JP2006300582A - Waste management system - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To obtain a waste management system capable of integrally controlling waste as a whole facility treating waste. <P>SOLUTION: The system comprises measurement controllers 16a to 16c for operating facilities 11a to 11c treating waste 12a to 12c, waste data acquisition devices 14a to 14c acquiring waste data 13a to13c generated from each facility, a data preserver 18 electrically collecting and preserving data obtained from the measurement controller and the waste data acquisition devices, a waste control program controlling the quality data of solid manufactured from waste to be disposed and a terminal device for controlling and processing based on the data preserved in the data preserver 18 and the waste control program. <P>COPYRIGHT: (C)2007,JPO&INPIT

Description

  The present invention relates to a waste management system that manages waste in a nuclear fuel reprocessing factory or a product manufacturing factory.

  For example, wastes from nuclear fuel reprocessing plants, especially radioactive wastes, are individually managed for each type of waste generated by each facility (combustible, non-combustible, etc.), amount generated, and radioactive concentration. ing. This is because it is required by law to keep a record of the type, amount generated, radioactivity concentration, etc. each time the waste is disposed of.

  To dispose of radioactive waste in Japan, it is considered to be buried underground and has already been used as a disposal method for waste generated from nuclear power plants. There are three important requirements for safety, cost and cost reduction.

  Requirement 1 is volume reduction of waste. Each time radioactive waste is disposed of, disposal costs, taxes, and post-disposal management costs are incurred, which account for the majority of disposal costs. In order to reduce such disposal costs, it is necessary to reduce the volume of waste and reduce the amount of underground disposal.

  Requirement 2 is mineralization / immobilization. If waste contains organic matter, microbial degradation may occur when it is disposed of in the ground. In addition, if water enters the wastewater due to rainwater or groundwater, the radionuclide contained in the waste ionizes and flows out into the soil together with moisture, which may cause radiation exposure. In order to prevent this, it is necessary to mineralize the waste by incineration to prevent microbial decomposition and to fix (stabilize) it so that it can be confined to suppress the ion exchange reaction.

  Requirement 3 is clearance. There are various waste disposal methods and disposal levels, but there are a series of provisions for radioactivity and immobilization methods for each disposal method. For example, in the method of landfill disposal on the surface of several meters (shallow disposal method), βγ amount is within 740GBq / t (subject to change in the future due to legal development), and total uranium amount is within 0.1g / t (subsequent change due to legal development) ), Etc. (may be added or deleted in the future due to legal development).

  In other words, in the case of waste that contains more radioactivity than this, another disposal method such as disposal in a pit several tens of meters underground (pit disposal method) must be used, and the disposal cost will vary greatly. . In the case of high-level wastes such as vitrified bodies, there is a rule to wind an overpack around the canister that encloses the vitrified bodies, and the cost of manufacturing the solidified bodies becomes expensive, so the overall disposal cost is further increased. To rise. In addition, the disposal method is also under investigation as a deep underground disposal method, which is buried several hundred meters to 1 kilometer underground, and the disposal cost is the highest compared to other methods.

  Generally, the disposal cost of the solidified product tends to be higher as the radioactive concentration contained in the solidified product is higher. Therefore, even when the same waste is disposed of, there are cases where the volume is reduced by concentrating to a high radioactivity concentration, and there are cases where it is diluted and enclosed in multiple drums, but the disposal costs differ depending on the disposal method. Therefore, which one is cheaper depends on the amount of waste and the amount of radioactivity. Therefore, in order to carry out cheap and safe waste disposal, it is necessary to thoroughly examine each individual in view of such circumstances and determine the waste treatment / disposal method. In order to satisfy these requirements 1, 2, and 3, the actual plant is making the following efforts.

(1) In order to satisfy the requirements 1 and 2, we have introduced facilities for mineralization, volume reduction and fixation by incineration, pressing, melting, etc., depending on the type of waste. In addition, a facility for producing a solidified body for disposal is scheduled to be expanded, whereby a solidified body for transporting waste to a buried disposal site is manufactured.

(2) In order to satisfy Requirement 3, when the waste is generated at each facility of the nuclear fuel reprocessing plant, the generation amount and radioactivity concentration are managed. When these become waste data and processed at a waste disposal facility, the waste (source) contained in the solidified body can be grasped so that the waste can be traced even if it becomes a solidified body. Yes. As a method for performing such waste management, in an actual plant, total management can be performed by a facility computer of a waste treatment facility. In addition, waste generators sort, sort, and measure the amount of radioactivity using paper slips, and have been collected as waste management data by using an independent management tool for each facility.

  For such waste management data, other reprocessing factories use a system in which the waste is enclosed in a vinyl bag, a barcode is attached to the vinyl bag, and the code number is read by a PDA and collected. Some facilities use computerized tools to follow up on the generation, transfer, and processing of goods.

In addition, when transporting radioactive materials by land or sea using transport vehicles or ships, state data indicating the current state of the radioactive materials (current transport position, current temperature of the related materials (ambient temperature also And the like, the pressure applied to the related object, the vibration of the related object, etc.} can be easily grasped and confirmed in one management system (for example, see Patent Document 1).
JP 2002-279035 A

  However, the waste management system in the nuclear fuel reprocessing plant has the following problems because each facility uses an independent waste management tool.

(A) In order to manage the waste as a whole nuclear fuel reprocessing plant, it is necessary to collect and collect information from each facility, but the existing management tools are based on the operation control system of the reprocessing plant. Since it is an independent system, data related to the reprocessing process is manually input. For this reason, it took a lot of time and effort to collect data.

(B) Since the waste data is manually input to the management tool based on the actual operation data, the waste data check function does not exist. For this reason, there is a possibility that the processing / disposal cost management related to the waste processing becomes inaccurate.

(C) The laws and regulations related to the disposal of waste are in the development stage, and it is highly likely that the management items will be changed due to the revision of the laws and regulations, and it was difficult to set the management items and clearance level.

(D) Since the waste processing facility only processes the waste that has entered the waste processing facility, the processing has no planability and it is difficult to make a processing plan. For this reason, it was difficult to control the operation of the waste treatment facility.

(E) Since it is allowed to randomly construct waste treatment lots, if there is waste with abnormal radioactivity in the waste treatment lots, the planned underground disposal cannot be performed. There was an increase in disposal costs. In addition, since the work for constructing the waste treatment lot is performed by a combination of trial and error, it takes a long time for the construction work.

  An object of the present invention is to obtain a waste management system capable of comprehensively managing waste as a whole facility that handles waste.

  The waste management system of the present invention includes a measurement control device that operates equipment of each facility that handles waste, a waste data collection device that collects waste data generated from each facility, the measurement control device, and the disposal A data storage device for electronically collecting and storing data obtained from the material data collection device, a waste management program for managing quality data of solidified bodies produced from waste to be disposed of, and the data storage device And a terminal device for performing a waste management process based on the stored data and the waste management program.

  According to the present invention, since it is possible to automatically register data without manually inputting waste data, it is possible to remarkably reduce the waste data collection work load on the operators of each facility.

  FIG. 1 is a configuration diagram of an example of a waste management system according to an embodiment of the present invention. For example, wastes 12a to 12c are generated in the facilities 11a to 11c of the nuclear fuel reprocessing plant. The waste data 13a to 13c of the wastes 12a to 12c are collected by the waste data collection devices 14a to 14c and input to the respective facility management computers 15a to 15c. Further, process data 17a to 17c of the measurement control devices 16a to 16c that operate the facilities of the respective facilities 11a to 11c are also input to the respective facility management computers 15a to 15c. The waste data 13a to 13c and the process data 17a to 17c input to each facility management computer 15a to 15c are stored in the data storage device 18. On the other hand, the process data 17n of the measurement control device 16n that operates the facilities of the waste treatment facility 11n is also input to the facility computer 15n and stored in the data storage device 18. In the waste disposal facility 11n, a solidified body 19 of waste is generated. The data stored in the data storage device 18 is managed by the waste management server 20 and distributed to the terminal device 21. The waste management server 20 manages a waste management program for managing the quality data of the solidified body 19 produced from the wastes 12a to 12c to be disposed.

  As described above, the waste management system according to the embodiment of the present invention includes facility computers 15a to 15c that collect process data 17a to 17c obtained from the measurement control devices 16a to 16c of the facilities 11a to 11c, The facility computer 15n that collects the process data 17n obtained from the measurement control device 16n of the waste disposal facility 11n, and the waste data 13a to 13w obtained from the facility computers 15a to 15c of the facilities 11a to 11c 13c and process data 17a to 17n, a data storage device 18 for collecting the data and a waste management server 20 are provided.

  In this case, the waste management server 20 has a case where the waste management server 20 exists as shown in FIG. 1 and a case where it is included as software in the data storage device 18 as shown in FIG. possible. FIG. 2 is a configuration diagram of another example of the waste management system according to the embodiment of the present invention, in which the waste management server 20 and the data storage device 18 are integrated. This is the same in any case of FIG.

  The waste management server 20 collects the waste data 13a to 13c from the facility computers 15a to 15c via the data storage device 18 by an electronic method. In addition, the process data 17a to 17n such as device operation and temperature / pressure of each facility 11a to 11n is in the form of a computer tag in which an address area name is arbitrarily defined on a unique address on the computer shared memory by MAP communication. The transmission data is collected and the process data 17a to 17n can be collected in real time. For this reason, by collecting these data, it becomes possible to cover and collect all the process operation data of each of the facilities 11a to 11n.

  As described above, both the process data 17a to 17n and the waste data 13a to 13c can be aggregated via the facility computers 15a to 15n of the facilities 11a to 11n. There is no need to manually input various data, and it is possible to eliminate the enormous amount of time and labor required for data aggregation work. For this reason, the work load and management cost concerning waste management can be remarkably reduced. Further, since the waste data 13a to 13c are aggregated based on the data obtained in real time from the facilities 11a to 11c, it always contributes to collecting accurate data and enabling cost management for waste processing. .

  Here, when measuring and recording the amount of radioactivity of the wastes 12a to 12c, the wastes 12a to 12c generated at the waste generation source before the waste processing are measured and added each time the processing proceeds. There are a method of counting and a method of measuring the solidified body itself after manufacturing the solidified body. The latter is often adopted in power plants and the like, but in the case of a reprocessing plant, the radioactive concentration and composition differ depending on the facilities 11a to 11c that generate the wastes 12a to 12c. By applying the result of measuring ~ 13c in more detail, it is possible to trace back from the produced solidified body 19 to the waste generation source. For this reason, the former method is applied in the embodiment of the present invention.

  In the embodiment of the present invention, since the collected data is stored in the data storage device 18, a check function for the collected data is provided, and it becomes impossible to tamper and forge the collected data. For this reason, it contributes to providing as quality assurance (accuracy of composition data of waste solidified body) data of the waste solidified body 19 to be manufactured. This has the effect of proving that the waste is properly treated for local residents, power companies, government offices, etc., and at the same time proving that the composition of the solidified body is appropriate for the disposal contractor. .

  That is, the waste data 13a to 13c generated in each facility 11a to 11c is waste data at the time of waste generation such as the type of the wastes 12a to 12c and the radioactive concentration, and the waste data collection devices 14a to 14c. It is collected and automatically transmitted to the facility computers 15a to 15n. Therefore, it becomes possible to automatically register data in the facility computers 15a to 15n without manually inputting the waste data 13a to 13c. For this reason, it becomes possible to remarkably reduce the waste data collection work load of the operators of the facilities 11a to 11c. In addition, since the collected data is checked, it is possible to contribute to quality assurance of the solidified waste produced.

  The data storage device 18 that collects data from the facility computers 15a to 15n is not only the waste data 13a to 13c but also various process data 17a such as facility management data and nuclear management data generated by facility operation. Since ~ 17n can be comprehensively aggregated as a whole factory, it can be applied not only to the wastes 12a to 12c but also to the aggregation and management of various data.

  The main application examples are the equipment management system that collects the operating status of the equipment in each facility 11a to 11c and visually provides it to the administrator, the nuclear material management system for grasping the movement of the nuclear material, reagents, Visually provide usage of utilities, etc., reagent management system for predicting reagent replenishment timing and reagent cost, keeping equipment maintenance and inspection records, managing and predicting replacement parts and repair schedules and costs It can be applied to maintenance and inspection management systems.

  Next, waste management items will be described. FIG. 3 is an explanatory diagram for setting the waste management items. A tool for setting waste management items necessary for waste management is achieved by executing a waste management program by the waste management server 20. The setting of the waste management item is performed via the terminal device 21.

The waste management items in the current reprocessing factory are: waste type (combustible, non-combustible, metal, etc.), waste transport container (drum, container, special shielding container, etc.), solidification method (cement solidification, compression) Volume reduction solidification, incineration, etc.), radioactivity concentration (α / βγ concentration), nuclide composition ratio (nuclide such as Cs, Sr, K, Cl, U, Pu), isotope composition ratio ( ⁹⁰ Sr, ¹⁴⁰ mCs, ²³⁵ U, ²³⁸ U, ²⁴¹ Pu, etc.).

  At present, since the laws and regulations related to landfill disposal are being developed, it is expected that among the waste management items, the control items related to nuclides and the clearance level (upper limit values such as radioactivity concentration in landfill disposal) will be changed. The Therefore, by providing a setting tool for waste management items, it is possible to easily reset even if the management items are changed due to legal revisions. As a result, it is possible to reduce the cost of software replacement as a response to legal revisions.

  In FIG. 3, the waste classification is not limited to categorization according to classification such as combustibles and noncombustibles due to the revision of the law. In anticipation of this, the setting tool can arbitrarily set the waste type. For example, a plurality of items are prepared as characteristics, and “add”, “delete”, and “edit” buttons are prepared for each item. This makes it possible to trace what type of waste was originally generated from the buried waste.

  FIG. 4 is an explanatory diagram for setting radioactivity concentration management items, and FIG. 5 is an explanatory diagram for setting nuclides. As shown in FIG. 4, a tool for setting management items necessary for radioactive concentration management is achieved by executing a waste management program by the waste management server 20. The setting of the radioactive concentration management item is performed via the terminal device 21.

  In this setting, it is possible to individually select various nuclides that should be managed and those that do not need to be managed. For example, when an “add” button for the nuclide / isotope composition ratio is pressed, the screen shifts to a screen for selecting from the nuclide list (FIG. 5), and a variety of nuclides to be managed can be selected. In addition, it is possible to set a half-life boundary value and group by the half-life of nuclides. Even if the necessity of management is not individually set for each nuclide, the necessity of nuclide management is determined based on the set half-life. Can be set at once. As a result, if the setting is made to ignore those below a certain half-life, only nuclides having a half-life longer than the set half-life can be managed. Also, the radiation concentration can be set, so that the work load related to the setting work can be significantly reduced.

  To set the nuclide, when the “add” button of the nuclide / isotope composition ratio in FIG. 4 is pressed, for example, the screen shown in FIG. 5 is displayed, and the control nuclide is selected from the element periodic table. The element types are displayed in different colors, for example, by metallic elements, non-metallic elements, fiber metals, rare gases, and the like. In addition, double-clicking on an element displayed in the periodic table of elements sets whether or not to make it a management target, and, for example, a check is placed in the upper right for the element that becomes the management target. In addition, isotopes of nuclides to be managed are displayed in a separate table. As described above, when setting the nuclide, data such as the half-life of the nuclide and the radiation spectrum are registered in advance.

  The setting data set here is an instruction to revise the database of the waste management server 20, notify the facility computers 15a to 15n through the data storage device 18, and change the classification method and criteria to the facilities 11a to 11c. Become. Thereby, it becomes possible to revise the waste management items after the setting in accordance with the change contents according to the setting data. That is, since management items are not arbitrarily set in each facility, it is possible to provide a function of notifying items to be managed as a whole factory and revising the database.

  Further, depending on the facilities 11a to 11c, there may be cases where special waste is generated (glove box accessories, filter cask, shearing blade of a shearing machine, etc.), so that it is possible to set facility-specific waste. It becomes possible.

  Next, the function of predicting the amount of waste and the amount of radioactivity generated from each facility will be described. The waste management program is provided with a function for predicting the amount of generated waste or the amount of radioactivity based on the data of raw materials used in product manufacture, so that the waste treatment facility 11n can be operated systematically.

  Conventionally, in order to predict the amount of waste generated, it was only possible to operate a factory for a certain period of time, and to calculate basic units based on statistical data and simple calculations based on operational results. For this reason, the divergence between the predicted value and the actual value is large, and even if the divergence occurs, it is usually not managed. This made it difficult to predict the amount of waste generated, and also caused the predicted value to not be fully utilized. Therefore, in the embodiment of the present invention, the amount of waste and the amount of radioactivity generated from each facility are predicted.

  First, when predicting the amount of waste generated, a method of calculating the amount of waste generated in that year by a mathematical analysis method based on the number of spent nuclear fuels to be processed and the burnup level in that year is used. For example, as shown in FIG. 6, the Kalman filter method can be cited as an existing regression analysis method. This is an analysis method in which a matrix is applied to find a solution when other different conditions are given based on at least three or more initial conditions given by one or more dimensions. According to this, by setting the amount of waste generated at that time using the number of treated fuel per day as a parameter, or the number of treated fuel per day and the burnup of each of these fuels as parameters, It is possible to analytically calculate the amount of waste generated based on the planned value of the number of fuels to be processed.

  In this method, the first at least three initial conditions must be given in advance. However, since the reprocessing plant is currently in a testing stage and an operation evaluation test is planned to be performed in the future, at least three initial conditions should be set. It can be obtained at the test stage, and it becomes possible to satisfy the necessary conditions by setting the waste data generated at this time.

  Then, as shown in FIG. 6, the waste generation amount (actual value), the waste buffer amount (allowable value−waste generation amount), and the expected waste generation amount are displayed for each facility. In addition, the facility is selected to display the amount of waste treated and the amount of waste generated, and the respective expected lines are also displayed.

  That is, by managing the difference from the actual value for the predicted amount of waste generated, the difference is fed back to the initial condition and contributing to calculating a more accurate value, thereby calculating the amount of waste generated. It is possible to give sufficient conditions necessary for In addition, the amount of abnormal waste generated at the time of an accident can be calculated by comparing the difference between the predicted value and actual value that increases with each operation and the abnormal events such as accidents that can occur at each facility. Therefore, it is possible to flexibly cope with the generation of waste in the event of an emergency.

  As a result, the amount of waste transported to the waste treatment facility 11n can be predicted in advance using the spent fuel to be treated as a parameter. It is possible to plan for shifts. In addition, since a function for effectively utilizing the predicted value and feeding back to the next operation data is provided, it is possible to estimate the cost of future waste production and disposal as an approximation. Further, since it can be applied not only to solid waste but also to liquid waste and gas waste, it is also possible to predict the replacement time of a filter and the amount of material at the time of filter discard.

  Next, as for the radioactivity concentration, each facility 11a to 11c is given based on the burnup data based on the fuel processing plan and the amount of nuclides existing in each facility 11a to 11c is given by the radioactivity concentration distribution ratio based on the ORIGEN database. It is possible to give the composition ratio of nuclides contained in the waste generated in This eliminates the need to individually set the nuclide composition ratio and the amount of nuclide for the waste generated at each facility 11a to 11c. It is possible to automatically set the isotope composition ratio. This is because it will be possible to simulate the transition of the solidified radioactive concentration after the solidified material is buried in the ground in the future, so that it will be possible to manage the attenuation of the radioactive content after being buried. Contribute to.

  As a result, the amount of radioactivity transported to the waste treatment facility 11n can be predicted in advance, and the control of the operation load / operation time of the waste treatment facility 11n and the shift of employees can be planned. It becomes possible. In addition, since a function for effectively utilizing the predicted value and feeding back to the next operation data is provided, it is possible to estimate the cost of future waste production and disposal as an approximation. Moreover, since it can be applied not only to solid waste but also to liquid waste and gas waste, it is possible to predict the replacement time of the filter and the amount of radioactivity at the time of filter disposal.

  As can be seen from the above description, the waste composition collected from each facility 11a to 11c (hereinafter referred to as a source) can be managed to manage the waste composition and the radioactivity concentration for each source. The amount and type of waste data are arranged by the waste processing method, and the sources necessary to manufacture one solidified body are provided to the administrator in combination. Thereby, it becomes possible to indicate a source group necessary for producing a solidified body.

  For example, as a method of giving this mathematically, as shown in FIG. 7, after sorting the source for each waste treatment method, there is a method of performing a merge sort based on the radioactivity concentration or the isotope composition ratio. The merge sort is a computer algorithm that divides a huge amount of data into a plurality of pieces, individually assigns permutations, and then integrates and sorts the whole. For this reason, it generally has a feature that the time required for sorting is shorter than the well-known heap sort. The feature of this embodiment is that this sort function is introduced into waste management, and the waste sources to be processed are sorted to create a combination (processing lot), which is visually provided to the manager and instructed. It is.

  When the upper limit radioactivity concentration required per solidified body is given by the setting data set in Fig. 4, the waste source should be selected so that this set upper limit (clearance) will not be exceeded. Thus, it is possible to automatically calculate a source necessary for manufacturing one solidified body and visually instruct it. In this way, even when a certain source has a very high radioactivity concentration and it is difficult to produce a solidified body as it is, the radioactivity concentration is diluted by mixing other sources having a low radioactivity concentration. As a result, it is possible to select a source necessary for producing a solidified body that does not exceed the upper limit set in FIG. 4, and therefore instruct the processing facility of a combination of sources that can be disposed in the ground. Is possible.

  In addition, waste disposal / disposal costs are automatically calculated and visually presented to the user, so case studies can be conducted when the disposal method is changed according to the disposal level (clearance level). When producing solidified bodies from waste with high capacity, the cost of manufacturing and disposal is simulated by comparing the volume reduced and the disposal level increased with the volume increased and the disposal level lowered. Therefore, it is possible to give a processing lot instruction with a view to the disposal method of the generated waste.

  In the embodiment of the present invention, since such processing lots are automatically generated and provided, the processing lot creation work load is significantly reduced. In addition, the processing lot is a recommended value, and the administrator can mix other sources with the recommended value, so that it is possible to simulate the solidified product specification after manufacture. This makes it possible to plan a waste treatment that is flexible and that complies with the upper limit (clearance) as necessary.

  In addition, since the equipment operation status is obtained as electronic data as described above, it is possible to monitor whether the waste processing facility is processing waste according to the specified processing lot, and the waste processing status It becomes possible to follow up the plan contents together with monitoring. That is, when processing waste generated at each facility at the waste processing facility, it is possible to instruct the waste processing facility in advance about the content of the waste processing, and to manage that the processing is performed as instructed.

  In the above description, the nuclear fuel reprocessing factory has been described. However, the present invention can be applied to waste management in a product manufacturing factory other than the nuclear fuel reprocessing factory. That is, the present invention can be similarly applied to processing from raw materials used in product manufacture to waste.

The block diagram of an example of the waste management system concerning embodiment of this invention. The block diagram of the other example of the waste management system concerning embodiment of this invention. Explanatory drawing about the setting of the waste management item in embodiment of this invention. Explanatory drawing about the setting of the radioactive concentration management item in embodiment of this invention. Explanatory drawing about the setting of the nuclide in embodiment of this invention. Explanatory drawing of the prediction scheme of the waste generation amount in embodiment of this invention. Explanatory drawing of the production | generation scheme of the waste treatment lot in embodiment of this invention.

Explanation of symbols

DESCRIPTION OF SYMBOLS 11 ... Facility, 12 ... Waste, 13 ... Waste data, 14 ... Waste data collection device, 15 ... Facility computer, 16 ... Measurement control device, 17 ... Process data, 18 ... Data storage device, 19 ... Solidified body, 20 ... Waste management server, 21 ... Terminal device

Claims (5)

  A measurement control device that operates equipment of each facility that handles waste, a waste data collection device that collects waste data generated from each facility, and data obtained from the measurement control device and the waste data collection device Data storage device for electronically collecting and storing, waste management program for managing quality data of solidified bodies manufactured from waste to be disposed of, data stored in the data storage device and waste management A waste management system comprising: a terminal device that performs waste management processing based on a program.   2. The waste management program according to claim 1, wherein the waste management program has a function of arbitrarily setting a waste management item via the terminal device and instructing the waste management item as necessary. system.   The waste management system according to claim 1, wherein the waste management program has a function of predicting the amount of generated waste or the amount of radioactivity based on raw material data used in product manufacture.   The waste management program instructs the waste processing facility in advance to handle the waste generated at each facility at the waste processing facility, and manages that it is being processed as instructed. The waste management system according to claim 1, further comprising a function capable of being performed.   The waste management system according to claim 1, wherein the waste management program has a function of automatically calculating waste disposal / disposal costs and visually presenting them to a user.

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