination process (column 174), for example, shows when, which facility, and which method was used to decontaminate the waste "P0111" and the waste before it was dismantled, and what the decontamination coefficient of the decontamination was. The decontamination day and decontamination coefficient can also be predetermined.

The dismantling process (column 175) shows when, in which facility, and in which method the waste "P0111" and the waste before it was dismantled were dismantled. The dismantling date can also be the scheduled date.

The measurement history (column 176) shows when, at which facility and by which method the waste was measured What is the result of the radiation dose of "P0111" and its waste before dismantling? In addition, the summary column displays the waste before dismantling showing this value.

The temporary storage information (column 177) shows when, in which facility, and in which container the waste "P0111" and the waste before dismantling were stored. The storage period may also be a predetermined period.

Final disposal information (column 178) shows when, which facility, and which disposal method was used to finally dispose of waste "P0111". The disposal date can also be a scheduled date.

(Processing order)

The processing procedure of this embodiment will be described below. There are three processing sequences, which are the planning creation processing sequence, the measurement processing sequence, and the history creation processing sequence.

(Plan creation processing sequence)

Figure 11 is a flow chart of the plan creation processing sequence. Currently, it is assumed that a certain atomic power station will be abandoned.

In step S201, the disposal plan creation unit 21 of the power plant disassembly management device 1 specifies the waste. Specifically, the disposal plan creation unit 21 receives the waste ID of a certain group of wastes (for example, a system) among the wastes from the power plant terminal device 2 . For convenience of explanation, here, it is assumed that the waste ID "P01" (condenser secondary side piping unit) is received.

In step S202, the treatment plan creation unit 21 obtains 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 Design Information 31 is based on the product Each part (piping, etc.) of "P01" is described with the designed radiation dose during normal operation of product "P01" and the attenuation characteristics after operation is stopped.

In step S203, the treatment plan creation unit 21 obtains 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 from the power plant terminal device 2 . The measurement information here has the form of one record of measurement information 34 in Figure 8 .

In step S204, the treatment plan creation unit 21 estimates the radiation dose. Specifically, the treatment plan creation unit 21 estimates the radiation dose using the design information 31 (design value) obtained in step S202 and the measurement information 34 (actual measurement value) obtained in step S203. The amount of radiation estimated here is, for example, the amount of radiation for each part of the time series starting from the current time point. There are also cases where parts that are designed to have a sufficiently low radiation dose actually have a high radiation dose.

In step S205, the treatment plan creation unit 21 specifies the radiation source. Specifically, the disposal plan creation unit 21 specifies the portion (piping, etc.) constituting the waste "P01" that has the highest radiation dose. There is a high possibility that a radioactive source is attached to this part. The treatment plan creation unit 21 may also specify the radiation source (symbol 48 in FIG. 3 ) based on the image captured by the robot operating the camera.

In step S206, the treatment plan creation part 21 determines whether decontamination is required. Specifically, the treatment plan creation unit 21 compares the radiation dose specified in step S205 with any of the following thresholds.

‧Threshold 1: The upper limit that can ensure the safety of nuclear power plant operators

‧Threshold 2: The upper limit for applying the target disposal method or reuse method

In step S207, the treatment plan creation part 21 determines whether decontamination is required. Specifically, when the comparison result in step S206 is that the radiation dose is equal to or greater than the threshold (step S207 "Yes"), the treatment plan creation unit 21 proceeds to step S209. Otherwise (step S207 "no") (No)"), proceed to step S208.

In step S208, the disposal plan creation part 21 determines the disassembly method. Specifically, the disposal plan creation unit 21 determines the dismantling method of the waste "P01" based on the design information 31 (materials, etc.) and the size of the container to be stored. When the mobile processing equipment can be used, the treatment plan creation unit 21 determines its use (the same applies to steps S209 to S211).

In step S209, the disposal plan creation part 21 determines the decontamination method before disassembly. Specifically, the disposal plan creation part 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 water-flowing system, the disposal plan making unit 21 selects chemical decontamination. Furthermore, select a chemical suitable for the material (heat-resistant steel) and radiation dose of waste "P01".

In step S210, the disposal plan creation part 21 determines the disassembly method. Specifically, the disposal plan creation unit 21 decontaminates the waste "P01" using the decontamination method determined in step S209, and based on this premise, determines the disposal based on the design information 31, the amount of radiation, the size of the container to be contained, etc. The disassembly method of object "P01".

In step S211, the disposal plan creation part 21 determines the decontamination method after disassembly. Specifically, the disposal plan creation part 21 determines the decontamination method for each part (piping, etc.) after disassembling the waste "P01" based on the design information 31 and the amount of radiation. At this time, the disposal plan creation unit 21 decontaminates the waste "P01" using the decontamination method determined in step S209, and disassembles the waste "P01" using the disassembly method determined in step S210. Based on this, Decide on the method of disassembly. The disassembly method decided here is, for example, mechanical decontamination of the pipes divided into half.

Alternatively, by repeating the processing of steps S209 to S211, the disposal plan making unit 21 can make a plan for decontaminating and dismantling the waste “P01” in multiple stages.

In step S212, the disposal plan creation unit 21 determines reuse and final disposal. Specifically, first, the disposal plan creation unit 21 receives the recycling materials required by the recycling facility, the required timing, and their purchase price from the recycling facility terminal device 6 of each recycling facility.

Secondly, the disposal plan creation unit 21 receives from the final disposal facility terminal device 5 of each final disposal facility the wastes that the final disposal facility can ingest in the future, their incorporation timing, and their disposal prices.

Third, the disposal plan creation unit 21 determines a reuse facility that can recycle the waste "P01" and the like, and/or a final disposal facility that can finally dispose of the waste "P01" and the like. "Waste "P01", etc." is the collective name for waste "P01" and its dismantled parts (the same applies hereafter). The disposal plan creation unit 21 determines the reuse facilities based on, for example, the purchase price presented at each reuse facility, and determines the final disposal facility based on, for example, the inclusion timing presented at each final disposal facility.

In step S213, the disposal plan creation part 21 determines the storage method and the transportation company. specific First, the disposal plan creation unit 21 sends the amount of waste "P01" and the like to be temporarily stored and the period until final disposal to the temporary storage facility terminal device 4 of each temporary storage facility. Then, the temporary storage facility terminal device 4 replies to the power plant dismantling management device 1 whether the temporary storage is possible and the storage fee.

Secondly, the disposal plan creation unit 21 sends the amount of waste "P01" and other materials to be transported between the nuclear power plant and each facility and between each facility, the amount of radiation, etc., to the transporter terminal device 7 of each transporter. Then, the transportation operator terminal device 7 replies whether transportation is possible and the transportation fee to the power plant disassembly management device 1 .

Third, the disposal plan creation unit 21 determines a temporary storage facility that can temporarily store the waste “P01” and the like, and a transportation company that can transport the waste. The disposal plan creation unit 21 determines a temporary storage facility based on the storage fees reported by each temporary storage facility, and determines a transportation provider based on the transportation fees reported by each transportation provider.

In step S214, the treatment plan creation unit 21 creates the treatment plan information 35 (Fig. 9). Specifically, the treatment plan creation unit 21 creates the treatment plan information 35 based on the content determined in steps S208 to S213, and stores the treatment plan information 35 in the auxiliary memory device 15. At this stage, each facility (stakeholder) associated with the waste "P01" in the disposal plan information 35 accesses the power plant disassembly management device 1 through its own terminal device, and can recognize the information related to the waste "P01" Records of disposal plan information35.

Thereafter, stakeholders carry out decontamination, dismantling, temporary storage, transportation, reuse and final disposal based on the disposal plan information 35. Each stakeholder implements the resolution plan information 35 from free Responsible part. However, there are also situations where the plan cannot be implemented.

In step S215, the treatment plan creation unit 21 receives the 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 disassembly of F01 has been carried out as planned", "the decontamination of F0111 has been changed to chemical decontamination", etc. The treatment plan creation unit 21 stores the received implementation report in the auxiliary memory device 15 .

In step S216, the treatment plan creation unit 21 memorizes the change points to the plan. Specifically, when the implementation report received in step S215 shows changes to the plan, the treatment plan creation unit 21 overwrites the treatment plan information 35 with the changed content and stores it in the auxiliary memory device 15 . Thereafter, the plan creation processing sequence ends.

In addition, steps S215 and S216 are repeated each time each stakeholder performs disassembly, decontamination, etc. As a result, the disposal plan information 35 is always maintained in the latest state.

The processing subject that obtains information from interested parties in the processing of steps S201 to S216 may also be the information collection unit 22. In this case, the information collection unit 22 hands over the acquired information to the solution plan creation unit 21 and entrusts subsequent processing.

(Measurement processing sequence)

Figure 12 is a flow chart of the measurement processing sequence. All interested parties can measure the radiation dose of the waste at any point in time. In this embodiment, each stakeholder other than the transportation operator measures the radiation dose of the waste before and after dismantling or decontaminating the waste through its own terminal devices 2 to 6, and sends it to the power plant disassembly management device 1 . Currently, for ease of illustration, treatment facilities are used 63 (Figure 2) as an example of a stakeholder.

In step S301, the information collection unit 22 of the power plant disassembly management device 1 determines whether preparations for disassembly are completed. Specifically, when the information collection unit 22 receives from the processing facility terminal device 3 of the processing facility 63 that the preparation for dismantling of the waste is completed (step S301 "Yes"), the information collection unit 22 proceeds to step S303, and otherwise proceeds to step S303. If so (step S301: No), proceed to step S302.

In step S302, the information collection unit 22 determines whether the preparation for decontamination is completed. Specifically, when the information collection unit 22 receives from the processing facility terminal device 3 of the processing facility 63 that the preparation for decontamination of the waste has been completed (step S302 "Yes"), the information collection unit 22 proceeds to step S303 . If this is the case ("No" in step S302), return to step S301.

In step S303, the information collection unit 22 obtains the radiation dose. Specifically, first, the information collection unit 22 receives the radiation dose of the waste from the processing facility terminal device 3 of the processing facility 63 .

Secondly, the information collection unit 22 creates a record of the measurement information 34 (Fig. 8) based on the received radiation dose.

In step S304, the information collection unit 22 determines whether the disassembly is completed. Specifically, the information collection unit 22 proceeds to step S306 when receiving from the processing facility terminal device 3 of the processing facility 63 that the disassembly of the waste has been completed (YES in step S304). In other cases, (No in step S304), proceed to step S305.

In step S305, the information collection unit 22 determines whether decontamination is completed. Specifically, when the information collection unit 22 receives the completion of decontamination of the waste from the processing facility terminal device 3 of the processing facility 63 (YES in step S305), the information collection unit 22 proceeds to step S306. In other cases, the information collection unit 22 proceeds to step S306. (No in step S305), return to step S304.

In step S306, the information collection unit 22 acquires the radiation dose and the like. Specifically, first, the information collection unit 22 receives the radiation dose of the waste from the processing facility terminal device 3 of the processing facility 63 .

Secondly, the information collection unit 22 creates a record of the measurement information 34 (Fig. 8) based on the received radiation dose.

Third, the information collection unit 22 receives the content of dismantling or decontamination of waste from the processing facility terminal device 3 of the processing facility 63 . In addition, the information received here may also be the same as the implementation report of step S215 (Fig. 11).

Fourth, the information collection unit 22 creates a record of the disassembly information 33 (Fig. 7) or the decontamination information 32 (Fig. 6) based on the received disassembly or decontamination content. After that, the measurement processing sequence ends.

As is clear from the above, the power 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.

(Process creation processing sequence)

Figure 13 is a flow chart of the procedure of process creation. Each stakeholder can request the power plant disassembly management device 1 for the process of the waste it handles. For convenience of explanation, it is currently 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 accommodate it.

In step S401, the history providing unit 23 of the power plant disassembly management device 1 receives a history request from the terminal device. Specifically, the history providing unit 23 receives the 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 keyword to obtain matching data from the information. Specifically, the history providing unit 23 uses the waste ID "P0111" as a search keyword to search for the design information 31 (Fig. 5), the decontamination information 32 (Fig. 6), the disassembly information 33 (Fig. 7), and the measurement information 34 (Figure 8), disposal plan information 35 (Figure 9) and other information. In addition, the history providing unit 23 obtains all data associated with "P0111". The "other information" here is the implementation report received by the treatment plan production part 21 in step S215 (Fig. 11).

In step S403, the history providing unit 23 creates 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 obtained in step S402. In addition, the data in the temporary storage information column 177 and the final disposal information column 178 in the waste history information 36 created here are in the planning stage.

In step S404, the history providing unit 23 sends the waste history information 36 (Fig. 10) to the terminal device. Specifically, the history providing unit 23 sends the waste history information 36 created in step S403 to the temporary storage facility terminal device 4 of the temporary storage facility 65 .

Thereafter, the process creation processing sequence is completed.

(Effects of this embodiment)

The effects of the power plant disassembly management device of this embodiment are as follows.

(1) The power plant dismantling management device can plan the steps of waste and allow stakeholders to share waste process information. Therefore, the power plant dismantling management device not only contributes to the traceability of waste, but also significantly reduces the management costs of all stakeholders.

(2) The power plant dismantling management device can receive waste-related information from stakeholders.

(3) The power plant dismantling management device can manage the dismantling, decontamination, and temporary storage of waste until its reuse or final disposal.

(4) The power plant dismantling management device can accurately and effectively plan the method of decontamination or dismantling after a specific radioactive source.

(5) The power plant dismantling management device can be applied to the waste furnace of the reactor.

(6) The power plant dismantling management device can use waste design information to determine decontamination and dismantling methods.

(7) The income from the management steps of dismantling the management equipment of the power plant.

(8) The power plant dismantling management device can update the steps based on performance.

In addition, the present invention is not limited to the above-described embodiment and includes various modifications. For example, the above-described embodiments are described in detail in order to easily understand the present invention, and are not necessarily limited to those having all the components described. Furthermore, part of the components of a certain embodiment may be replaced with components of another embodiment, and components of another embodiment may be added to the components of a certain embodiment. In addition, other components may be added, deleted, or replaced with part of the components of each embodiment.

In addition, each of the above-mentioned structures, functions, processing units, processing methods, etc. can be realized by, for example, integrated circuits. Road design, etc. are implemented in part or in whole by hardware. In addition, each of the above-mentioned components, functions, etc. can also be implemented in software by causing the processor to interpret and execute a program that implements each function. Programs, tables, files and other information to realize various functions can be placed in memory, hard disk, SSD (Solid State Drive: solid state drive) and other recording devices, or IC (Integrated Circuit: integrated circuit) card, SD (Secure Digital) : Secure Digital) card, DVD (Digital Video Disk: Digital Video Disc) and other recording media.

In addition, control lines or information lines are shown only when deemed necessary for explanation, and may not necessarily show all control lines or information lines on the product. It can also be considered that virtually all components are interconnected.

35: Disposal plan information

161: Information column before disassembly

162: Disassemble the information column at once

163:Second dismantling information column

164: Temporary storage information column

165: Final disposal information column

166:Reuse information column

167:Income column

Claims (10)

A power plant dismantling management device, characterized by having: a disposal plan production unit that plans the waste from the time it is discharged from the power plant until it is reused based on the design information of the waste discharged from the power plant and the amount of radioactivity of the waste. or the steps up to final disposal; and a process providing unit that sends process information to the terminal device of the above-mentioned stakeholder based on the waste identification code assigned to the above-mentioned waste based on the request from the stakeholder in the above-mentioned steps; and The above-mentioned wastes are equipment other than used fuel generated from the abandoned furnaces of nuclear power plants. The power plant dismantling management device of claim 1 includes: an information collection unit that receives information related to the waste handled by the above-mentioned stakeholders. For example, the power plant dismantling management device of claim 2, wherein the above steps include: at least one of the dismantling, decontamination and temporary storage of the above waste, the above process information includes: the design information of the above waste, and the above waste At least one of the information related to the radiation dose, decontamination, dismantling, temporary storage and final disposal of the object. For example, the power plant dismantling management device of Claim 3, wherein the above-mentioned disposal plan making department plans a method of decontamination or dismantling after identifying the part of the waste that becomes a radioactive source. For example, if the power plant dismantling management device of item 4 is requested, the above-mentioned stakeholders include: atomic energy power plant, the above-mentioned waste processing facilities, the above-mentioned waste temporary storage facilities, the above-mentioned waste recycling facilities, and the above-mentioned waste recycling facilities. At least one of the final disposal facilities. For example, if the power plant dismantling management device of item 5 is requested, the above-mentioned disposal plan production department shall decide whether it is necessary to decontaminate the above-mentioned waste and the amount of radioactivity of the above-mentioned waste based on the design information of the above-mentioned waste. At least one of the methods and methods for dismantling the above-mentioned waste. For example, the power plant dismantling management device of claim 6, wherein the above-mentioned disposal plan production department manages the income from the above-mentioned steps, and the above-mentioned steps include steps that can use equipment that can be used jointly among the above-mentioned stakeholders. For example, if the power plant dismantling management device in claim 7 is used, The above-mentioned disposal plan production department updates the above-mentioned steps based on the information received from the above-mentioned stakeholders. A power plant dismantling management method of a power plant dismantling management device, characterized in that the disposal plan making unit of the power plant dismantling management device plans the above-mentioned waste based on the design information of the waste discharged from the power plant and the radiation amount of the above-mentioned waste. The steps from the discharge of the waste from the above-mentioned power plant to the reuse or final disposal. The process provider of the above-mentioned power plant disassembly management device shall, based on the waste identification given to the above-mentioned waste, based on the request from the stakeholders in the above-mentioned step. The code sends the process information to the terminal devices of the above-mentioned stakeholders; and the above-mentioned wastes are equipment other than used fuel generated with the decommissioning of nuclear power plants. A power plant dismantling management program, characterized by causing a computer to function as a disposal plan production unit that plans the waste discharged from the power plant based on the design information of the waste discharged from the power plant and the radiation amount of the waste. The steps after discharge from the factory until reuse or final disposal; and the process providing department, which sends the process information to the above-mentioned stakeholders based on the waste identification code assigned to the above-mentioned waste based on the request from the stakeholders in the above-mentioned steps. terminal equipment; and the above-mentioned wastes are equipment other than used fuel produced with the abandoned furnaces of atomic energy power plants.