Methods for disposing of waste from a designated area or industrial waste contaminated with radioactive materials.

Abstract

Efficiently recover recyclable resources from waste within the designated area or from industrial waste contaminated with radioactive materials. [Solution] A method for processing waste from a designated area or industrial waste contaminated with radioactive materials, comprising: (A) a step of conducting dose tests on waste from a designated area when it is brought into a processing facility; (B) a step of transporting waste from a designated area to a designated workroom according to its type; (C) a step of performing at least one type of processing selected from the group consisting of crushing, sorting and decontamination on the waste from a designated area to obtain processed material; (D) a step of conducting dose tests on the processed material; (E) a step of collecting processed material that is below the standard value as a result of the dose test; (F) a step of loading the collected waste onto a transport vehicle; (G) a step of conducting dose tests on the waste loaded onto the transport vehicle and the transport vehicle before transporting the waste after the collection step; and (H) a step of removing and collecting dust generated at each step of the processing facility.

Description

Technical Field

[0001] The present invention relates to a method for treating industrial waste contaminated by waste or radioactive substances within a countermeasure area.

Background Art

[0002] Waste within the countermeasure area means waste within the contaminated waste countermeasure area (when the waste is carried out of the contaminated waste countermeasure area, it includes the carried-out waste. Also, except as specified by the Ordinance of the Ministry of the Environment.). (See Article 13, Paragraph 1 of the Special Measures Law Concerning Measures against Environmental Pollution Caused by Radioactive Substances Released due to the Accident at Nuclear Power Plants Associated with the Great East Japan Earthquake that Occurred on March 11, 2011 (Law No. 110 of August 30, 2011)).

[0003] Waste within the countermeasure area may contain radioactive substances at high concentrations and is subjected to treatment such as decontamination. For example, Patent Document 1 discloses a method for separating waste with a low radiation dose from radioactive waste.

Prior Art Documents

Patent Documents

[0004]

Patent Document 1

Summary of the Invention

Problems to be Solved by the Invention

[0005] By the way, industrial waste contaminated by waste or radioactive substances within the countermeasure area contains metal raw materials such as copper and iron, and it is required to recycle these as safe resources.

[0006] Therefore, an object of the present invention is to provide a technique for efficiently recovering recycled resources from industrial waste contaminated by waste or radioactive substances within the countermeasure area.

Means for Solving the Problems

[0007] A first aspect of the present invention is: A method for processing waste from a designated area or industrial waste contaminated with radioactive materials, (A) A process of conducting dose tests on waste from the aforementioned designated area or industrial waste contaminated with radioactive materials when transporting it to the processing facility. (B) A process of transporting waste from within the designated area or industrial waste contaminated with radioactive materials into designated work rooms according to type. (C) A process of obtaining a processed material by performing at least one treatment selected from the group consisting of crushing, sorting and decontamination on the waste from the aforementioned area of ​​control or industrial waste contaminated with radioactive material that has been brought in. (D) A step of performing a dose test on the processed material, (E) A step of recovering the processed material for which the results of the dose test are below the standard value, (F) A step of loading the recovered processed material onto the transport vehicle, (G) A step of performing dose inspections on the processed material loaded onto the transport vehicle and the transport vehicle before transporting the processed material after the recovery process, (H) A process for removing and recovering dust generated at each stage of the processing facility. This is a method for processing waste from a designated area or industrial waste contaminated with radioactive materials, including [specific materials mentioned].

[0008] A second aspect of the present invention is, in the first aspect, The reference values ​​for the aforementioned dose test are: In dose tests conducted after the process of obtaining the aforementioned processed material, if the processed material is not organic sludge or roof tiles / bricks, the surface dose rate is 0.23 [μSv / h] or less; if the processed material is organic sludge, the surface dose rate is 0.50 [μSv / h] or less; and if the processed material is roof tiles / bricks, the radioactivity concentration is 8000 [Bq / kg] or less. In dose tests conducted before the aforementioned waste is transported, if the cargo consists of materials other than organic sludge and roof tiles / bricks, the surface dose rate is 0.23 [μSv / h] or less; if the cargo consists of organic sludge, the surface dose rate is 0.50 [μSv / h] or less; if the cargo consists of roof tiles / bricks, the radioactivity concentration is 8000 [Bq / kg] or less; and if the cargo consists of roof tiles / bricks, the surface contamination density around the vehicle's tires and wheel wells is 40 [Bq / cm³]. 2 When the transport vehicle is unloaded, the surface contamination density around the cargo bed, vehicle tires, and wheel wells is 40 [Bq / cm³] or less, and when the transport vehicle is unloaded, the surface contamination density around the cargo bed, vehicle tires, and wheel wells is 40 [Bq / cm³]. 2 The following applies: The dose measurement can be performed using a known measuring instrument, or it may be performed by an automated robot. For example, when a dose measurement is performed using a known GM survey meter, the number of radiation doses measured per minute (cpm) can be obtained as the measurement value. By performing calibration under appropriate conditions, the measurement value will be less than or equal to a predetermined value, thus achieving a reading of 40 Bq / cm². 2 The following may be considered equivalent: The conversion between the measured value from the measuring instrument and the surface contamination density is made considering the effective area of ​​the detection window of the measuring instrument, the dose efficiency, and the measurement efficiency of each individual instrument.

[0009] A third aspect of the present invention is, in the first or second aspect, The processing facility is maintained and controlled to be under negative pressure relative to the outside of the facility.

[0010] A fourth aspect of the present invention is, in any one of the first to third aspects, The aforementioned waste within the designated area or industrial waste contaminated with radioactive materials includes at least one item selected from concrete, asphalt rubble, waste stone, metals, roof tiles / bricks, glass, rubble mixtures, refrigerators, washing machines, air conditioners, cathode ray tube televisions, gas cylinders, lighters / aerosol cans / cassette gas canisters, pesticides / chemicals, infectious waste, organic sludge, waste acids / waste alkalis, electrical equipment containing low concentrations of PCBs, liquid crystal panels, mixed metal scrap including waste plastics, heavy machinery / agricultural machinery / motorcycles, automobiles, unidentified waste oil, waste fire extinguishers, waste lead batteries, fluorescent lamps, and batteries. In addition, in this specification, the "tiles and bricks" refers to tiles, bricks, and mixtures thereof, and the "mixed metal scraps such as waste plastics" refers to metal scraps mixed with various waste plastics.

[0011] The fifth aspect of the present invention is any one of the first to fourth aspects, When carrying in to the (A) treatment facility, an automated robot performs a dose inspection of industrial waste contaminated by waste or radioactive substances within the countermeasure area, a dose inspection of the (D) processed material, and a dose inspection of the processed material loaded on the (G) transport vehicle and the transport vehicle.

[0012] The sixth aspect of the present invention is any one of the first to fifth aspects, For the crushing, one or both of an impact crusher and a twin-shaft crusher are used.

[0013] The seventh aspect of the present invention is any one of the first to sixth aspects, For the sorting, at least one sorting method selected from magnetic separation, specific gravity separation, air separation, electrostatic separation, eddy current separation, manual sorting, and color difference sorting is used.

[0014] The eighth aspect of the present invention is any one of the first to seventh aspects, The spatial dose is monitored inside and outside the treatment facility.

[0015] The ninth aspect of the present invention is any one of the first to eighth aspects, The treatment facility has a double shutter structure for the entrance gate before loading and the exit gate before unloading, and one of the two shutters in each case is in a closed state.

Advantages of the Invention

[0016] According to the present invention, renewable resources can be efficiently recovered from industrial waste contaminated by waste or radioactive substances within the countermeasure area.

Brief Description of the Drawings

[0017] [Figure 1]Figure 1 is a flowchart showing an example of a method for treating waste within a designated area or industrial waste contaminated with radioactive materials, according to a first embodiment of the present invention. [Figure 2] Figure 2 is a schematic top view showing the general layout of the processing facility. [Modes for carrying out the invention]

[0018] <One Hundred Ideas> One embodiment of the present invention will be described below with reference to the drawings. Figure 1 is a flowchart showing an example of a method for treating waste from a designated area or industrial waste contaminated with radioactive materials according to this embodiment. Figure 2 is a schematic top view showing the outline of a treatment facility. The present invention is not limited to these examples, but is shown in the claims, and all modifications within the meaning and scope of the claims are intended to be included.

[0019] In this embodiment, the target of treatment is waste from within the designated area or industrial waste contaminated with radioactive materials. The waste from within the designated area or industrial waste contaminated with radioactive materials is stored, for example, in a temporary storage site within the contaminated waste control area, and is introduced from the temporary storage site to the treatment facility for treatment. A temporary storage site refers to a place where waste from within the designated area is separated by type and temporarily stored.

[0020] Industrial waste contaminated with radioactive materials or waste within the designated area (hereinafter also simply referred to as "waste") includes, for example, at least one item selected from concrete, asphalt rubble, waste stone, metals, roof tiles and bricks, glass, rubble mixtures, refrigerators, washing machines, air conditioners, cathode ray tube televisions, gas cylinders, lighters, spray cans and cassette gas canisters, pesticides and chemicals, infectious waste, organic sludge, waste acids and alkalis, electrical equipment containing low concentrations of PCBs, liquid crystal panels, mixed metal scrap including waste plastics, heavy machinery, agricultural machinery and motorcycles, automobiles, unidentified waste oil, waste fire extinguishers, waste lead batteries, fluorescent lamps and batteries.

[0021] The method for processing waste from a designated area or industrial waste contaminated with radioactive materials according to this embodiment includes, for example, a first dose inspection step S101, a receiving step S102, a crushing / sorting / decontamination step S103, a dust separation step S104, a second dose inspection step S105, a sorting and recovery step S106, a loading step S107, and a third dose inspection step S108, as shown in Figure 1. The general configuration of the processing facility and the method for processing waste from a designated area or industrial waste contaminated with radioactive materials at the processing facility will be described in detail below.

[0022] (1) Processing facilities The processing facility 1 comprises a processing unit 10 having multiple work rooms 11 for processing waste 50 according to type, a receiving unit 20 for bringing waste 50 into the processing unit 10, and a discharge unit 30 for discharging processed material 60 from the processing unit 10.

[0023] The loading area 20 is an entrance for, for example, transport vehicles 40 to enter the processing area 10 within the processing facility 1, and is equipped with an entrance gate 21. Figure 2 shows a case where the loading area 20 has two lanes. For example, one lane may be a dedicated line for transport vehicles 40 that enter loaded with waste 50 and exit empty, and a dose meter may be placed there. The other lane may be a dedicated line for transport vehicles 40 that enter empty and exit loaded with processed materials 60, and a dose meter may not be placed there.

[0024] The unloading section 30 is an exit for, for example, a transport vehicle 40 to leave the processing section 10 within the processing facility 1, and is equipped with an exit gate 31. In Figure 2, the unloading section 30 has one lane and may be used as a line for transport vehicles 40, either empty or loaded with processing material 60.

[0025] In Figure 2, the loading section 20 and the unloading section 30 have a double shutter structure that opens and closes the gates so that when one gate is opened, the other gate is closed. This allows the processing section 10 inside the processing facility 1 to be isolated from the outside air when transport vehicles 40 enter and exit.

[0026] The loading area 20 and the unloading area 30 are equipped with dose meters (not shown) for measuring the radiation levels of the cargo on the transport vehicles 40. If multiple lanes are provided in each of the loading area 20 and the unloading area 30, dose meters are provided so that the radiation levels of the cargo can be inspected during entry and exit. However, in the loading area 20, dose meters may be provided in at least one of the multiple lanes. Known measuring instruments such as GM survey meters and gamma-ray scintillation survey meters can be used as dose meters. Dose inspection may be performed by an automated robot.

[0027] Furthermore, in order to manage the loading and unloading of waste 50, a weight measuring device (not shown) may be installed to measure the weight of transport vehicles 40 entering and leaving the processing unit 10 within the processing facility 1. For example, it is preferable to measure the load weight of the transport vehicles 40 and calculate the weight of the waste 50 brought in and the weight of the processed materials 60 removed. This ensures reliable waste management.

[0028] The processing unit 10 has multiple workrooms 11 for processing waste 50 according to type. The processing unit 10 is provided with pathways through which transport vehicles 40 can pass, and multiple workrooms 11 are provided along these pathways. Since the crushing, sorting, and decontamination methods differ depending on the type of waste 50, multiple workrooms 11 are provided according to the processing method. For example, Figure 2 shows a case where the processing unit 10 has four workrooms 11 for processing metals, bulky waste, concrete, and solar panels, respectively. Figure 2 illustrates the case where there are four workrooms 11, but the number is not particularly limited.

[0029] Each work chamber 11 is equipped with a processing device 12 for crushing, sorting, and decontamination, depending on the processing method. Conventional known devices can be used as these processing devices 12. As a crushing device, at least one of an impact crusher and a twin-shaft crusher can be used. As an impact crusher, for example, a hammer mill or jaw crusher can be used. As a sorting device, for example, at least one device selected from a magnetic separator, gravity separator, air separator, electrostatic separator, eddy current separator, manual separator and color difference separator can be used. As a decontamination device, for example, a laser decontamination device can be used. In addition, each work chamber 11 may be appropriately combined with the crushing device, sorting device and decontamination device depending on the type of waste 50 to be processed.

[0030] The processing unit 10, the loading unit 20, and the unloading unit 30 are preferably under negative pressure relative to the outside of the processing facility 1 so that the waste 50 does not scatter from the processing facility 1 to the outside. Negative pressure can be achieved by lowering the atmospheric pressure inside the processing facility 1 to atmospheric pressure, and preferably the pressure difference between the internal pressure and external pressure inside the processing facility 1 is -20 Pa or more and less than 0 Pa.

[0031] From the viewpoint of creating a negative pressure environment in the processing unit 10, it is preferable to provide a ventilation device 13. The ventilation device 13 can discharge the air from the processing unit 10 to the outside, creating a negative pressure environment in the processing unit 10. Furthermore, from the viewpoint of suppressing the scattering of waste 50 to the outside, it is preferable to provide a filter in the ventilation device 13. This allows for the capture of extremely fine particles from the waste 50.

[0032] Furthermore, in processing facility 1, radiation dose monitors (not shown) may be installed both inside and outside the facility to measure the radiation dose in the internal space and the external space outside it. This allows for monitoring the dispersion of radioactive materials originating from the waste and ensuring safety.

[0033] (2) Method of disposing of waste within the area under control Next, we will explain how to process waste 50 at the aforementioned processing facility 1. Here, we will explain the process using waste from within the designated area as an example.

[0034] (First dose inspection process S101) The first dose inspection process S101 is a process for measuring the dose of waste 50 being transported from a temporary storage site within the contaminated waste management area to the processing facility 1. At the temporary storage site, the waste 50 is loaded onto transport vehicles 40 according to its type. The transport vehicles 40 enter the loading area 20 of the processing facility 1. At this time, a dose meter is used to perform a dose inspection on the waste 50. For example, the dose of the waste 50 loaded onto the transport vehicles 40 is measured. After confirming the dose, the transport vehicles 40 are introduced into the processing area 10 and the waste 50 is transported in.

[0035] Furthermore, in the first dose inspection process S101, it is advisable to measure the weight of the waste 50 along with the dose inspection.

[0036] (Carry-in process S102) The loading process S102 is the process of loading the waste 50 from the loading section 20 to the workroom 11 of the processing section 10. Here, the transport vehicle 40 loaded with the waste 50 is moved to the corresponding workroom 11 according to the type of waste 50, and the waste 50 is loaded into the workroom 11.

[0037] (Crushing / sorting / decontamination process S103) The crushing / sorting / decontamination process S103 is a process in which at least one of the operations of crushing, sorting, and decontamination is performed on the waste 50 brought in in the workroom 11. Here, for example, by crushing the waste 50, it is crushed to a predetermined particle size according to the constituent materials, and crushed material is obtained. In addition, by sorting the waste 50 as is, or by sorting the crushed material, metal components such as iron, aluminum, and copper are separated from civil engineering materials such as concrete. Furthermore, by decontaminating the waste 50 as is, or by decontaminating the crushed material and sorted material, the radiation dose is reduced. Through these processes, the waste 50 is sorted according to the differences in constituent components and radiation dose, and processed material 60 is obtained in which the radiation dose of the waste 50 is below the standard value.

[0038] For example, if waste 50 consists of metals such as iron, copper, and aluminum, it is advisable to crush the metals and then separate them by type using methods such as magnetic separation or eddy current separation. Also, if waste 50 consists of bulky waste such as refrigerators, washing machines, and air conditioners, it is advisable to use a twin-shaft shredder to shear and crush the bulky waste, resulting in a mixed crushed material containing metals and plastics, which can then be separated using methods such as magnetic separation, eddy current separation, or wind separation. Furthermore, if waste 50 consists of reinforced concrete, it is advisable to crush the large chunks of concrete with a jaw crusher and then separate the crushed material into concrete and rebar using a sieve or magnetic separator. Finally, if waste 50 consists of solar panels, it is advisable to remove the frames and then separate the glass from the rest of the material using a glass stripper.

[0039] In the crushing / sorting / decontamination process S103, it is preferable to crush the waste 50 to a predetermined size according to its type. For example, concrete and asphalt rubble are best crushed to 100 mm or less, and waste stone, which has a simple shape and is easy to sort and test, can be crushed to a relatively large size, preferably 300 mm or less. On the other hand, metals and bulky waste (such as refrigerators and washing machines) have a complex shape and are difficult to sort and test, so it is preferable to crush them to a small size, preferably 100 mm or less. Furthermore, sorting can be carried out using known methods such as specific gravity separation, magnetic separation, eddy current separation, and electrostatic separation, depending on the type of waste. For decontamination, methods such as blasting, polishing, and laser decontamination can be used as appropriate, from the viewpoint of processing costs and decontamination efficiency.

[0040] (Dust separation process S104) A dust separation process S104 can be provided. The dust separation process S104 is a process for separating the dust generated in each process of the processing facility 1. Fine dust may be generated in the processing equipment 12 due to the processing of waste 50. It is advisable to collect and recover the dust by creating a negative pressure state near the dust generation site. For example, an exhaust device with a dust collection filter can be installed at any location near the processing equipment 12, and the dust collected by the dust collection filter can be recovered and separated from the dust-containing air. Furthermore, for safety reasons in the work environment, it is advisable to spray water on the dust generation site to suppress excessive dust generation.

[0041] (Second dose inspection process S105) The second dose inspection process S105 is a process in which dose inspections are performed on the processed material 60 after the crushing / sorting / decontamination process S103. Specifically, in each workroom 11, dose inspections are performed using a dose measuring instrument on the processed material 60, which has undergone at least one operation of crushing, sorting, and decontamination on the waste 50.

[0042] The radiation dose of the processed material 60 will be determined by setting standard values ​​according to the type of processed material 60. The standard values ​​should be set as follows, depending on whether the processed material 60 originates from roof tiles / bricks, organic sludge, or something else. For example, if the processed material 60 originates from roof tiles / bricks among the waste 50, it will be classified as low-concentration material if the radioactivity concentration is 8000 [Bq / kg] or less, and as high-concentration material if the radioactivity concentration exceeds 8000 [Bq / kg]. Also, for example, if the processed material 60 originates from organic sludge among the waste 50, it will be classified as low-dose material if the surface dose rate is 0.50 [μSv / h] or less, and as high-dose material if the surface dose rate exceeds 0.50 [μSv / h]. For example, if the processed material 60 originates from waste 50 other than roof tiles, bricks, and organic sludge, it will be classified as low-dose material if the surface dose rate is 0.23 [μSv / h] or less, and as high-dose material if the surface dose rate exceeds 0.23 [μSv / h].

[0043] (Sorting and recovery process S106) The sorting and recovery process S106 is a process for sorting and recovering processed materials 60 whose dose is below the standard value. Here, low-dose processed materials 60 whose dose is below the standard value in the second dose inspection process S105 described above are sorted and recovered. These low-dose processed materials 60 can be reused as recycled resources. If the processed materials 60 contain a large amount of metals such as copper and iron, they can be recovered and used as recycled resources for metal raw materials.

[0044] (Loading process S107) The loading process S107 is the process of loading the processed materials 60 sorted in each workroom 11 onto the transport vehicles 40. Since the processed materials 60 are sorted according to type, it is preferable to load each type of sorted processed material 60 into separate transport vehicles 40.

[0045] (Third dose inspection process S108) The third dose inspection step S108 is a step in which the surface dose rate of the processed material 60 to be loaded and the surface contamination density of the loading bed, tires, and surrounding areas of the wheel wells (hereinafter referred to as the tire area) of the transport vehicle 40 are measured before the processed material 60 is transported out of the processing facility 1. Here, at the loading section 30 of the processing facility 1, dose inspections are performed on the processed material 60 and the surrounding areas of the tires of the transport vehicle 40 that is loading the processed material 60 using a dose measuring device.

[0046] If the radiation doses of the loaded material 60 and the transport vehicle 40 are both below the standard value, the material 60 can be transported outside the treatment facility 1 by the transport vehicle 40. Specifically, if the material 60 to be loaded is derived from something other than organic sludge and roof tiles / bricks, the surface dose rate of the material 60 must be 0.23 [μSv / h] or less, and the surface contamination density around the transport vehicle 40 and its tires must be 40 [Bq / cm³]. 2 If the following conditions are met, the material may be transported. Furthermore, if the processed material 60 to be loaded is derived from organic sludge, the surface dose rate of the processed material 60 must be 0.50 [μSv / h] or less, and the surface contamination density around the transport vehicle 40 and its tires must be 40 [Bq / cm³]. 2If the following conditions are met, the materials may be transported. Furthermore, if the processed materials 60 to be loaded are derived from roof tiles or bricks, the radioactivity concentration of the processed materials 60 must be 8000 [Bq / kg] or less, and the surface contamination density around the tires of the transport vehicle 40 must be 40 [Bq / cm³]. 2 Items below the specified limit can be transported.

[0047] As a result, waste 50 can be processed at processing facility 1, and processed material 60 with a radiation level below the standard value can be efficiently recovered as a recyclable resource.

[0048] Furthermore, when performing the first dose inspection process S101 to the third dose inspection process S108 described above at processing facility 1, it is advisable to monitor the ambient dose rates both inside and outside processing facility 1. This allows for confirmation of the dispersion of radioactive materials to the outside and the safety inside processing facility 1.

[0049] <Other embodiments of the present invention> Although embodiments of the present invention have been specifically described above, the present invention is not limited to the embodiments described above, and various modifications are possible without departing from the spirit of the invention.

[0050] In the above-described embodiment, a case was explained in which waste within the designated area with radiation levels below the standard value is sorted and collected as recyclable resources. However, the present invention is not limited to this. For example, if components with high radiation levels are identified in waste 50, further decontamination treatment may be performed. Components that cannot be completely decontaminated and whose radiation levels cannot be reduced may be collected separately.

[0051] Furthermore, in the above-described embodiment, the case in which the transport vehicle 40 is loaded with processed material 60 (waste with a dose below the standard value) in the third dose inspection step S108 was explained, but the present invention is not limited to this. For example, the transport vehicle 40 may not be loaded with processed material 60, and there may be no cargo. In this case, a dose inspection may be performed on the transport vehicle 40 without cargo to determine whether the dose meets the standard value. Specifically, the surface contamination density around the cargo bed and tires of the transport vehicle 40 is 40 [Bq / cm²]. 2If the level is below 40 [Bq / cm³], the vehicle may be removed. In other words, for the transport vehicle 40, regardless of whether it is loaded or not, the surface contamination density around the cargo bed and tires must be 40 [Bq / cm³]. 2 Verify that the following conditions apply.

[0052] Furthermore, in the above-described embodiment, the case was explained in which a transport vehicle 40 loads waste 50 and brings it into the processing facility 1, and then loads processed material 60 onto the transport vehicle 40 and transports it out of the processing facility 1. However, in the processing method of the present invention, the transport vehicles that bring in and transport out are separate. For example, the transport vehicle 40 may enter without loading waste 50 and leave with processed material 60 loaded, or it may enter with waste 50 loaded, transport the waste 50 into the work room 11, and then leave without loading processed material 60.

[0053] The above-described embodiment explains the process of processing waste within a designated area, but the present invention is not limited thereto. For example, industrial waste contaminated with radioactive materials may also be processed. When processing this industrial waste, the process can be carried out in the same manner as described above, except that the standard values ​​at each dose stage are changed to different standards than those used for waste within a designated area. Specifically, the standard values ​​for the treated material in the second dose inspection step S105, in which dose inspections are performed on the industrial waste treated material 60, and the third dose inspection step S108, in which dose inspections are performed before the industrial waste treated material 60 is transported out of the treatment facility 1, should be set to (1) to (3) below. (1) If the processed material (derived from industrial waste) is ultimately disposed of in a landfill, the radioactivity concentration of the processed material must be 8000 Bq / kg or less. (2) When the processed material (derived from industrial waste) is recycled or otherwise reused without restrictions, the radioactivity concentration of the processed material must be 100 Bq / kg or less. (3) When the treated material (derived from industrial waste) is used in outdoor public works such as roads and rivers in the Hamadori and Nakadori regions of Fukushima Prefecture, the radioactivity concentration of the treated material must be 100 Bq / kg or less or the surface dose rate must be 0.23 μSv / h or less. [Explanation of Symbols]

[0054] 1. Processing facility 10 Processing Unit 11. Workshop 12 Processing Unit 13 Ventilation system 20 Loading area 21 Entrance Gate 30 Loading section 31 Exit Gate 40 Transport Vehicles 50. Waste from within the designated area or industrial waste contaminated with radioactive materials. 60. Processed materials (waste with radiation levels below the standard)

Claims

1. A method for processing waste from a designated area or industrial waste contaminated with radioactive materials, (A) A process of conducting dose tests on waste from the aforementioned designated area or industrial waste contaminated with radioactive materials when transporting it to the processing facility. (B) A process of transporting waste from within the designated area or industrial waste contaminated with radioactive materials into designated work rooms according to type. (C) A process of obtaining a processed material by performing at least one treatment selected from the group consisting of crushing, sorting and decontamination on the waste from the area of ​​action that has been brought in or industrial waste contaminated with radioactive material. (D) A step of performing a dose test on the processed material, (E) A step of recovering the processed material that is below the standard value as a result of the dose test, (F) A step of loading the recovered processed material onto the transport vehicle, (G) A step of performing dose inspections of the processed material loaded onto the transport vehicle and the transport vehicle before transporting the processed material after the recovery process, (H) A process for removing and recovering dust generated in each process of the processing facility, A method for disposing of waste from a designated area or industrial waste contaminated with radioactive materials, including [specific examples of waste].

2. The reference values ​​for the aforementioned dose test are: In dose tests conducted after the process of obtaining the aforementioned processed material, if the processed material is not organic sludge or roof tiles / bricks, the surface dose rate is 0.23 [μSv / h] or less; if the processed material is organic sludge, the surface dose rate is 0.50 [μSv / h] or less; and if the processed material is roof tiles / bricks, the radioactivity concentration is 8000 [Bq / kg] or less. In dose tests conducted before the aforementioned waste is transported, if the cargo consists of materials other than organic sludge and roof tiles / bricks, the surface dose rate is 0.23 [μSv / h] or less; if the cargo consists of organic sludge, the surface dose rate is 0.50 [μSv / h] or less; if the cargo consists of roof tiles / bricks, the radioactivity concentration is 8000 [Bq / kg] or less; and the surface contamination density around the vehicle's tires and wheel wells is 40 [Bq / cm³]. ２ When the transport vehicle is unloaded, the surface contamination density around the cargo bed, vehicle tires, and wheel wells is 40 [Bq / cm³]. ２ The following is true: A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

3. The processing facility is maintained and controlled to be under negative pressure relative to the outside of the facility. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

4. The aforementioned waste within the designated area or industrial waste contaminated with radioactive materials includes at least one item selected from concrete, asphalt rubble, waste stone, metals, roof tiles / bricks, glass, rubble mixtures, refrigerators, washing machines, air conditioners, cathode ray tube televisions, gas cylinders, lighters / aerosol cans / cassette gas canisters, pesticides / chemicals, infectious waste, organic sludge, waste acids / waste alkalis, electrical equipment containing low concentrations of PCBs, liquid crystal panels, mixed metal scrap including waste plastics, heavy machinery / agricultural machinery / motorcycles, automobiles, unidentified waste oil, waste fire extinguishers, waste lead batteries, fluorescent lamps, and batteries. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

5. The automated robot performs the following actions upon delivery to the processing facility: (A) dose testing of waste from the designated area or industrial waste contaminated with radioactive materials; (D) dose testing of the processed materials; and (G) dose testing of the processed materials loaded onto the transport vehicle and the transport vehicle itself. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

6. The crushing is performed using either an impact crusher or a twin-shaft crusher, or both. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

7. The sorting method used is at least one sorting method selected from magnetic sorting, specific gravity sorting, wind sorting, electrostatic sorting, eddy current sorting, manual sorting, and color difference sorting. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

8. The ambient dose rate is monitored both inside and outside the aforementioned processing facility. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

9. The aforementioned processing facility has a double-shutter structure at the entrance gate before loading and the exit gate before loading, with one of the double shutters in each case being closed. A method for treating waste within a designated area or industrial waste contaminated with radioactive material, as described in claim 1.

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