WO2017064930A1 - 放射性廃棄物の容器収容条件決定方法、放射性廃棄物収容方法および当該方法により製造される廃棄体 - Google Patents

放射性廃棄物の容器収容条件決定方法、放射性廃棄物収容方法および当該方法により製造される廃棄体 Download PDF

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WO2017064930A1
WO2017064930A1 PCT/JP2016/074890 JP2016074890W WO2017064930A1 WO 2017064930 A1 WO2017064930 A1 WO 2017064930A1 JP 2016074890 W JP2016074890 W JP 2016074890W WO 2017064930 A1 WO2017064930 A1 WO 2017064930A1
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Prior art keywords
waste
condition
storage
storage container
piece
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English (en)
French (fr)
Japanese (ja)
Inventor
知久 岡本
登 黒川
敏也 小室
俊光 馬越
小松　直隆
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Mitsubishi Heavy Industries Ltd
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Mitsubishi Heavy Industries Ltd
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Application filed by Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to CA2990372A priority Critical patent/CA2990372C/en
Priority to US15/739,400 priority patent/US20190074097A1/en
Priority to EP16855184.4A priority patent/EP3300083B1/en
Priority to KR1020177036539A priority patent/KR20180008773A/ko
Publication of WO2017064930A1 publication Critical patent/WO2017064930A1/ja
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16—Measuring radiation intensity
    • G01T1/167—Measuring radioactive content of objects, e.g. contamination
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/003—Nuclear facilities decommissioning arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present disclosure relates to a method for efficiently storing a waste piece obtained by cutting radioactive waste into a storage container, and a waste manufactured by the method.
  • Radioactive waste discharged from nuclear facilities etc. is permanently stored in a completely sealed state. Therefore, the amount of radioactive waste stored year by year is increasing, and the storage cost is also increasing. Under these circumstances, it is desirable to reduce the volume of radioactive waste generated as much as possible.
  • Patent Document 1 in order to enable safe recovery of control rod cluster guide tubes provided in the reactor vessel, the control rod cluster guide tubes are divided into a plurality of pieces, and each divided body is stored in a separate storage container.
  • a cutting volume reduction device is disclosed.
  • Patent Document 2 a thin board is placed on a cartridge containing radioactive waste, and pressed from above by a compression device, and the next radioactive waste is contained while maintaining the state, There is disclosed a volume reduction process in which the process of pressing from the top is sequentially repeated and the top is fixed with a lid and accommodated.
  • Patent Document 3 discloses a volume-reduction processing device that crushes radioactive waste and evacuates and compresses a storage bag filled with the crush material.
  • the cutting and volume reduction method described in Patent Document 2 requires cutting out radioactive waste in accordance with the volume of the storage container (so as not to be too large or too small compared to the volume of the storage container). There are significant limitations imposed on them and they are inflexible.
  • radioactive waste such as core structures with extremely high radioactive levels is not suitable for finely shredding (for example, in the form of powder) from the viewpoint of preventing radioactive contamination and diffusion, the cutting and volume reduction method described in Patent Document 3 It is difficult to handle by
  • an object of at least one embodiment of the present invention is to efficiently store a plurality of waste pieces in a storage container, thereby satisfying the physical constraints required for each waste body.
  • the plurality of waste pieces obtained by at least cutting radioactive waste are stored in at least one storage container to obtain the at least one waste body.
  • the container accommodation condition determination method for determining the accommodation condition of the waste piece of each of the storage container of each storage destination of the waste piece and a plurality of arrangement condition candidates for defining the accommodation position in the storage container, The step of selecting one or more of the candidate arrangement conditions satisfying the constraints required of the waste body for each of the storage containers, assuming that the waste pieces are arranged in the storage containers according to the candidate arrangement conditions.
  • a necessary storage container which is the number of the storage containers required to store the plurality of waste pieces according to the selected candidate for the placement condition Calculating a employs a configuration including a step of identifying the arrangement condition candidates the required storage container number is minimized.
  • the storage container to which each waste piece is stored and the storage position in the storage container are defined by the arrangement condition candidates. Then, in at least one embodiment of the present invention, one or more placement condition candidates satisfying the constraint conditions are selected from the plurality of placement condition candidates, and a plurality of waste pieces are selected from the selected placement condition candidates.
  • a candidate arrangement condition capable of reducing the number of storage containers required to store the container is determined as the storage condition of the waste piece in the storage container.
  • the storage condition of the waste piece thus obtained is a condition that satisfies the constraints of the individual wastes among the plurality of arrangement condition candidates, and the required number of storage containers is minimized. Therefore, according to at least one embodiment of the present invention, a plurality of waste pieces can be efficiently stored in the storage container, and the required number of storage containers can be satisfied while satisfying the physical constraints required for each waste body. Can be reduced.
  • the method of (1) selecting the arrangement condition candidate for each of the plurality of cutting conditions of the radioactive waste and the number of required storage containers Calculating a combination of the cutting condition and the placement condition candidate that minimize the number of required storage containers.
  • various ways of cutting when cutting radioactive waste to obtain plural waste pieces are defined as plural cutting conditions, and each of plural cutting conditions is specified.
  • the storage condition which can reduce the number of waste bodies obtained by storing the waste pieces in the storage container can be calculated.
  • the combination of the most efficient cutting condition and the arrangement condition as the accommodation condition capable of reducing the number of waste bodies by efficiently accommodating the waste pieces in the storage container It can be identified.
  • the method further includes the step of acquiring a radiation dose distribution of the radioactive waste, and selecting the arrangement condition candidate
  • the step is characterized in that, on the basis of the radiation dose distribution, the placement condition candidate satisfying the restriction condition which at least defines that the surface dose rate of the waste body becomes equal to or less than a threshold value is selected.
  • the method (3) is useful in such a case because it may be necessary to ensure the safety and efficiency in discarding or storing the waste.
  • the method of (1) or (2) further includes the step of measuring the radiation dose of each of the waste pieces, and selecting the placement condition candidate
  • the candidate arrangement conditions may be selected to satisfy the restriction condition which at least defines that the surface dose rate of the waste becomes equal to or less than a threshold.
  • the method (4) is useful in such a case because it may be necessary to ensure the safety and efficiency in discarding or storing the waste. According to the method of the above (4), by setting the surface dose rate for each waste to a threshold value or less based on the radiation dose distribution of radioactive waste, safety and efficiency in discarding or storing the waste can be improved. At the same time, the required number of storage containers can be reduced while ensuring.
  • the step of storing, in the database, the characteristic description information indicating the respective characteristics of the plurality of waste pieces is further included.
  • the step of selecting the placement condition candidate when the waste piece is placed in the storage container according to the placement condition candidate based on the characteristic description information stored in the database, each of the storage containers It may be determined whether or not the restriction condition required for the waste body is satisfied.
  • the operation of selecting the arrangement condition candidate for determining the arrangement method when arranging the waste piece in the storage container is a characteristic description showing the characteristic of each waste piece Based on the information, efficient volume reduction processing can be performed according to the characteristics of each waste piece.
  • the characterization information includes at least one of the shape, weight, or dose of each of the waste pieces.
  • the placement condition candidate can be selected in consideration of the shape, weight, or dose of the waste piece.
  • At least one type of compression treatment is performed on a plurality of divided bodies obtained by cutting the radioactive waste. And forming the plurality of waste pieces having a standardized shape.
  • the plurality of waste pieces obtained by cutting the radioactive waste is formed into a waste piece having a standardized shape (including the size) and then stored. Contained in a container. Therefore, according to the configuration of the above (7), it is possible to greatly simplify the calculation process for determining the storage condition for reducing the amount of waste obtained by storing the waste piece in the storage container. Further, in the configuration of (7) above, by appropriately designing the standardized shape, it is possible to calculate the storage condition in which the waste piece can be packed into the storage container as closely as possible.
  • the constraints required for the wastes are the weight, surface dose rate or surface dose rate of each of the wastes. It includes the condition that at least one of the calorific value falls within the allowable range.
  • at least one of the dose rate, weight and calorific value for each waste body is made within the allowable limit based on the radiation dose distribution of radioactive waste. This makes it possible to reduce the number of storage containers required while at the same time ensuring the safety and efficiency of waste transfer operations.
  • the plurality of arrangement condition candidates include a first waste piece in each storage container, The second waste is stored in a first area located in the center of the storage container, and a second waste piece having a radiation dose lower than that of the first waste piece surrounds the first waste piece. At least one candidate arrangement condition is stored in the second area surrounding the first area in the storage container.
  • the high-dose in the storage container Even if the first waste piece is stored, the low-dose second waste piece surrounding it functions as a radiation shield to reduce the radiation amount reaching the waste body surface. Therefore, if a plurality of arrangement condition candidates include arrangement condition candidates that define how to arrange waste pieces according to the above method (9), the number of available storage containers should be small and the containers should be accommodated. Even in situations where there are a large number of high-dose waste pieces, it is possible to increase the likelihood that such placement condition candidates will satisfy the constraints.
  • the waste piece is accommodated in the storage container according to the accommodation condition determined by any of the methods (1) to (9) above.
  • Obtaining at least one waste body may be provided.
  • the configuration of the above (10) by using the method of determining the container storage condition described in the above (1) to (9), a plurality of waste pieces are stored in one or more storage containers.
  • the embodiment according to the present invention can be implemented as a storage method of
  • a method of containing a plurality of waste pieces obtained by at least cutting radioactive waste in at least one storage container to obtain at least one waste body is the first waste Storing the object piece in a first area located at the center of the storage container, and a second waste piece having a radiation dose lower than that of the first waste piece surrounding the first waste piece Storing the second waste piece in a second area surrounding the first area in the storage container.
  • the waste having a relatively low radiation dose may be disposed around the waste piece having a relatively high radiation dose housed in the central portion of the storage container.
  • the pieces are arranged to surround as a radiation shield.
  • At least one waste body obtained by storing a plurality of waste pieces obtained by at least cutting radioactive waste in at least one storage container is A first waste piece housed in a first area located at a central portion, and a second area surrounding the first area in the storage container, the first waste piece being stored so as to surround the first waste piece; A second waste piece whose radiation dose is lower than that of the first waste piece; To provide a configuration.
  • the waste piece having a low dose is a radiation shielding material around the waste piece having a high dose stored in the central part of the storage container. It is generated in the form of being arranged as surrounding. Therefore, the waste according to the above embodiment (12) is a waste that is capable of containing more pieces of waste with a higher radiation dose at a higher filling rate in the storage container as compared with the conventional accommodation method. can do.
  • the low dose waste piece surrounding the high dose waste piece functions as a radiation shield in the storage container. Thereby, the waste according to the embodiment of the above (12) can effectively reduce the surface dose rate and the calorific value on the surface of the waste even if waste pieces of high radiation dose are accommodated. Waste disposal and storage can be facilitated.
  • the need for the storage container is satisfied while satisfying the physical constraints required for each waste body.
  • the number can be reduced.
  • FIG. 1 shows a computer system according to an embodiment of the present invention. It is a flow chart which shows a flow of a series of processing operations concerning one embodiment of the present invention.
  • it illustrates the process of shaping the waste piece into a standardized shape.
  • It is a figure showing a computer system concerning this embodiment.
  • It is a flowchart which shows the flow of a series of processing operation which concerns on this embodiment.
  • It is a figure which shows a mode that the waste piece was accommodated in the storage container in this embodiment.
  • FIG. 1 is a diagram showing an entire flow of a method of treating radioactive waste according to an embodiment. As shown in FIG.
  • the storage condition of at least one storage container 91 (91A to 91C) of the plurality of waste pieces 900 obtained by at least cutting the radioactive waste 9 is determined According to the storage condition, the waste piece 900 is stored in the storage container 91 (91A to 91C) to obtain the waste body 950 (950A to 950C).
  • the radioactive waste 9 is illustrated as the reactor internals 9 a in the reactor vessel 1, but in other embodiments, the radioactive waste 9 is a reactor. It is good also as reactor containers other than internals, a steam generator, piping etc. In yet another embodiment, the radioactive waste 9 may be low-level radioactive waste emitted from nuclear related facilities.
  • FIG. 2 and FIG. 3 are diagrams each showing an example of a plurality of arrangement condition candidates used in the waste disposal method shown in FIG.
  • FIG. 4 is a figure which shows the correspondence between the set of arrangement condition candidates, the sufficiency of a constraint condition, and the required number of storage containers 91 in one Embodiment of this invention.
  • the placement condition candidate is a condition for specifying this pattern. That is, the placement condition candidate is a condition that defines the storage container 91 (91A to 91C) of the storage destination of each waste piece 900 and the storage position in the storage container 91 (91A to 91C).
  • the shape (including the dimensions) of the waste piece 900 is non-uniform and random three-dimensional.
  • each waste piece 900 is represented in a simple two-dimensional shape, and in the space in the box-shaped container represented by a rectangular two-dimensional area, in order to simplify the explanation and simplification.
  • a schematic example of dimensional accommodation is shown.
  • the shape of the waste piece 900 is also different between the example shown in FIG. 2 and the example shown in FIG.
  • the specific accommodation position of the waste piece 900 in a container is illustrated only about the first three storage containers 91-1 to 91-3, and the fourth and subsequent ones.
  • the specific storage position in the storage container 91 is omitted.
  • positioning conditions which determine the method of accommodation at the time of accommodating the several waste piece 900 in the one or more storage containers 91, other arbitrary arrangement
  • the constraints mean constraints on the characteristics of the waste body 950 that must be satisfied as the waste body 950 as a whole.
  • the constraint includes the condition that at least one of the weight, surface dose rate or calorific value of each waste body 950 falls within an acceptable range.
  • the constraint includes the condition that all of the weight, surface dose rate and calorific value of each waste body 950 fall within an acceptable range.
  • waste pieces 900 in the storage container 91 according to each of N arrangement condition candidates A i (1 ⁇ i ⁇ N, where N is an integer of 2 or more). It is determined on the assumption that the storage containers 91 (91A to 91C) satisfy the constraints required for the wastes. Then, from among the i arrangement condition candidates, one or more arrangement condition candidates satisfying the restriction condition required for the waste body are selected for each storage container 91 (91A to 91C). Note that FIG. 4 shows, as an illustrative embodiment, a case where placement condition candidates A 1 , A 2 , A 5 , A 6 , and A 8 are selected as the condition that satisfies the constraint condition.
  • a constraint that at least the surface dose rate of the waste body 950 (950A to 950C) becomes equal to or less than the threshold based on the radiation dose distribution of the radioactive waste 9 J (1 ⁇ j ⁇ N) placement condition candidates that satisfy the condition are selected.
  • the method of obtaining the radiation dose distribution of the radioactive waste 9 is not particularly limited.
  • the radiation dose distribution may be obtained from the result of measuring the radiation dose distribution of the radioactive waste 9 at a plurality of measurement points, The radiation dose distribution may be estimated based on the past radiation exposure history of the radioactive waste 9.
  • the placement condition candidate that minimizes the required storage container number X is specified.
  • the placement condition candidate thus obtained is a condition satisfying the constraint condition and having the minimum required number of storage containers X among the i placement condition candidates A examined. Therefore, according to the method described above, the plurality of waste pieces 900 can be efficiently stored in the storage container 91, and the required number of storage containers 91 can be satisfied while satisfying the physical constraints required for each waste body. The required number of storage containers X can be reduced.
  • a plurality of cutting conditions for the radioactive waste 9 that may contribute to the reduction of the required number of storage containers X may be selected.
  • cutting conditions such as cutting high dose portions in radioactive waste at fine intervals (fine particle size) and cutting low dose portions in radioactive waste at large intervals (coarse particle size) You may set it.
  • FIG. 5 shows an exemplary method for cutting the internals 9a of the reactor 1 to obtain a plurality of waste pieces 900 (e.g. 900A to 900E) having a high radiation dose. Cutting conditions are illustrated.
  • the high-dose region 90 shown in FIG. 5 indicates a portion where the radiation dose is particularly high in the furnace, and the cutting conditions are set so that the particle size is cut with a finer particle size than the other portions in the internal 9a.
  • 900A-900C have larger particle sizes than 900D and 900E).
  • other arbitrary cutting conditions other than cutting condition B shown in FIG. 5 can also be used.
  • the step of selecting the placement condition candidate A j and the step of calculating the required number of storage containers X are performed for each of the plurality of cutting conditions B k. It is characterized in that the combination of B and the placement condition candidate A is specified.
  • the arrangement condition candidates of A 1 and A 2 are selected as the condition satisfying the constraint condition are, required storage container number X corresponding to the arrangement condition candidate a 1 and a 2 are five and four, respectively.
  • arrangement condition candidates A 5 and A 6 in the arrangement candidate conditions in the case of cutting conditions B 2 cut radioactive waste 9 are selected as satisfying the constraint condition condition, arrangement condition candidate A 5 and A
  • the required storage container numbers X corresponding to 6 are 6 and 5 respectively.
  • the layout condition candidate satisfies the constraints condition A 8 in the arrangement candidate conditions in the case of cutting the radioactive waste 9 in cutting conditions B 3, to be corresponding to the arrangement condition candidate A 8
  • the number of storage containers X is six. Accordingly, in the exemplary embodiment shown in FIG. 4, as a combination of cutting conditions B and arrangement condition candidate A required storage container number X is minimized, the combination of the arrangement condition Candidate A 2 and the cutting conditions B 1 is identified .
  • various cutting methods when cutting the radioactive waste 9 to obtain the plurality of waste pieces 900 are defined as the plurality of cutting conditions B,
  • a storage condition capable of reducing the number of waste bodies 950 obtained by storing the waste piece 900 in the storage container 91 can be calculated for each of the cutting conditions.
  • the most efficient cutting condition as a storage condition capable of reducing the number of waste bodies 950 by efficiently storing the waste piece 900 in the storage container 91.
  • a combination of B and placement condition A can be specified.
  • the method for determining container accommodation condition further includes the step of acquiring the radiation dose distribution of the radioactive waste 9, and in the step of selecting the arrangement condition candidate A ′ j , the acquired radiation dose distribution is selected. based on, may be selected to satisfy the constraint placed condition candidate a 'j of the surface dose rate is at least stipulates that falls below the threshold value of the waste 950 (950A ⁇ 950C). The above method is useful in such a case because it may be necessary to ensure the safety and efficiency in discarding or storing the waste body 950 (950A to 950C).
  • safety and efficiency in discarding or storing the waste body 950 can be achieved by setting the surface dose rate for each waste body 950 equal to or less than the threshold value based on the radiation dose distribution of the radioactive waste 9 At the same time, it is possible to reduce the required number of storage containers X, which is the required number of storage containers, while securing the property.
  • the container housing conditions determination method further comprises a step of measuring a radiation dose distribution of a radioactive waste 9, in the step of selecting an arrangement candidate conditions A 'j, the radiation dose distribution that the measured based on, may be selected to satisfy the constraint placed condition candidate a 'j of the surface dose rate is at least stipulates that falls below the threshold value of the waste 950 (950A ⁇ 950C).
  • the above method is useful in such a case because it may be necessary to ensure the safety and efficiency in discarding or storing the waste body 950 (950A to 950C).
  • safety and efficiency in discarding or storing the waste body 950 can be achieved by setting the surface dose rate for each waste body 950 equal to or less than the threshold value based on the radiation dose distribution of the radioactive waste 9 At the same time, it is possible to reduce the required number of storage containers X, which is the required number of storage containers, while securing the property.
  • the storage container 91 as the storage destination of each waste piece 900 and the storage position in the storage container 91 are defined by the arrangement condition candidate A.
  • the arrangement condition candidate A among the plurality of arrangement condition candidates A i (1 ⁇ i ⁇ N), the number of storage containers 91 necessary for storing the plurality of waste pieces 900 is necessary.
  • the storage container number X reduce possible arrangement candidate conditions a o is determined as capacity limitations for waste piece into the storage container. Therefore, according to at least one embodiment of the present invention, when the plurality of waste pieces 900 are stored in at least one storage container 91 to obtain at least one waste body 950, the amount of waste bodies 950 can be reduced. Containment conditions can be calculated.
  • a placement condition candidate A j that satisfies a constraint that at least defines that the surface dose rate of the waste body 950 is less than or equal to the threshold value based on the radiation dose distribution.
  • the radiation dose information for each waste piece 900 is relevant.
  • the surface dose rate of the waste body 950 can be obtained. Then, by determining whether or not the surface dose rate of the waste body 950 is equal to or less than the threshold value, it is determined whether the arrangement condition candidate A ′ j satisfies the above constraint condition.
  • the container accommodation condition determination method described above may be implemented using any computer program executed on any computer system.
  • the container accommodation condition determination method described above may be implemented using a computer program 124 executed in computer system 10 shown in FIG.
  • the computer system 10 includes a computer 100a communicably connected to each other by a local area network 230a, a database 210a, and a control console 220a.
  • the computer 100a executes the computer program 124 in response to an instruction from the control console 220a.
  • the database 210 a identifies each of the one or more waste bodies 950 by identification information of a tag attached to each waste body 950, and characterization information describing the physical property condition for each waste body 950 as each waste body They are stored in association with 950.
  • the control console 220a may function as a terminal for the system user to give instructions and information to the computer program 124 on the computer 100a and displaying the output of the computer program 124 on the screen.
  • the computer 100a is configured of a CPU 110a, a main storage 120a, and an interface 130a.
  • the CPU 110a reads out and executes the computer program 124 stored on the main storage 120a.
  • the main memory 120a stores information on a plurality of (N) cutting conditions 121k (1 ⁇ k ⁇ N) and a plurality of (M) arrangement condition candidates 122i (1 ⁇ i ⁇ M). Further, the main memory 120a stores data representing other information other than the above in the temporary storage area 123a.
  • the interface 130a provides a communication path for exchanging data and control signals between the CPU 110a, the main memory 120a and the local area network 230a.
  • a plurality of program modules or functions constituting the computer program 124 may be read from the main storage 120a by the CPU 110a and executed as functional modules 111a to 118a.
  • the input / output and main control unit 111a functions as an input / output unit for the functional modules 112a to 118a described above to exchange data, control commands, etc. with the main memory 120a, the database 210a and the control console 220a. Further, the input / output and main control unit 111a has a role of controlling the overall flow of a series of processing operations executed by the above-described functional modules 112a to 118a. For example, the series of processing operations executed by the above-described functional modules 112a to 118a are looped until a combination of cutting conditions and candidate arrangement conditions is found that minimizes the required number of storage containers when all waste pieces are accommodated. It must be repeatedly executed by control. Therefore, the input / output and main control unit 111a repeatedly calls and executes the above-described functional modules 112a to 118a for the number of times of repetitive execution controlled by the loop control.
  • the arrangement condition candidate generation unit 113a generates the storage container 91 of the storage destination of each waste piece 900 and a plurality of arrangement condition candidates 122i (1 ⁇ i ⁇ M) that define the storage position in the storage container 91. . Subsequently, the placement condition candidate selection unit 114a that has received the plurality of placement condition candidates 122i (1 ⁇ i ⁇ M) generated by the placement condition candidate generation unit 113a follows the plurality of placement condition candidates 122i (1 ⁇ i ⁇ M). Assuming that the waste piece 900 is placed in the storage container 91, one or more candidate for placement condition 122j (1 ⁇ j ⁇ M) satisfying the restriction condition required for the waste body is selected for each storage container 91 Do.
  • the required storage container number calculation unit 115a that has received one or more selected arrangement condition candidates 122j (1 ⁇ j ⁇ M) determines the plurality of waste pieces 900 according to the selected arrangement condition candidates 122j (1 ⁇ j ⁇ M). Calculate the required number of storage containers X, which is the number of storage containers 91 required to accommodate.
  • the optimal placement condition candidate identification unit 116a receives the plurality of placement condition candidates 122j (1 ⁇ j ⁇ M) and the required storage container number X calculated for each placement condition from the required storage container number calculation unit 115a.
  • the placement condition candidate 122 (0) which minimizes the value is identified and output to the input / output and main control unit 111a.
  • the process performed by the functional modules 113a-118a may be performed for each of a plurality of radioactive waste cutting conditions 121k (1 ⁇ k ⁇ N).
  • the cutting condition acquisition unit 112a acquires a plurality of cutting conditions 121k (1 ⁇ k ⁇ N), and stores the acquired plurality of cutting conditions 121k (1 ⁇ k ⁇ N) in the main storage 120a. Do. Subsequently, the process of selecting the arrangement condition candidate 122 j (1 ⁇ j ⁇ M) and the process of calculating the required number of storage containers X are acquired by the cutting condition acquiring unit 112 a and the plurality of cutting conditions stored in the main memory 120 a.
  • the optimum arrangement condition candidate identification unit 116a identifies a combination of the cutting condition 121k (1 ⁇ k ⁇ N) and the arrangement condition candidate 122j (1 ⁇ j ⁇ M) that minimizes the required number of storage containers X.
  • the cutting condition acquiring unit 112a acquires the characteristic description information indicating the respective characteristics of the plurality of waste pieces 900, and the database 210a. You may save it to In at least one embodiment, the following operation may be performed in the process of selecting the placement condition candidate 122 j (1 ⁇ j ⁇ M). First, the characteristic description information acquisition unit 118a is instructed to acquire the characteristic description information stored in the database 210a.
  • each waste body 950 for each storage container 91 The placement condition candidate selection unit 114a determines whether the constraint condition required for the condition is satisfied.
  • the flowchart of FIG. 7 starts from step S801 by the radiation dose distribution acquisition unit 117a being called by the input / output and main control unit 111a.
  • the radiation dose distribution acquiring unit 117a acquires radiation dose distribution measurement data regarding radioactive waste before being cut into a plurality of waste pieces 900, and cuts the radiation dose distribution measurement data through the main memory 120a into the cutting condition acquiring unit 112a. Pass to
  • the cutting condition acquisition unit 112a acquires the plurality of cutting conditions 121k (1 ⁇ k ⁇ N) of the radioactive waste while referring to the radiation dose distribution measurement data, and acquires the plurality of acquired cutting conditions 121k (1 ⁇ ). Store k ⁇ N) in the main memory 120 a.
  • the arrangement condition candidate generation unit 113a reads a plurality of cutting conditions 121k (1 ⁇ k ⁇ N) from the main memory 120a
  • the arrangement condition candidate generating unit 113a selects one or more unselected cutting conditions 121k (1 ⁇ k ⁇ N)
  • One cutting condition 121 ' is selected.
  • the arrangement condition candidate generation unit 113a generates one arrangement condition candidate 122j based on the selected cutting condition 121 ', and stores the one arrangement condition candidate 122j in the main storage 120a.
  • step S804 the placement condition candidate selection unit 114a reads the placement condition candidate 122j from the main memory 120a, and uses the characteristic description information for each waste piece obtained from the placement condition candidate generation unit 113a to obtain the placement condition. It is determined whether the candidate 122 j satisfies the constraint condition required for each waste body. Subsequently, in step S805, if the arrangement condition candidate selection unit 114a determines that the arrangement condition candidate 122j satisfies the predetermined constraint condition, the process proceeds to step S806 in FIG. 7 and it is determined that the condition is not satisfied. The process proceeds to step S807 in FIG.
  • the placement condition candidate selection unit 114a may select placement condition candidates as described below with reference to FIG. 12 as placement condition candidates satisfying the above constraint conditions. Specifically, the placement condition candidate selection unit 114a sets a low dose around the high-dose waste piece 920 (FIG. 12) disposed at the center in the storage container 91 as a placement condition candidate satisfying the above constraint conditions. Arrangement condition candidates may be selected such that the waste piece 930 (FIG. 12) is surrounded.
  • step S806 in FIG. 7 when the required storage container number calculation unit 115a receives the placement condition candidate 122j determined that the placement condition candidate selection unit 114a is a candidate satisfying the above constraint condition, the required storage container for the placement condition candidate 122j is stored. Calculate the number X.
  • the required number of storage containers X is a value in which the number of storage containers 91 required when storing all of the plurality of waste pieces 900 in one or more storage containers 91 in accordance with each arrangement condition candidate is predicted.
  • step S807 in FIG. 7 the arrangement condition candidate generation unit 113a can generate another arrangement condition candidate from the plurality of waste pieces 900 obtained by cutting the radioactive waste according to the currently selected cutting condition 121 '. It is determined whether the If another arrangement condition candidate can be generated, the process returns to step S 803 in FIG. 7, and the arrangement condition candidate generation unit 113 a can obtain the radioactive waste according to the currently selected cutting condition 121 ′. Another arrangement condition candidate is generated from the plurality of waste pieces 900. If, in step S807, the placement condition candidate generation unit 113a determines that another placement condition candidate can not be generated any more from the plurality of waste pieces 900 obtained according to the currently selected cutting condition 121 ', the process is performed as shown in FIG. The process proceeds to step S808.
  • step S808 in FIG. 7 the cutting condition acquisition unit 112a processes the steps S802 to S807 in FIG. 7 among the plurality of cutting conditions 121k (1 ⁇ k ⁇ N) stored in the main memory 120a. It is determined whether there are unselected unselected cutting conditions left. If an unselected cutting condition remains, the process returns to step S802, and the cutting condition acquisition unit 112a does not select among the plurality of cutting conditions 121k (1 ⁇ k ⁇ N) stored in the main memory 120. Choose a new cutting condition for selection. If no unselected cutting condition remains in the plurality of cutting conditions 121k (1 ⁇ k ⁇ N), the process proceeds to step S809.
  • the optimal arrangement condition candidate identification unit 116a calculates the required number of storage containers X calculated for each of the plurality of arrangement condition candidates and the arrangement conditions for all of the plurality of cutting conditions 121k (1 ⁇ k ⁇ N). It receives from calculation part 115a. Subsequently, the optimum placement condition candidate identification unit 116a determines the required number of storage containers 91 out of the required storage container number X calculated for each placement condition candidate for each of the plurality of cutting candidates 121k (1 ⁇ k ⁇ N). Identify the set of efficient placement condition candidates and cutting candidates that minimize. Finally, the optimum arrangement condition candidate specifying unit 116a outputs the set of the specified optimum arrangement condition candidate and the cutting candidate to the input / output and the main control unit 111a.
  • a plurality of such waste pieces 910 which are cut out from the reactor according to predetermined cutting conditions and discharged from the nuclear power plant 93 are separated according to the dose. It is also good.
  • the plurality of waste pieces 910 may be separated by the sorting device 94 into a high dose piece (G1 in FIG. 8), a medium dose piece (G2 in FIG. 8) and a low dose piece (G2 in FIG. 8). It divides into G3) of FIG.
  • the forming suitable for the waste pieces 910 sorted according to the dose is performed. Do the processing.
  • arrangement conditions capable of reducing the required number of storage containers are determined, and all waste pieces 910 are accommodated in one or more storage containers 91 according to the determined arrangement conditions.
  • One or more waste bodies 960 (960A to 960C) are produced and stored in a storage building 92.
  • a plurality of divided bodies 940 obtained by cutting the radioactive waste 9 are formed into a standardized shape (including dimensions) by compression molding.
  • a plurality of waste pieces 910 may be accommodated in one or more storage containers 91 according to suitable arrangement conditions.
  • the standardized shape (including the dimensions) of the waste piece will be referred to as a standardized shape.
  • the length of the long side, the length of the short side, and the depth of the cross section of the storage space in the storage container 91 are divided by appropriate integers
  • the dimensions cut off may be the vertical, horizontal, and height dimensions, and the shape having the dimensions may be a standardized shape.
  • the dimensions of the length, width, and height of the waste piece 910 are the length of the long side, the length of the short side, and the depth of the storage space cross section in the storage container 91. May be divided by an appropriate integer, and the waste piece 910 may be compression molded so as to be rounded off.
  • the long side length, the short side length and the depth of the section of the storage space in the storage container 91 are Lx, Ly and Lz, respectively.
  • appropriate integers ⁇ , ⁇ and ⁇ are used.
  • the dimensions lx, ly and lz of the height, width and height of the standardized shape may be calculated according to the following equation.
  • the above-described compression molding process is performed by cutting, compressing, dissolving, or a combination of these processes on a plurality of divided bodies 940 cut out of the radioactive waste 9 Also good.
  • the radioactive waste 9 may include a furnace internal 9a that is cut by a cutting tool.
  • the plurality of divided bodies 940 obtained by cutting the radioactive waste may be sorted according to the radioactive level, for example, by the sorting device 94 shown in FIG.
  • radioactive waste 9 (S1 in FIG. 9) is cut into a plurality of divided bodies 940 and disassembled (S2 in FIG. 9), and the plurality of divided bodies 940 are used for the compression molding process
  • the sheet is compression-molded from the front, rear, left and right, and the top and bottom (S3 in FIG. 9) by a plate-like pressing member included in the compression device (S3 in FIG. 9), and molded into a cube having standardized dimensions (S4 in FIG. 9).
  • the compression molding process described above with reference to FIG. 9 is performed on the waste piece 910 after the waste piece 910 is separated by the sorting device 94 in the disposal procedure shown in FIG. It may be implemented as a molding process.
  • a plurality of divided bodies 940 formed by cutting radioactive waste are separated according to the radiation dose as in the modified embodiment shown in FIG. 8, and the divided bodies are compression molded for each separated radiation level.
  • standardized shapes corresponding to high radiation levels are designed with small dimensions to small size or fine particle size
  • standardized shapes corresponding to low radiation levels are designed with large size to large size or coarse particle size It is also good.
  • the above-mentioned integers ⁇ , ⁇ and ⁇ used for dividing Lx, Ly and Lz described above as the length and the length of the long side of the long side of the storage space cross section in the storage container 91 into the desired particle size Adjust accordingly.
  • the dimensions lx, ly and lz of the height, width and height of the standardized shape are calculated according to the above equation (1).
  • the high radiation dose waste pieces have a standardized shape of small dimensions, so it is possible to avoid storing a large amount of high dose pieces in one storage container at one time.
  • waste pieces with high radiation dose have a standardized shape with small dimensions, so it can be accommodated in each storage container while finely adjusting the amount of high-dose waste pieces little by little, and the surface dose rate for each storage container It becomes easy to be within the allowable range.
  • the above integers ⁇ , ⁇ and ⁇ used to divide Lx, Ly and Lz described above as the long side length, short side length and depth of the storage space cross section in the storage container 91 are desired. Adjust according to particle size. Then, the dimensions lx, ly and lz of the height, width and height of the standardized shape are calculated according to the above equation (1).
  • the embodiment shown in FIG. 9 may be implemented, for example, using a computer program 125 executed on computer system 20 shown in FIG.
  • a computer program 125 executed on computer system 20 shown in FIG.
  • FIG. 10 in order to explain the system configuration according to the embodiment shown in FIG. 10, only the differences between the embodiment shown in FIG. 10 and the embodiment shown in FIG. 6 will be described, and the embodiment shown in FIG. Description of the same configuration as that of the above will be omitted.
  • all the waste pieces 910 are treated as being formed into a simple standardized shape, and efficient placement condition candidates can be obtained without considering multiple cutting conditions. It differs from the embodiment shown in FIG. 6 in that it can be determined. Further, in the embodiment shown in FIG. 10, the surface dose rate, calorific value, weight and the like of each of the plurality of waste pieces 910 formed into a standardized shape are obtained by actual measurement in advance in the following pretreatment, The values are recorded in database 210b. In one embodiment, this pre-processing may be performed with the intervention of a worker in the nuclear power plant prior to determining efficient placement condition candidates using computer system 20. .
  • the characteristic description information for each waste piece includes the actual measurement values measured in advance as described above for each of the plurality of waste pieces 910, and two or more types of standardized shapes are defined according to the plurality of radioactive levels. If yes, it may also include information on the type of standardized shape.
  • steps S1201 to S1206 correspond to the above-described pretreatment, and the plurality of divided bodies obtained by cutting the radioactive waste are compressed and processed to have at least one standardized shape.
  • the process of forming into a waste piece and the process of measuring the weight, radiation dose and calorific value of each said waste piece are included.
  • steps S1207 to S1212 correspond to the processing executed by the functional modules 113 to 118 configuring the computer program 125 to determine efficient placement condition candidates using the computer system 20. Do.
  • step S1201 The process of the flowchart of FIG. 11 starts from step S1201, and the radioactive waste is cut into a plurality of divided bodies and disassembled. Subsequently, the process proceeds to step S1202, and the plurality of divided bodies are molded so as to have a standardized shape.
  • the plurality of divided bodies are separated according to the radioactive level, the plurality of divided bodies are formed and processed according to standardized shapes of two or more different sizes for each radioactive level, and a plurality of waste pieces 910 May be obtained.
  • step S 1203 each of the plurality of waste pieces 910 is tagged. In the tag attached to each of the plurality of waste pieces 910, identification information for uniquely identifying each waste piece 910 is recorded. Subsequently, the process proceeds to step S 1204, where the weight of each waste piece is measured for each of the plurality of waste pieces. In addition, when two or more types of standardized shapes are defined, it is also determined as to which type of standardized shape each of the plurality of waste pieces has. Subsequently, the process proceeds to step S1205, and the surface dose rate and calorific value for each waste piece are measured for each of the plurality of waste pieces.
  • step S1206 information representing the weight for each waste piece actually measured or determined as described above for each of the plurality of waste pieces, type of standardized shape, surface dose rate and calorific value, etc. It is recorded in the database 210b.
  • information representing weight for each waste piece, type of standardized shape, surface dose rate, calorific value, etc. is for each waste piece recorded in a tag attached to each of the plurality of waste pieces 910.
  • step S1207 the placement condition candidate selection unit 114b may select placement condition candidates as described below with reference to FIG. 12 as placement condition candidates satisfying the above constraint conditions. Specifically, the placement condition candidate selection unit 114b sets a low-dose waste piece around the high-dose waste piece 910 placed at the center in the storage container 91 as a placement condition candidate satisfying the above constraint conditions. You may select candidate placement conditions that surround it.
  • a plurality of waste pieces 900 (920, 930) obtained by at least cutting the radioactive waste 9 (9a) is contained in at least one storage container 91 to obtain at least one waste body 950.
  • the second waste piece 930 which contains the first waste piece 920 in the first area located at the center of the storage container 91 and whose radiation dose is lower than that of the first waste piece 920 is the first waste piece
  • a second waste piece 930 may be stored in the storage container 91 in a second area surrounding the first area to surround 920.
  • the plurality of arrangement condition candidates 122 i (1 ⁇ i ⁇ M) are firstly discarded in each storage container 91.
  • Object piece 920 is accommodated in a first area located at the center of the storage container 91, and a second waste piece 930 having a radiation dose lower than that of the first waste piece 920 surrounds the first waste piece 920
  • the second waste piece 930 may be stored in a second area surrounding the first area in the storage container 91, and may include at least one candidate arrangement condition.
  • the arrangement condition candidate generation units 113 a and 113 b refer to FIG. 12 as at least one of the plurality of arrangement condition candidates 122 i (1 ⁇ i ⁇ M).
  • candidate arrangement conditions may be included which define how to arrange the waste pieces 920 and 930 described above.
  • candidate arrangement conditions which define the arrangement (FIG. 12) of surrounding the high-dose waste piece 920 in the storage container 91 with the low-dose waste piece 930. Even if the high-dose waste piece 920 is contained, the low radiation dose waste piece 930 surrounding it can function as a radiation shield to reduce the radiation amount reaching the waste body 950 surface. Therefore, if a plurality of placement condition candidates include candidates for defining the disposition method of the waste piece as shown in FIG. Even in the situation where there are many waste pieces of dose 920, such a placement condition candidate can increase the possibility of satisfying the constraints.

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PCT/JP2016/074890 2015-10-16 2016-08-25 放射性廃棄物の容器収容条件決定方法、放射性廃棄物収容方法および当該方法により製造される廃棄体 Ceased WO2017064930A1 (ja)

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CA2990372A CA2990372C (en) 2015-10-16 2016-08-25 Method of determining conditions for accommodating radioactive waste in container, radioactive waste accommodating method, and waste body produced using said method
US15/739,400 US20190074097A1 (en) 2015-10-16 2016-08-25 Method of determining conditions for accommodating radioactive waste in container, radioactive waste accommodating method, and waste body produced using said method
EP16855184.4A EP3300083B1 (en) 2015-10-16 2016-08-25 Method of determining conditions for accommodating radioactive waste in container and radioactive waste accommodating method
KR1020177036539A KR20180008773A (ko) 2015-10-16 2016-08-25 방사성 폐기물의 용기 수용 조건 결정 방법, 방사성 폐기물 수용 방법 및 당해 방법에 의해 제조되는 폐기체

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JP6863865B2 (ja) * 2017-09-12 2021-04-21 日立Ｇｅニュークリア・エナジー株式会社 クリアランス計測システムおよび方法
JP7168428B2 (ja) * 2018-12-03 2022-11-09 日立Ｇｅニュークリア・エナジー株式会社 廃棄物処理装置、および、廃棄物処理方法
WO2023056052A2 (en) * 2021-09-30 2023-04-06 Deep Isolation, Inc. Radioactive waste canister systems and methods
FR3131064B1 (fr) * 2021-12-21 2024-02-16 Electricite De France Procédé de conditionnement de déchets nucléaires
FR3131065B1 (fr) * 2021-12-21 2024-02-09 Electricite De France Procédé de gestion d’un déchet nucléaire
KR102898185B1 (ko) * 2023-08-24 2025-12-09 한국수력원자력 주식회사 원자로 내부구조물의 절단 및 절단물의 장입 방법
CN117727481A (zh) * 2023-11-23 2024-03-19 中广核核电运营有限公司 废物整备方法、装置、计算机设备和存储介质
CN119358168B (zh) * 2024-11-12 2026-01-09 中国原子能科学研究院 反应堆构件的切割方法
JP7881035B1 (ja) * 2025-12-23 2026-06-26 三菱重工業株式会社 原子炉設備の解体方法

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59126297A (ja) * 1983-01-06 1984-07-20 株式会社日立製作所 不燃性雑固体廃棄物の処理方法
JPS6289000A (ja) * 1985-10-16 1987-04-23 日本碍子株式会社 放射性廃棄物の充填処理方法
JP2002207098A (ja) * 2001-01-11 2002-07-26 Toshiba Corp 放射性固体廃棄物処理方法
JP2015087300A (ja) * 2013-10-31 2015-05-07 日立Ｇｅニュークリア・エナジー株式会社 プラント解体計画支援装置及びプラント解体計画支援方法

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5961800A (ja) * 1982-10-01 1984-04-09 株式会社東芝 放射性廃棄物の保管方法
JPS60146200A (ja) * 1984-01-11 1985-08-01 株式会社日立製作所 放射性廃棄物充填方法
DE3842215A1 (de) * 1988-12-15 1990-06-21 Bayer Ag Verfahren zur deponierung von abfaellen
WO1996041348A1 (en) * 1995-06-07 1996-12-19 Molten Metal Technology, Inc. Apparatus and method for reducing volume of radioactive waste
US5963863A (en) * 1995-12-01 1999-10-05 Telefonaktiebolaget L M Ericsson Routing system for automatically routing a call to a multi-mode transceiver in a wireless network
US5936863A (en) * 1998-01-28 1999-08-10 Lockheed Martin Idaho Technologies Company Optimal segmentation and packaging process
JP2000044008A (ja) * 1998-07-31 2000-02-15 Yashiki Kankyo Hozen:Kk 廃蛍光管収集処理管理システム
JP2001141887A (ja) * 1999-11-10 2001-05-25 Toshiba Corp 原子力施設解体廃棄物の管理方法
JP5079374B2 (ja) * 2007-04-12 2012-11-21 日本原子力発電株式会社 放射性廃棄物保管兼処分容器
KR100880823B1 (ko) * 2008-10-24 2009-02-02 주식회사 소명특수건업 방사성 폐기물 고형화 처리방법 및 장치
JP2014185919A (ja) * 2013-03-22 2014-10-02 Toshiba Corp 放射性廃棄物の処理方法及び処分容器
JP6297929B2 (ja) * 2014-06-04 2018-03-20 日立Ｇｅニュークリア・エナジー株式会社 放射性廃棄物収納計画支援システム

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59126297A (ja) * 1983-01-06 1984-07-20 株式会社日立製作所 不燃性雑固体廃棄物の処理方法
JPS6289000A (ja) * 1985-10-16 1987-04-23 日本碍子株式会社 放射性廃棄物の充填処理方法
JP2002207098A (ja) * 2001-01-11 2002-07-26 Toshiba Corp 放射性固体廃棄物処理方法
JP2015087300A (ja) * 2013-10-31 2015-05-07 日立Ｇｅニュークリア・エナジー株式会社 プラント解体計画支援装置及びプラント解体計画支援方法

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
See also references of EP3300083A4 *

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