Recycling method of radioactive solid waste

Abstract

The invention discloses a radioactive solid waste recycling method, which belongs to the technical field of radioactive waste treatment, and comprises the following steps: processing and forming radioactive solid waste into a ray source according to shape and size requirements, and measuring the energy and equivalent dose of rays on the surface of the ray source; an irradiation field is built, shielding measures are taken, an irradiation device used for placing an object to be irradiated is installed in the irradiation field, and a ray source is placed in the irradiation field; according to the irradiation purpose, a position meeting preset ray energy and equivalent dose rate is selected in the irradiation device, and the to-be-irradiated object is placed for irradiation; and after the to-be-irradiated object is irradiated to the target absorbed dose, taking out the irradiated object at a single time or in batches. Rays radiated in the radionuclide decay process are effectively utilized, a large amount of radioactive solid waste can be treated and repeatedly utilized, and the method is suitable for treatment of radioactive solid waste generated in reactors such as commercial reactors and research reactors and has important research value and application prospects.

Description

Technical Field

[0001] The present application belongs to the technical field of radioactive waste treatment, and in particular relates to a method for recycling radioactive solid waste. Background Art

[0002] The reactor will produce a certain amount of radioactive solid waste during its service life, and the amount produced after decommissioning is much higher than that during service. According to relevant foreign experience, each nuclear power unit will produce about 7000m3 of radioactive solid waste when it is decommissioned. 3 The disposal of this radioactive waste is a common challenge faced by industries worldwide. Aside from a very small portion of beneficial and high-value nuclides that are recycled, the majority of solid radioactive waste is disposed of in a variety of ways, depending on its radioactivity level, including storage, decay, release, landfill, near-surface, intermediate-depth, and deep geological disposal. Because waste disposal sites are not necessarily located in areas with the highest concentration of nuclear power plants, local governments only bear the responsibility and rarely share in the benefits. This has resulted in decades of difficult and ineffective regional waste disposal.

[0003] Currently, there is a lack of effective methods for utilizing radioactive solid waste. Existing technologies for volume reduction and disposal of radioactive solid waste primarily consider the hazards of radioactivity, employing methods such as volume reduction, increased shielding, and storage, landfill, and geological disposal away from human habitation. This consumes significant manpower, material, and financial resources, while failing to fully utilize the radiation emitted by these wastes. The radiation released by the radionuclides contained in radioactive solid waste during their decay process has significant application value, but simplistic storage, landfill, and geological disposal methods effectively waste radiation resources. Summary of the Invention

[0004] The present application aims to solve the technical problem of the current lack of methods for effectively utilizing radioactive solid waste. To this end, the present application provides a method for recycling radioactive solid waste, which effectively utilizes the rays radiated during the decay of radioactive nuclides, can process and reuse radioactive solid waste in large quantities, and is suitable for the disposal of radioactive solid waste generated in reactors such as commercial reactors and research reactors.

[0005] The present invention provides a method for recycling radioactive solid waste, which includes:

[0006] Process radioactive solid waste into radiation sources according to shape and size requirements, and measure the energy and equivalent dose of radiation on the surface of the radiation source;

[0007] Build an irradiation field and take shielding measures, install irradiation equipment for placing objects to be irradiated in the irradiation field, and place radiation sources in the irradiation field;

[0008] According to the irradiation purpose, select a position in the irradiation device that meets the preset radiation energy and equivalent dose rate, and place the object to be irradiated for irradiation;

[0009] When the object to be irradiated has been irradiated to a target absorbed dose, the irradiated object is obtained and taken out in a single or batch manner.

[0010] In some embodiments, further comprising:

[0011] Before processing radioactive solid waste into radiation sources, the radioactive solid waste shall be classified according to the type of main radionuclides and the radioactivity level;

[0012] When processing radioactive solid waste into radiation sources, they can be processed into various types of radiation sources according to the classification of the radioactive solid waste;

[0013] Before placing the radiation source in the irradiation field, select the radiation source according to the irradiation purpose and the object to be irradiated.

[0014] In some embodiments, radioactive solid waste is classified according to the size of radioactivity, specifically: radioactive solid waste is classified according to the equivalent dose of radiation of <10mSv / h, 10-100mSv / h, 100-500mSv / h, and >500mSv / h.

[0015] In some embodiments, all objects to be irradiated placed in the irradiation device are arranged vertically, in an array, or horizontally, and the objects to be irradiated are relatively stationary or moving relative to the radiation source.

[0016] In some embodiments, the radiation source is a cube, a cylinder, or a sphere; or the radiation source is a cube, a cylinder, or a sphere and is provided with a slot, a hole, or a channel for accommodating an object to be irradiated.

[0017] In some embodiments, the radioactive solid waste is a material capable of generating gamma rays, causing the radiation source to generate gamma rays.

[0018] In some embodiments, the radioactive solid waste includes pure metal materials, and / or alloy materials.

[0019] In some embodiments, the size range of the ray source is [a cm, b*100 m], where a and b are both natural numbers less than or equal to 10.

[0020] In some embodiments, the method further includes periodically measuring the equivalent dose of radiation at different positions in the irradiation device, and removing and disposing of radiation sources that do not meet the expected equivalent dose.

[0021] In some embodiments, not meeting the expected equivalent dose refers to:

[0022] For food irradiation, the equivalent dose of surface gamma rays is less than 5mSv / h;

[0023] For scientific research, the equivalent dose of surface gamma rays is less than 10mSv / h;

[0024] For the irradiation modification of industrial raw materials, the equivalent dose of surface gamma rays is less than 50mSv / h.

[0025] It can be seen from the above technical solution that the beneficial effects of this application are:

[0026] This application processes radioactive solid waste into a radiation source and measures the energy and equivalent dose of the radiation, thereby converting radioactive solid waste into controllable radioactive materials for use as needed. By building an irradiation field and installing an irradiation device, an irradiation environment and conditions under independent protection can be formed. The energy and dose requirements of the radiation are determined based on the irradiation purpose, and then the corresponding position is selected to place the object to be irradiated, achieving targeted dose control. While improving the utilization rate of radioactive waste, the safety of the irradiation process is guaranteed. After irradiation to the target absorbed dose, the irradiation of the object to be irradiated is completed by batch / single material extraction. In this way, this application effectively utilizes the radiation emitted during the decay of radioactive nuclides, can process and reuse radioactive solid waste in large quantities, and is suitable for the disposal of radioactive solid waste generated in reactors such as commercial reactors and research reactors. BRIEF DESCRIPTION OF THE DRAWINGS

[0027] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the following will briefly introduce the drawings required for the description of the embodiments one by one. Obviously, the drawings described below are some embodiments of the present application. For those of ordinary skill in the art, other embodiments and drawings can be obtained based on these drawings without inventive work. Various schematic diagrams according to the embodiments of the present application are shown in the drawings. These drawings are not necessarily drawn to scale. For the purpose of clarity, some details are magnified and some details may be omitted.

[0028] Figure 1 A schematic diagram showing the steps of an embodiment of the method for recycling radioactive solid waste according to the present invention is shown;

[0029] Figure 2 A schematic diagram showing the use of an embodiment of a ray source and an irradiation device according to the present invention is shown;

[0030] Figure 3 A schematic diagram showing the use of an embodiment of a ray source and an irradiation device according to the present invention is shown;

[0031] Figure 4 A schematic diagram showing the use of an embodiment of a ray source and an irradiation device according to the present invention is shown;

[0032] Reference numerals: 1. radiation source; 2. irradiation device; 3. object to be irradiated. DETAILED DESCRIPTION

[0033] The following will be combined with the accompanying drawings corresponding to the specific embodiments of the present application to clearly and completely describe the technical solutions in the embodiments of the present application. The following detailed description of the embodiments of the present application provided in the accompanying drawings is not intended to limit the scope of the present application for protection. The described embodiments are only part of the embodiments of the present application, not all of the embodiments. Based on the embodiments in the present application, various different configurations can be arranged and designed. All other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of this application.

[0034] The present application is described below with reference to specific embodiments and with reference to the accompanying drawings:

[0035] Please refer to Figure 1 , an embodiment of the present application provides a method for recycling radioactive solid waste, which comprises:

[0036] S1. Process the radioactive solid waste into a radiation source 1 according to required shape and size, and measure the energy and equivalent dose of the radiation on the surface of the radiation source 1. The shape and size can be determined based on the irradiation purpose, the object to be irradiated 3, and its scale. The processing process includes: pre-treating the radioactive waste (such as melting) to form a liquid or granular material, then performing metallurgical, extrusion, or high-temperature calcination processes, and finally cutting and polishing the material. When measuring the radiation, ionization chamber methods, semiconductor detectors, etc. can be used to directly detect the energy and equivalent dose, and energy spectrum analysis can be used to determine the type of nuclide and decay characteristics.

[0037] S2. Build an irradiation field and take shielding measures. Install an irradiation device 2 for placing the object 3 to be irradiated in the irradiation field, and place a radiation source 1 in the irradiation field. The irradiation field is built in an irradiation facility, and the irradiation facility is constructed at the ground surface or several tens of meters below the surface. Take shielding measures to ensure that the radiation generated by the radiation source 1 does not leak out. The shielding measures include laying lead bricks, concrete, carbon steel, etc. to establish a shield. The irradiation device 2 needs to be matched with the irradiation field. For example, an irradiation field where the object 3 to be irradiated is placed statically uses a static irradiation device 2, while a relatively moving irradiation field uses an irradiation device 2 that can drive the object 3 to be irradiated to move.

[0038] S3. Based on the irradiation purpose, a location in the irradiation device 2 that meets the preset radiation energy and equivalent dose rate is selected and the object to be irradiated 3 is placed there for irradiation. Irradiation purposes include irradiation breeding of animals, plants, bacteria, viruses, etc. for scientific research, irradiation treatment of food (to improve taste, inhibit germination, delay ripening, extend shelf life, and degrade harmful residues such as antibiotics, pesticides, veterinary drugs, allergens, and biotoxins), and irradiation modification of industrial raw materials. The preset radiation energy and equivalent dose rate are determined based on the radiation dose required for the object to be irradiated 3. Since the distance and position of each location in the irradiation device 2 relative to the radiation source 1 vary, the equivalent dose also varies, so the location can be selected based on the needs.

[0039] S4. After the irradiated object 3 has been irradiated to the target absorbed dose, the irradiated object is obtained and removed individually or in batches. After removal, the irradiated object is subjected to scientific research or analytical testing. When the cumulative absorbed dose of the irradiated object 3 in the irradiation device 2 reaches the target absorbed dose, the object can be removed. Real-time measurement can be performed using existing dose monitoring devices. After removal, the irradiated object is tested according to radiation-related quality standards.

[0040] Currently, there is a lack of effective methods and adapters for the utilization of radioactive solid waste, and existing technologies result in a de facto waste of radiation resources in the treatment of radioactive solid waste. However, the present application, by processing radioactive solid waste into a radiation source 1 and measuring the energy and equivalent dose of the radiation, can convert radioactive solid waste into controllable radioactive materials for use as needed. By constructing an irradiation field and installing an irradiation device 2, an irradiation environment and conditions can be formed under independent protection. The energy and dose requirements of the radiation are determined based on the irradiation purpose, and then the corresponding location is selected to place the irradiated object 3, achieving targeted dose control. This improves the utilization rate of radioactive waste while ensuring the safety of the irradiation process. After irradiation reaches the target absorbed dose, the irradiation of the irradiated object 3 is completed through batch / single material removal. In this way, the present application effectively utilizes the radiation emitted during the decay of radionuclides, can process and reuse radioactive solid waste in large quantities, and is suitable for the disposal of radioactive solid waste generated in reactors such as commercial reactors and research reactors. It has important research value and application prospects in the fields of irradiation breeding, food irradiation treatment, and irradiation modification of industrial raw materials.

[0041] In some embodiments, further comprising:

[0042] S0. Before processing radioactive solid waste into radiation source 1, the radioactive solid waste shall be classified according to the type and radioactivity of the main radionuclides, such as martensitic steel, austenitic steel, carbon steel, 316L stainless steel, etc. 55 Fe, 59Fe is classified as Class 1 (steel); processing methods include melting, casting, compression, cutting, etc.

[0043] S11. When processing radioactive solid waste into radiation sources 1, multiple radiation sources 1 are processed according to the classification of the radioactive solid waste; the processed radiation sources 1 are suitable for different irradiation scenarios and needs, and can be differentiated according to the irradiation purpose and object in the subsequent process.

[0044] S21: Before placing the radiation source 1 in the irradiation field, select the radiation source 1 according to the irradiation purpose and the object to be irradiated 3. This step can be performed before the last step of S2 is completed, or after S1 and before S2.

[0045] In some embodiments, radioactive solid waste is classified according to the level of radioactivity, specifically by the following: radioactive solid waste radiation equivalent dose of less than 10 mSv / h (e.g., 5 mSv / h, 8 mSv / h), 10-100 mSv / h (e.g., 10 mSv / h, 50 mSv / h, 100 mSv / h), 100-500 mSv / h (e.g., 100 mSv / h, 300 mSv / h, 500 mSv / h), and >500 mSv / h (e.g., 505 mSv / h, 700 mSv / h). Objects 3 to be irradiated can be selected based on the equivalent dose, including objects involved in scientific research and production, such as seeds, semi-finished foods, or industrial raw materials.

[0046] Please refer to Figure 2 、 Figure 3 and Figure 4In some embodiments, all objects to be irradiated 3 placed in the irradiation device 2 are arranged vertically, in an array, or horizontally. The objects to be irradiated 3 and the radiation source 1 are relatively stationary or in relative motion. By rationally designing the irradiation field and the irradiation device 2, the gamma rays emitted during the decay of the radioactive nuclides therein can be reused. For the objects to be irradiated 3 arranged in the above manner, the irradiation device 2 used is of a lifting type, a stationary type, or a conveying type. For example, when multiple objects to be irradiated 3 are arranged vertically, the irradiation device 2 adopts a frame structure with vertical layers, with one object to be irradiated 3 placed on each layer. The radiation source 1 adopts a columnar body with a cylindrical hole recessed inward at the top for accommodating the irradiation device 2. The top of the irradiation device 2 is bent and can be mounted on the radiation source 1. When multiple objects to be irradiated 3 are arranged in an array, the irradiation device 2 adopts a layered frame structure with each layer separated. For example, the irradiation device 2 places 2×2 objects to be irradiated on each layer. The irradiated object 3 is processed into a cube or columnar shape, and each irradiation source 1 is placed between two objects 3 to be irradiated, with a total of 4 layers. When multiple objects 3 to be irradiated are arranged horizontally, the irradiation device 2 adopts a conveying type. For example, the irradiation device 2 is a conveyor capable of cyclic transmission, which has a conveyor belt. The objects 3 to be irradiated are arranged on the conveyor belt at intervals. The irradiation source 1 is cylindrical and placed horizontally. The cylindrical irradiation source 1 is provided with a channel connecting the two end faces, and the conveyor belt passes through the channel, so that the objects 3 to be irradiated can pass through the irradiation source 1 and be conveyed with the irradiation device 2.

[0047] In some embodiments, the radiation source 1 is a cube, cylinder, or sphere; or the radiation source 1 is a cube, cylinder, or sphere with slots, holes, or channels for accommodating the object to be irradiated. Radioactive solid waste is processed into the radiation source 1 according to required shape and size. The shape can be determined based on the irradiation purpose and the object to be irradiated, such as a rectangular parallelepiped, cube, sphere, spherical shell, or tube. The size can also be determined based on the irradiation purpose and the object to be irradiated, ranging from centimeters to hundreds of meters. In some embodiments, the size range of the radiation source 1 is [a cm, b*100 m], where a and b are both natural numbers less than or equal to 10. For example, the size range of the radiation source 1 is a 5 cm × 5 cm × 5 cm cube. The scale of the irradiation field also depends on the irradiation purpose and the object to be irradiated. Irradiation fields constructed for scientific research can be as small as centimeters, while those constructed for production can be as large as hundreds of meters.

[0048] In some embodiments, the radioactive solid waste includes pure metal materials, and / or alloy materials, mainly including pure aluminum and aluminum alloys, steel, nickel alloys, pure copper and copper alloys, zirconium alloys, niobium alloys, molybdenum alloys, hafnium alloys, tantalum alloys, tungsten alloys, rhenium alloys, etc. In some embodiments, the radioactive solid waste is a material that can generate gamma rays, so that the ray source 1 generates gamma rays. The radioactive solid waste contains complex radioactive nuclides, and the energy range of the radiated rays is very wide, which can induce more complex and diverse biochemical reactions. The present application utilizes the gamma rays generated by radioactive waste, wherein the irradiation source mainly used for the utilization of gamma rays is 60 Co and 137 Cs, the gamma rays emitted by these two radioactive sources have the characteristics of high energy and high intensity, which have great advantages in some application scenarios that require strong radiation (such as irradiation sterilization, etc.); however, some other application scenarios have relatively low requirements for the energy and intensity of gamma rays. The gamma rays emitted by radioactive solid waste can meet the use requirements to a certain extent, and 60 Co and 137 The energy of gamma rays emitted by Cs radioactive sources is relatively single.

[0049] This application utilizes the gamma rays generated by the radiation source 1, which has significant research value and application prospects in the fields of irradiation breeding (for animals, plants, beneficial bacteria, viruses, etc.), food irradiation treatment (for example, inhibiting germination, delaying maturity, extending storage life, degrading harmful residues such as antibiotics, pesticides, veterinary drugs, allergens, biotoxins, and wine aging), and irradiation modification of industrial raw materials. Utilizing the gamma rays emitted by these radioactive solid wastes could generate considerable economic value and promote the construction of radioactive solid waste disposal sites (also serving as gamma ray utilization sites), effectively alleviating the increasing pressure on my country's radioactive solid waste disposal.

[0050] In some embodiments, the method further includes: S5, regularly measuring the equivalent dose of radiation at different positions within the irradiation device 2, and removing and disposing of radiation sources 1 that do not meet the expected equivalent dose. The period of regular measurement depends on the half-life of the main radioactive nuclides. Radiation sources that do not meet the expected equivalent dose are deemed to have no application value. The expected equivalent dose may vary depending on different purposes, mainly considering the value and time cost of gamma rays. If the value of gamma rays in irradiating the object 3 to be irradiated is insufficient to cover the time cost, the radiation source 1 in this part will be disposed of as radioactive waste. After removal, the treatment of the radiation source 1 must comply with relevant national laws and regulations on the disposal of radioactive waste. In some embodiments, not meeting the expected equivalent dose means: for food irradiation treatment, the equivalent dose of surface gamma rays is less than 5mSv / h, such as 4.8mSv / h, 3.0mSv / h, etc.; for scientific research, the equivalent dose of surface gamma rays is less than 10mSv / h, such as 6.0mSv / h, 9.5mSv / h, etc.; for irradiation modification of industrial raw materials, the equivalent dose of surface gamma rays is less than 50mSv / h, such as 48mSv / h, 30mSv / h, etc.

[0051] The following are some examples of methods for recycling radioactive solid waste:

[0052] Example 1

[0053] S0. According to the types and radioactivity of the main radioactive nuclides, the radioactive solid waste is classified and radioactive solid waste stainless steel is selected. The information of the main radioactive nuclides is shown in Table 1.

[0054] Table 1 Information on major radionuclides in stainless steel radioactive solid waste

[0055]

[0056] S1. The screened radioactive solid waste stainless steel was processed into a tubular gamma-ray source 1 with an outer diameter of 20 cm, a wall thickness of 5 mm, and a height of 50 cm by melting and then casting. The energy of the gamma-ray on its surface was measured to be 126 keV to 1674.73 keV, and the surface equivalent dose was about 500 mSv / h.

[0057] S2. In a Class A non-sealed source workplace, use a tubular gamma-ray source 1 to build an irradiation field, use lead bricks for shielding around it, and build a lifting irradiation device 2 in conjunction with it.

[0058] S3. The irradiated objects 33 (a total of 5 groups, namely rice seeds, pea seeds, corn seeds, strawberry seeds, and bifidobacterium colonies) whose irradiation purpose is irradiation breeding for food production are selected, and the irradiated objects 3 are placed in the grid of the irradiation device 2.

[0059] S4. Irradiate to the target absorbed dose (5Gy~400Gy), and take out in batches for subsequent scientific research.

[0060] S5. Re-measure the equivalent dose of gamma rays at different positions in the irradiation device 2 every year. When the equivalent dose on the surface of the tubular gamma ray source 1 is less than 10 mSv / h, it shall be transported to a near-surface disposal site as radioactive waste for disposal.

[0061] Example 2

[0062] S0. According to the types and radioactivity of the main radioactive nuclides, the radioactive solid waste was classified and the radioactive solid waste 6061 aluminum alloy was selected. The information of the main radioactive nuclides is shown in Table 2.

[0063] Table 2 Information on major radionuclides in 6061 aluminum alloy radioactive solid waste

[0064] Serial number Main nuclides half life γ-ray energy / keV 1 <![CDATA[ 55 Fe]]> 2.73a 126 2 <![CDATA[ 65 Zn]]> 244.06d 1115.539

[0065] S1. The screened radioactive solid waste 6061 aluminum alloy was processed into a tubular gamma-ray source 1 with an outer diameter of 1 m, a wall thickness of 1 cm, and a length of 5 m by melting and then casting. The energy of the gamma-rays on its surface was measured to be 126 keV and 1115.539 keV, and the surface equivalent dose was about 50 mSv / h.

[0066] S2. In the near-surface disposal site, a tubular gamma-ray source 1 is used to build an irradiation field, which is shielded by lead bricks and concrete around it, and a transmission-type irradiation device 2 is constructed in conjunction with it.

[0067] S3. Place 35 objects to be irradiated (4 groups in total, namely garlic, pumpkin, walnut, and mung bean) for food irradiation treatment for scientific research on the conveyor belt of the irradiation device 2, start the conveyor, and the objects to be irradiated 3 are periodically conveyed through the irradiation device 2 in sequence.

[0068] S4. Irradiate to the target absorbed dose (0.01Gy~0.5Gy), and take out in batches for subsequent scientific research.

[0069] S5. Re-measure the equivalent dose of gamma rays at different positions in the irradiation device 2 every year. When the equivalent dose on the surface of the tubular gamma ray source 1 is less than 5 mSv / h, it shall be transported to a near-surface disposal site as radioactive waste for disposal.

[0070] Example 3

[0071] S0. According to the type and radioactivity of the main radioactive nuclides, the radioactive solid waste is classified and screened out. The information of the main radioactive nuclides of Zr-4 alloy in the radioactive solid waste is shown in Table 3.

[0072] Table 3 Information on main radionuclides in Zr-4 alloy radioactive solid waste

[0073] Serial number Main nuclides half life γ-ray energy / keV 1 <![CDATA[ 95 Zr]]> 64.03d 235.69、724.193、756.729 2 <![CDATA[ 95 Nb]]> 34.99d 204.12、561.88、765.803 3 <![CDATA[ 119 Sn]]> 293.1d 23.875

[0074] S1. The screened radioactive solid waste Zr-4 alloy was processed into a cubic gamma-ray source 1 with a side length of 50 cm by cutting and compressing. The energy of the gamma-ray on its surface was measured to be 23.875 keV to 765.803 keV, and the surface equivalent dose was about 200 mSv / h.

[0075] S2. In the near-surface disposal site, a cubic gamma-ray source 1 is used to build an irradiation field, and the surrounding area is shielded with concrete and carbon steel. A static irradiation device 2 is constructed in conjunction with the irradiation field. The irradiation field is divided into a four-layer grid structure, with two cubic gamma-ray sources 1 symmetrically placed on each layer.

[0076] S3. Place the irradiated objects 9 (a total of 4 groups, namely chrysanthemums, roses, and orchids for ornamental plant irradiation breeding, and white wine for irradiation aging treatment) for the purpose of scientific research on irradiation breeding and food irradiation treatment on the grid of the irradiation device 2, respectively on both sides of the ray source 1 on each layer.

[0077] S4. Irradiate to the target absorbed dose (2Gy~2kGy), and take out in batches for subsequent scientific research or analytical testing.

[0078] S5. Re-measure the equivalent dose of gamma rays at different positions in the irradiation device 2 every six months. When the equivalent dose on the surface of the cubic gamma ray source 1 is less than 5mSv / h, it shall be transported to a near-surface disposal site as radioactive waste for disposal.

[0079] Regarding the specific implementation of this application, it should be noted that:

[0080] In the description of this application, unless otherwise clearly specified and limited, the terms "connect", "fixed", "connected", etc. should be understood in a broad sense. For example, "fixed" can be a fixed connection, a detachable connection, or an integral molding; "connection" can be a mechanical connection or an electrical connection; it can be a direct connection or an indirect connection through an intermediate medium, it can be the internal connection of two elements or the interaction relationship between two elements, unless otherwise clearly limited; "connected" can be the internal connection of two parts and between two parts, or the spatial connection between the two, and the two are directly or indirectly connected through the part that forms the space. The terms "set", "install", "provided with", "configured", etc. should also be understood in a broad sense. For ordinary technicians in this field, the specific meanings of the above terms in this application can be understood according to the specific circumstances.

[0081] In the description of this application, the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "up", "down", "front", "back", "left", "right", "vertical", "horizontal", "top", "bottom", "inside", "outside", "clockwise", "counterclockwise", etc., indicating directions or positional relationships, are based on the directions or positional relationships shown in the accompanying drawings and are only used to facilitate the description of this application and simplify the description. They do not indicate or imply that the system or component referred to must have a specific direction, be constructed and operate in a specific direction, and therefore should not be understood as limiting this application. All directional indications are only used to explain the relative positional relationships, movement conditions, etc. between the components in a specific posture. If the specific posture changes, the directional indication will also change accordingly.

[0082] In the description of this application, reference to the terms "some embodiments", "optional embodiments", "examples", "specific examples", "optional examples" or "optional embodiments" and the like means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of this application, but does not mean that these embodiments illustrate and describe all possible forms of the invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. In addition, those skilled in the art may combine and combine the different embodiments or examples described in this specification.

[0083] The present invention has been described in detail above with reference to specific embodiments and exemplary examples. The above description is illustrative, not exhaustive, and is not limited to the disclosed embodiments; the above description cannot be understood as a limitation of the present invention. The technical solutions between the various embodiments can be combined with each other, but must be based on the ability of ordinary technicians in this field to implement. When the combination of technical solutions is mutually contradictory or cannot be implemented, it should be considered that such a combination of technical solutions does not exist and is not within the scope of protection required by this application. Although the embodiments of the present application have been shown and described, these embodiments can be subjected to various changes, modifications, substitutions and variations without departing from the principles and purposes of the present application. Ordinary technicians in this field can understand that various other specific changes and combinations of embodiments that do not depart from the essence of the present application are made according to the technical inspirations disclosed in this application, and are still within the scope of protection defined by the claims of the present invention and its equivalent technical solutions.

Claims

1. A method for recycling radioactive solid waste, characterized in that: include: Processing radioactive solid waste into a radiation source according to shape and size requirements, and measuring the energy and equivalent dose of radiation on the surface of the radiation source; Building an irradiation field and taking shielding measures, installing an irradiation device for placing the object to be irradiated in the irradiation field, and placing the radiation source in the irradiation field; According to the irradiation purpose, a position that meets the preset radiation energy and equivalent dose rate is selected in the irradiation device, and the object to be irradiated is placed thereon for irradiation; When the object to be irradiated has been irradiated to a target absorbed dose, an irradiated object is obtained, and the irradiated object is taken out in a single or batch manner.

2. The method for recycling radioactive solid waste according to claim 1, characterized in that: Also includes: Before the radioactive solid waste is processed into a radiation source, the radioactive solid waste is classified according to the type of main radionuclides and the radioactivity level; When the radioactive solid waste is processed into a radiation source, the radioactive solid waste is processed into a variety of radiation sources according to the classification of the radioactive solid waste; Before placing the radiation source in the irradiation field, the radiation source is selected according to the irradiation purpose and the object to be irradiated.

3. The method for recycling radioactive solid waste according to claim 2, characterized in that: The radioactive solid waste is classified according to the size of the radioactivity, specifically: the radioactive solid waste is classified according to the equivalent dose of the radiation of <10mSv / h, 10-100mSv / h, 100-500mSv / h, and >500mSv / h.

4. The method for recycling radioactive solid waste according to claim 1, characterized in that: All the objects to be irradiated placed in the irradiation device are arranged vertically, in an array or horizontally, and the objects to be irradiated are relatively stationary or in relative motion with the radiation source.

5. The method for recycling radioactive solid waste according to claim 4, characterized in that: The ray source is a cube, a cylinder, or a sphere; or the ray source is a cube, a cylinder, or a sphere, and is provided with a slot, a hole, or a channel for accommodating the object to be irradiated.

6. The method for recycling radioactive solid waste according to claim 1, characterized in that: The radioactive solid waste is a material capable of generating gamma rays, so that the ray source generates gamma rays.

7. The method for recycling radioactive solid waste according to claim 6, characterized in that: The radioactive solid waste includes pure metal materials and / or alloy materials.

8. The method for recycling radioactive solid waste according to claim 6, characterized in that: The size range of the ray source is [a cm, b*100m], where a and b are both natural numbers less than or equal to 10.

9. The method for recycling radioactive solid waste according to any one of claims 1 to 8, characterized in that: Also includes: The equivalent dose of radiation at different positions in the irradiation device is measured regularly, and the radiation source that does not meet the expected equivalent dose is removed and disposed of.

10. The method for recycling radioactive solid waste according to claim 9, characterized in that: The undesirable equivalent dose refers to: For food irradiation, the equivalent dose of surface gamma rays is less than 5mSv / h; For scientific research, the equivalent dose of surface gamma rays is less than 10mSv / h; For the irradiation modification of industrial raw materials, the equivalent dose of surface gamma rays is less than 50mSv / h.

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