Radioactive waste servicing method and servicing system thereof

Abstract

The invention discloses a radioactive waste servicing method and a servicing system thereof, which can recycle part of disassembly products in detachable waste, reduce waste and reduce subsequent disposal cost. And secondly, before reconditioning, the volume of the disassembling product which finally needs reconditioning can be reduced by compressing the disassembling product which finally needs reconditioning, so that the waste filling rate is improved, and the waste minimization level is favorably improved. The preparation method comprises the steps that S1, detachable waste in radioactive waste is disassembled into disassembled products, so that the space occupied by the detachable waste is reduced; s2, detecting the radioactivity level of the disassembled product; and S3, according to the radioactivity level and the compression characteristic of the disassembled product, the disassembled product is subjected to recovery, reconditioning or reconditioning after compression.

Description

Technical Field

[0001] The invention belongs to the technical field of radioactive waste treatment, and in particular relates to a radioactive waste conditioning method and a conditioning system thereof. Background Art

[0002] Reprocessing plants generate low-level solid waste during operation and maintenance, a considerable portion of which is surface-contaminated radioactive metal waste, including surface-contaminated pump cores, valve cores, pipe fittings, equipment parts, hot cell tools and control area maintenance tools.

[0003] The existing means are mainly to prepare by means of super compaction or cement fixation. Filter elements, ground-penetrating valves, plunger pump cores, etc. need to be placed in steel boxes for cement fixation. The existing technology usually directly treats each radioactive metal waste as a whole as low-level solid waste by cement fixation. However, the radioactivity levels of different components of radioactive metal waste are very unevenly distributed and have a wide range of radioactivity levels. The extremely low radioactivity level (for example, less than or equal to 10 4 Bq / kg) is wasted, which is not conducive to waste minimization (waste minimization refers to reducing the amount and activity of radioactive waste generated by reprocessing plants during operation, maintenance and decommissioning through a series of technical, management and strategic means). Summary of the invention

[0004] The technical problem to be solved by the present invention is to provide a radioactive waste conditioning method and a conditioning system thereof in view of the above-mentioned deficiencies in the prior art, which can recycle part of the disassembly products in the disassemblyable waste to reduce waste and reduce subsequent disposal costs; and by compressing the disassembly products that ultimately need to be conditioned before conditioning, the volume of the disassembly products that ultimately need to be conditioned can be reduced, the waste filling rate can be increased, and the level of waste minimization can be improved.

[0005] In a first aspect, an embodiment of the present invention provides a method for conditioning radioactive waste, wherein the radioactive waste includes decomposable waste; the conditioning method comprises: S1, disassembling the decomposable waste in the radioactive waste into disassembly products to reduce the space occupied by the decomposable waste; S2, detecting the radioactivity level of the disassembly products; S3, recovering, conditioning or compressing the disassembly products according to the radioactivity level and compression characteristics of the disassembly products.

[0006] In some embodiments, the decomposable waste includes a ventilation filter element, and the ventilation filter element includes a square filter element; the disassembly product is a metal plate and a filter material; the step S1 includes: disassembling the square filter element into a square frame and a filter material, and continuing to decompose the square frame into a metal plate.

[0007] In some embodiments, after step S1 and before step S2, the preparation method further includes: respectively loading the metal plate and the filter material into different transfer barrels; step S2 specifically includes: detecting the radioactivity level of each transfer barrel; step S3 specifically includes: based on the relationship between the radioactivity level of each transfer barrel and the preset recovery value, and the compression characteristics of the radioactive waste loaded in the transfer barrel, the radioactive waste loaded in each transfer barrel is recycled, prepared, or compressed and prepared.

[0008] In some embodiments, the radioactive waste also includes non-disassembly waste, and the non-disassembly waste includes non-disassembly metal waste; before step S2, the preparation method also includes: according to the compression characteristics of the non-disassembly metal waste, loading the non-disassembly metal waste into different transfer barrels.

[0009] In some embodiments, the disassembled waste includes a ground-penetrating valve; the disassembly product is a ground-penetrating valve segment; then the step S1 specifically includes: disassembling the ground-penetrating valve into a plurality of ground-penetrating valve segments; the step S2 specifically includes: S21, detecting the radioactivity level of each ground-penetrating valve segment, and removing the ground-penetrating valve segment with a radioactivity level greater than a preset cleaning value; S22, cleaning the remaining ground-penetrating valve segments; S23, detecting the radioactivity level of the ground-penetrating valve segment after cleaning; S24, classifying the ground-penetrating valve segment after cleaning into recoverable ground-penetrating valve segments and ground-penetrating valve segments to be repaired according to the relationship between the radioactivity level of the ground-penetrating valve segment after cleaning and a preset recovery value; S25, loading the ground-penetrating valve segments with a radioactivity level greater than the preset cleaning value and the ground-penetrating valve segments to be repaired into the same transfer barrel, and loading the recoverable ground-penetrating valve segments into another transfer barrel; the radioactivity level of the ground-penetrating valve segment loaded in each transfer barrel is used as the radioactivity level of the corresponding transfer barrel.

[0010] In some embodiments, the radioactive waste also includes non-disassembled waste, and the non-disassembled waste includes pump cores; the step S21 also includes: detecting the radioactivity level of each pump core, and removing the pump cores whose radioactivity level is greater than the preset cleaning value; the step S22 also includes: cleaning the remaining pump cores; the step S23 also includes: detecting the radioactivity level of the pump cores after cleaning; the step S24 also includes: classifying the pump cores after cleaning into recyclable pump cores and pump cores to be conditioned according to the relationship between the radioactivity level of the pump cores after cleaning and the preset recovery value; the step S25 also includes: loading the pump cores with radioactivity levels greater than the preset cleaning value and the pump cores to be conditioned into the same transfer box, and loading the recyclable pump cores into another transfer box; taking the radioactivity level of the pump cores loaded in each transfer box as the radioactivity level of the corresponding transfer box; the step S3 also includes: recycling, conditioning or compressing the radioactive waste loaded in each transfer box according to the relationship between the radioactivity level of each transfer box and the preset recovery value, and the compression characteristics of the radioactive waste loaded in the transfer box.

[0011] In some embodiments, after step S2 and before step S3, the preparation method further includes: adding a corresponding identification code to each transfer barrel or transfer box based on the radioactivity level of each transfer barrel or transfer box obtained by detection, and the compression characteristics of the radioactive waste loaded in the transfer barrel or transfer box; reading the identification code on each transfer barrel or transfer box to obtain the corresponding radioactivity level of the transfer barrel or transfer box, and the compression characteristics of the radioactive waste loaded in the transfer barrel or transfer box.

[0012] In some embodiments, step S3 is specifically as follows: compare the relationship between the radioactivity level of each transfer barrel or transfer box and the preset recycling value, and obtain a comparison result; if the radioactivity level of the transfer barrel or the transfer box is less than or equal to the preset recycling value, recycle the radioactive waste in the transfer barrel or the transfer box; if the radioactivity level of the transfer barrel or the transfer box is greater than the preset recycling value, and the radioactive waste in the transfer barrel or the transfer box is compressible, compress the corresponding transfer barrel or the transfer box and put it into a waste preparation packaging container, and pour cement into the waste preparation packaging container to seal it; if the radioactivity level of the transfer barrel or the transfer box is greater than the preset recycling value, and the radioactive waste in the transfer barrel or the transfer box is incompressible, pour cement into the corresponding transfer barrel or the transfer box to seal it.

[0013] Therefore, the radioactive waste conditioning method provided by the embodiment of the present invention can reduce the gaps between the dismantled products and the gaps between the dismantled products and the side walls of the transfer barrel or conditioning container compared to the dismantled waste before dismantling, thereby reducing the space occupied by the dismantled waste after dismantling, and facilitating subsequent transportation and conditioning; by detecting the radioactivity level of the dismantled products and recovering the dismantled products according to the radioactivity level and compression characteristics of the dismantled products, the problem of uneven radioactivity level of the conditioning waste can be solved, and part of the radioactive waste can be recovered to reduce waste, thereby reducing the total amount of radioactive waste that ultimately needs to be conditioned; by compressing the remaining part of the radioactive waste and conditioning it, the gaps between the radioactive waste that ultimately needs to be conditioned can be reduced, thereby reducing the volume occupied by the radioactive waste that ultimately needs to be conditioned, and improving the filling rate of the radioactive waste after conditioning, which is conducive to ultimately improving the level of waste minimization.

[0014] In a second aspect, the embodiments of this aspect also provide a radioactive waste conditioning system, wherein the radioactive waste includes disassembled waste; the radioactive waste conditioning system includes a disassembly device, a waste detection device, and a recovery and conditioning device. The disassembly device is used to disassemble the disassembled waste in the radioactive waste into disassembly products to reduce the space occupied by the disassembled waste. The waste detection device is used to receive the disassembly products and detect the radioactivity level of the disassembly products. The recovery and conditioning device is used to receive the disassembly products detected in the waste detection device, and then, according to the radioactivity level and compression characteristics of the disassembly products, respectively, recover, condition, or condition the disassembly products after compression.

[0015] In some embodiments, the disassembled waste includes a ventilation filter element, the ventilation filter element includes a square filter element; the disassembled product is a metal plate and a filter material. The disassembly device includes a ventilation filter element disassembly device, the ventilation filter element disassembly device is used to disassemble the square filter element into a square frame and filter material, and continue to decompose the square frame into a metal plate; or, the disassembled waste includes a ground-penetrating valve; the disassembly product is a ground-penetrating valve section; the disassembly device includes a ground-penetrating valve disassembly device, the ground-penetrating valve disassembly device is used to disassemble the ground-penetrating valve into a plurality of ground-penetrating valve sections.

[0016] The radioactive waste conditioning system provided in the embodiment of the present invention has the same beneficial effects as the above-mentioned radioactive waste conditioning method, which will not be described in detail here. BRIEF DESCRIPTION OF THE DRAWINGS

[0017] Figure 1 : A flow chart of a method for preparing radioactive waste provided by an embodiment of the present invention;

[0018] Figure 2: A process flow chart for treating radioactive waste provided by an embodiment of the present invention;

[0019] Figure 3 :for Figure 2 A partial enlarged view of the middle Q1 area;

[0020] Figure 4A :for Figure 2 A partial enlarged view of the middle Q2 area;

[0021] Figure 4B : A schematic diagram of a square filter element provided in an embodiment of the present invention;

[0022] Figure 4C : A schematic diagram of a circular filter element provided in an embodiment of the present invention;

[0023] Figure 5 :for Figure 2 A partial enlarged view of the middle Q3 area;

[0024] Figure 6 : A partial flow chart of a method for preparing radioactive waste provided in an embodiment of the present invention;

[0025] Figure 7 :for Figure 2 A partial enlarged view of the middle Q4 area;

[0026] Figure 8 : A structural schematic diagram of a radioactive waste conditioning system provided in an embodiment of the present invention. DETAILED DESCRIPTION

[0027] In order to enable those skilled in the art to better understand the technical solution of the present invention, the present invention is further described in detail below with reference to the accompanying drawings and embodiments.

[0028] Embodiment 1:

[0029] like Figure 1 As shown, an embodiment of the present invention provides a method for preparing radioactive waste, which is applied in the field of nuclear chemical industry, for example, can be used to process radioactive waste with radioactivity generated by a post-processing plant.

[0030] like Figure 1 As shown, the radioactive waste preparation method includes: steps S1-S3.

[0031] S1. Disassemble the decomposable waste in the radioactive waste into disassembly products to reduce the space occupied by the decomposable waste.

[0032] Exemplarily, the waste is specifically radioactive waste from a post-processing plant, and the radioactive waste includes demountable waste and non-demountable waste; the demountable waste includes ventilation filter elements and ground-penetrating valves, and the non-demountable waste includes pump cores and non-demountable metal waste.

[0033] For example, the radioactivity level in different parts of the radioactive waste is greater than 10 3 Bq / kg, and less than 10 9 Bq / kg. For example, a ventilation filter element consists of a metal frame and filter material attached to the metal frame. The radioactivity level of the filter material is about 5×10 8 Bq / kg, while the radioactivity level of the metal frame of the ventilation filter is about 3×10 4 Bq / kg.

[0034] For example, the transfer barrel is a container for loading radioactive waste when transferring radioactive waste in different processes. The material, volume, shape and other characteristics of the transfer barrel are not limited and can be selected according to the size of the radioactive waste to be loaded. Figure 2 and Figure 3 As shown, the transfer barrel in this embodiment can be a 200L barrel (for example, a size of ).

[0035] In other examples, a larger transfer box (for example, 2000mm×1000mm×700mm) may be used to load the longer pump cores and ground-penetrating valves in the radioactive waste, where the length of the pump cores and ground-penetrating valves is approximately 2m.

[0036] Exemplary, combined Figure 2 and Figure 3 Before step S1, the preparation method further includes: collecting and classifying radioactive waste for later processing.

[0037] For example, Figure 3 As shown, transport vehicles are used to collect radioactive waste from various facilities / workshops in the reprocessing plant, and the radioactive waste is placed on the transport vehicles in a classified manner.

[0038] Normally, radioactive waste is conditioned by placing it in conditioning containers and then filling them with cement mortar to fix them.

[0039] It is understandable that, usually, the shape of disassembled waste is irregular, the overall size of disassembled waste is large, and it occupies more space. After the disassembled waste is loaded into the transfer barrel or preparation container, the gap between the disassembled waste and the side wall of the preparation container is large. The amount of disassembled waste that can be transported in a transfer barrel or preparation container is limited, which is not conducive to transportation. In addition, the final preparation volume is also large, and the internal filling rate is not high, which is not conducive to waste minimization. After the disassembled waste is disassembled, the size of the disassembled product is smaller and the space occupied is also less. In addition, the gap between the disassembled products and the gap between the disassembled products and the side wall of the transfer barrel or preparation container can be reduced, thereby reducing the space occupied by the disassembled waste after disassembly, which is convenient for subsequent transportation and preparation.

[0040] S2. Detect the radioactivity level of the disassembly products.

[0041] For example, during detection, the radioactivity level of each disassembly product may be detected separately, or after collecting multiple disassembly products, the overall radioactivity level of the multiple disassembly products may be detected.

[0042] S3. According to the radioactivity level and compression characteristics of the dismantling products, the dismantling products are recovered, conditioned or compressed before conditioning.

[0043] In this embodiment, the compression characteristic of an object indicates whether the object is compressible.

[0044] Exemplarily, the radioactivity level of the disassembly product is low (e.g., less than or equal to 10 4 Bq / kg), the dismantling products can be recycled (transported to temporary storage and then smelted), which can reduce the total amount of radioactive waste that needs to be prepared in the end; the radioactivity level of the dismantling products is high (for example, greater than 10 4 Bq / kg), the dismantling products need to be conditioned. During conditioning, if the dismantling products are compressible, they are first compressed. The total volume of the compressed radioactive waste becomes smaller, which can further reduce the total amount of radioactive waste that needs to be conditioned.

[0045] Therefore, by first disassembling the disassemblyable waste into disassembly products, the gaps between the disassembly products and the gaps between the disassembly products and the side walls of the transfer barrel or preparation container can be reduced compared to the disassemblyable waste before disassembly, thereby reducing the space occupied by the disassemblyable waste after disassembly, facilitating subsequent transportation and preparation; according to the radioactivity level and compression characteristics of the disassembly products, after recycling some of the disassembly products, it is possible to reduce the waste of disassembly products, reduce the total amount and volume of radioactive waste that ultimately needs to be prepared, and reduce the subsequent disposal cost; through compression and post-preparation, the volume of radioactive waste that ultimately needs to be prepared can be further reduced, and the filling rate of radioactive waste that ultimately needs to be prepared can be increased.

[0046] Therefore, the radioactive waste conditioning method provided by the embodiment of the present invention can reduce the gaps between the disassembled products and the gaps between the disassembled products and the side walls of the transfer barrel or conditioning container compared to the disassembled waste before disassembly, thereby reducing the space occupied by the disassembled waste after disassembly, and facilitating subsequent transportation and conditioning; by detecting the radioactivity level of the disassembled products and recovering the disassembled products according to the radioactivity level and compression characteristics of the disassembled products, part of the radioactive waste can be recovered, waste can be reduced, and the total amount of radioactive waste that needs to be conditioned is reduced, and the problem of uneven radioactivity level of the waste can be solved; by compressing and conditioning part of the radioactive waste that needs to be conditioned, the gaps between the radioactive waste that needs to be conditioned can be reduced, thereby reducing the volume occupied by the radioactive waste that needs to be conditioned, reducing the subsequent disposal cost, and improving the filling rate of the radioactive waste after conditioning, which is conducive to ultimately improving the level of waste minimization.

[0047] In some embodiments, in combination Figure 2 and Figure 4A The disassembled waste includes ventilation filter elements, and the ventilation filter elements include square filter elements; the disassembled products are metal plates and filter materials. The above step S1 includes: disassembling the square filter element into a square frame and filter materials, and further decomposing the square frame into metal plates.

[0048] In some examples, the vent filter element further comprises a round filter element.

[0049] Exemplary, combined Figure 2 and Figure 4A The processing of square filter elements and round filter elements is carried out in the ventilation filter element processing room, which is equipped with a ventilation filter element disassembly glove box and transfer facilities (crane, sling and roller, etc.).

[0050] For example, when a transport vehicle is used to collect radioactive waste from various facilities / workshops of a reprocessing plant, square filter elements and round filter elements are collected in a waste transfer container. After the square filter elements and round filter elements are collected, a crane and a sling are first used to lift the waste transfer container from the transport vehicle to a temporary waste storage room for temporary storage. When treatment is required, the waste transfer container is lifted onto a roller conveyor by a crane and a sling, and the waste transfer container equipped with square filter elements and round filter elements is sent to a ventilation filter element treatment room via a roller conveyor for treatment.

[0051] In the ventilation filter element processing room, the process of disassembling the square filter element into metal plates and filter materials can be: combined with Figure 4A , Figure 4B and Figure 4CFirst, the square filter element is flushed with 50MPa high-pressure water to separate the filter material from the square frame of the square filter element; the flushed filter material enters the centrifugal device for dehydration and drying, and the square frame is conveyed to the ventilation filter element disassembly glove box via a conveyor belt. After the operator removes the screws that fix the square frame with special tools, the square frame is disassembled into metal plates.

[0052] When washing with high-pressure water, the metal sheet can be indirectly decontaminated. Compared with before cleaning and decontamination, the disassembled products can be downgraded later to reduce the subsequent processing costs.

[0053] Through the above method, the square filter element can be disassembled into metal plates and filter materials that are easy to pack.

[0054] In some embodiments, after the above step S1 and before step S2, the preparation method further includes: loading the metal plate and the filter material into different transfer barrels respectively.

[0055] For example, Figure 4A As shown, the transfer barrel is docked with the bottom of the ventilation filter element treatment room, so that the metal sheet and the filter material are loaded into different transfer barrels.

[0056] That is, the metal plate is placed in one transfer barrel, and the filter material is placed in another transfer barrel, so that the metal plate and the filter material can be recovered, prepared, or compressed and prepared separately in the future.

[0057] In this step, the round filter element is also directly loaded into a transfer bucket.

[0058] The above step S2 specifically includes: detecting the radioactivity level of each transfer barrel. The step S3 specifically includes: recovering, conditioning or compressing the radioactive waste in each transfer barrel according to the relationship between the radioactivity level of each transfer barrel and the preset recovery value and the compression characteristics of the radioactive waste in the transfer barrel.

[0059] Exemplary, combined Figure 4A A first waste detection device is installed in the ventilation filter treatment room to detect the radioactivity level of each transfer barrel.

[0060] It can be understood that the metal plates and filter materials are both small in size and large in quantity. By first loading the metal plates and filter materials into a transfer barrel and then testing the radioactivity level of the transfer barrel, the amount of testing can be reduced.

[0061] For example, the recycling preset value can be set according to production experience, relevant regulations or specifications, etc. For example, the recycling preset value can be 10 4 Bq / kg.

[0062] Exemplarily, the radioactivity level of the transfer barrel containing the dismantling product (or the circular filter element) is less than or equal to 10 4 Bq / kg, the transfer barrel can be recycled (transported to the temporary storage room for temporary storage and subsequent smelting); the radioactivity level of the transfer barrel containing the dismantling product (or round filter element) is greater than 10 4 Bq / kg, the transfer barrel needs to be prepared.

[0063] At this point, the disassembled products of the square filter element can be recovered, sorted, or compressed before preparation.

[0064] In some embodiments, the non-disassembled waste also includes non-disassembled metal waste. Before the above step S2, the preparation method further includes: according to the compression characteristics of the non-disassembled metal waste, the non-disassembled metal waste is loaded into different transfer barrels.

[0065] Exemplarily, according to the compression characteristics of non-disassembled metal waste, the non-disassembled metal waste is divided into incompressible metal waste and compressible metal waste, the incompressible metal waste is loaded into one transfer barrel, and the compressible metal waste is loaded into another transfer barrel, so as to facilitate the subsequent recycling, preparation or compression and preparation of the incompressible metal waste and the compressible metal waste respectively.

[0066] Accordingly, the above step S3 also includes the recovery, preparation or preparation after compression of the transfer barrels containing the incompressible metal waste and the compressible metal waste.

[0067] In some embodiments, in combination Figure 2 , Figure 3 and Figure 5 , the disassembled waste includes a ground-penetrating valve (or a ground-penetrating valve core); the disassembled product is a ground-penetrating valve segment. Then step S1 specifically includes: disassembling the ground-penetrating valve into a plurality of ground-penetrating valve segments.

[0068] Exemplary, combined Figure 2 and Figure 5 The processing of the through-the-ground valve is carried out in the radioactive metal waste processing hot chamber.

[0069] For example, Figure 3 As shown, the ground-penetrating valve is placed in a waste transfer container after being collected. When the ground-penetrating valve needs to be processed, a crane is used to dock the waste transfer container equipped with the ground-penetrating valve with the top of the radioactive metal waste treatment hot chamber. After the docking is completed, the waste transfer container unloads the ground-penetrating valve from the inside, thereby completing the reception of the ground-penetrating valve in the radioactive metal waste treatment hot chamber.

[0070] Exemplarily, a ground-penetrating valve disassembly device is provided in a radioactive metal waste treatment hot chamber. In the radioactive metal waste treatment hot chamber, the ground-penetrating valve is firstly received remotely by the operating mechanism of the ground-penetrating valve disassembly device. According to the multi-section structural characteristics of the ground-penetrating valve, the ball buckle mechanism between the middle section and the lower section is automatically disengaged through the relative movement of the operating mechanism; the pin shaft connection between the upper section and the middle section of the ground-penetrating valve is manually disassembled; thereby, the ground-penetrating valve is disassembled into three sections, and the size of each ground-penetrating valve section is less than or equal to

[0071] In this case, if Figure 6 As shown, the above step S2 specifically includes: steps S21-S25.

[0072] S21, detecting the radioactivity level of each ground-penetrating valve section, and removing the ground-penetrating valve sections whose radioactivity level is greater than a preset cleaning value.

[0073] Exemplarily, a second waste detection device is provided in the radioactive metal waste treatment hot chamber to detect the radioactivity level of the through-ground valve section. The through-ground valve section is hoisted to the second waste detection device by a hoisting device for radioactivity level detection.

[0074] For example, the cleaning preset value can be set according to production experience, relevant regulations or specifications, etc. For example, the cleaning preset value is 10 7 Bq / kg.

[0075] If the radioactivity level of the through-the-ground valve section is greater than the preset cleaning value, it means that the through-the-ground valve section is not suitable for decontamination under the current conditions, and thus it is not cleaned.

[0076] S22, cleaning the remaining ground-penetrating valve sections.

[0077] Exemplary, combined Figure 5 The radioactive metal waste treatment hot room is equipped with an ultrasonic-chemical decontamination tank and a high-pressure water washing decontamination tank. The through-the-ground valve section is hoisted by a hoist, firstly in the ultrasonic-chemical decontamination tank for preliminary decontamination, and then hoisted to the high-pressure water decontamination tank for secondary decontamination and washing away the chemical reagents on the surface of the through-the-ground valve section. The decontaminated through-the-ground valve section is waiting to be drained.

[0078] S23. Detect the radioactivity level of the ground penetrating valve section after cleaning.

[0079] The drained through-ground valve section is hoisted to the second waste detection device, and the radioactivity level of the through-ground valve section is tested again by the second waste detection device.

[0080] S24. Classify the cleaned penetrating valve section into a recoverable penetrating valve section and a penetrating valve section requiring maintenance according to the relationship between the radioactivity level of the cleaned penetrating valve section and the preset recovery value.

[0081] For example, the default value of recycling is 10 4 Bq / kg.

[0082] Exemplarily, if the radioactivity level of the ground-penetrating valve section after cleaning is greater than the preset recovery value, it is classified as a ground-penetrating valve section that needs maintenance (non-recoverable); if the radioactivity level of the ground-penetrating valve section after cleaning is less than or equal to the preset recovery value, it is classified as a recoverable ground-penetrating valve section.

[0083] S25. Place the ground-penetrating valve sections whose radioactivity levels are greater than the preset cleaning value and the ground-penetrating valve sections that need to be repaired into the same transfer barrel, and place the recoverable ground-penetrating valve sections into another transfer barrel; the radioactivity level of the ground-penetrating valve sections placed in each transfer barrel is used as the radioactivity level of the corresponding transfer barrel.

[0084] After the through-ground valve section is loaded into the transfer barrel, it is transported out from the bottom interface of the radioactive metal waste treatment hot chamber.

[0085] Through steps S21-S25, the ground-penetrating valve sections can be classified and processed according to the radioactivity level, so that the ground-penetrating valve sections in the transfer barrel can be accurately processed according to the radioactivity level of the transfer barrel. In addition, the radioactivity level of the ground-penetrating valve sections can be reduced during flushing, and the ground-penetrating valve sections can be downgraded compared to before cleaning, thereby reducing the subsequent processing costs.

[0086] In some embodiments, the non-disassembled waste further includes a pump cartridge.

[0087] For example, Figure 3 As shown, the pump core is placed in a waste transfer container after being collected. When the pump core needs to be processed, a crane is used to dock the waste transfer container containing the pump core with the top of the radioactive metal waste treatment hot chamber. After the docking is completed, the waste transfer container unloads the pump core from the inside, thereby completing the reception of the pump core in the radioactive metal waste treatment hot chamber.

[0088] At this time, the above step S21 also includes: detecting the radioactivity level of each pump core, and removing the pump cores with a radioactivity level greater than the preset cleaning value. The above step S22 also includes: cleaning the remaining pump cores. The above step S23 also includes: detecting the radioactivity level of the pump core after cleaning. The above step S24 also includes: classifying the cleaned pump cores into recyclable pump cores and pump cores that need to be repaired according to the relationship between the radioactivity level of the cleaned pump core and the preset recycling value. The above step S25 also includes: loading pump cores with a radioactivity level greater than the preset cleaning value and pump cores that need to be repaired into the same transfer box, and loading recyclable pump cores into another transfer box; the radioactivity level of the pump core loaded in each transfer box is used as the radioactivity level of the corresponding transfer box.

[0089] The inspection, transfer, cleaning and testing methods of the pump core are similar to those of the ground-penetrating valve section and will not be repeated here.

[0090] The above step S3 also includes: recycling, conditioning or conditioning after compression of each transfer box according to the relationship between the radioactivity level of each transfer box and the preset recovery value, and the compression characteristics of the radioactive waste loaded in the transfer box.

[0091] Thus, the pump cores can be classified and processed according to the radioactivity level, so that the pump cores in the transfer barrel can be accurately processed according to the radioactivity level of the transfer barrel. In addition, the radioactivity level of the pump core can be reduced during flushing, so that the pump core can be downgraded compared to before flushing, reducing the subsequent processing costs.

[0092] In some embodiments, in combination Figure 2 , Figure 4A and Figure 5 , after the above step S2 and before step S3, the preparation method further includes: adding a corresponding identification code to each transfer barrel or transfer box according to the radioactivity level of each transfer barrel or transfer box obtained by detection, and the compression characteristics of the radioactive waste loaded in the transfer barrel or transfer box; reading the identification code on each transfer barrel or transfer box to obtain the radioactivity level of the corresponding transfer barrel or transfer box, and the compression characteristics of the radioactive waste loaded in the transfer barrel or transfer box.

[0093] Exemplary, combined Figure 2 , Figure 4A and Figure 5 The rear end of the ventilation filter processing room and the rear end of the radioactive metal waste processing hot chamber are equipped with coding devices and waste barrel identification and tracking devices.

[0094] The coder can identify the code on each transfer barrel or transfer box.

[0095] Exemplarily, the identification code consists of a QR code and numbers, and includes the source of the waste, waste characteristics (radioactivity level, compression characteristics), waste name, and transfer barrel or transfer box number, making the information of each transfer barrel or transfer box unique for easy tracking and management.

[0096] The waste barrel identification and tracking device can identify the identification code on the transfer barrel or transfer box, thereby identifying the relevant information of the radioactive waste in the transfer barrel or transfer box.

[0097] Through the above settings, each transfer barrel or transfer box can be marked and identified, which is convenient for tracking each transfer barrel or transfer box according to the identification code, facilitating the staff to manage the transfer barrels or transfer boxes and improving the automation level of transfer barrel or transfer box processing.

[0098] In some embodiments, in combination Figure 2 and Figure 7 , the above step S3 is specifically as follows: comparing the relationship between the radioactivity level of each transfer barrel or transfer box and the preset recycling value, and obtaining a comparison result; if the radioactivity level of the transfer barrel or transfer box is less than or equal to the preset recycling value, recycling the radioactive waste in the transfer barrel or transfer box; if the radioactivity level of the transfer barrel or transfer box is greater than the preset recycling value, and the radioactive waste in the transfer barrel or transfer box is compressible, compressing the corresponding transfer barrel or transfer box and loading it into a waste preparation packaging container, and pouring cement into the waste preparation packaging container to seal it; if the radioactivity level of the transfer barrel or transfer box is greater than the preset recycling value, and the radioactive waste in the transfer barrel or transfer box is incompressible, pouring cement into the corresponding transfer barrel or transfer box to seal it.

[0099] Exemplary, combined Figure 2-Figure 5 as well as Figure 7 The radioactive waste in the transfer barrels or transfer boxes that need to be recycled is first transferred to the temporary storage room for temporary storage.

[0100] like Figure 7 As shown, a compressible transfer barrel or transfer box (such as Figure 7 The 200L barrels of compressible metal waste in the cement plant are compressed by the super press to form compacted barrel cakes and then transported to the preferred area of ​​the cement fixation room by electric hoists. The waste is prepared and packaged in containers ( Figure 7 The 400L empty barrels in the storage room are transported to the cement fixed room, and the compacted barrel cakes after overpressure are loaded into the waste preparation packaging container ( Figure 7 The waste preparation and packaging container is transported to the cement fixing station via a roller conveyor for cement mortar injection and fixing. After the cement mortar is fixed, the waste preparation and packaging container ( Figure 7 The cement fixed steel drums and cement fixed steel boxes) are transported to the packaging container sealing device via a roller conveyor for sealing to form waste bags, thereby completing the final preparation. The prepared waste bags are lifted to the curing room for curing by a lifting device.

[0101] Non-compressible transfer barrels or boxes (such as Figure 7 The 200L barrels of incompressible metal waste) are directly transported to the cement fixing station for cement mortar injection and fixation. The transfer barrel or transfer box after cement mortar fixation is transported to the packaging container sealing device via a roller conveyor for sealing to form a waste package, thus completing the final preparation. The prepared waste package is lifted to the curing room for curing by a lifting device.

[0102] At this point, the recovery and conditioning of radioactive waste is completed.

[0103] The radioactive waste conditioning method provided in this embodiment can be finely classified and processed according to the type of radioactive waste, disassembled waste can be disassembled into disassembly products, and decontaminated metal waste (metal plates, ground-penetrating valve sections, pump cores, etc.) can be cleaned and decontaminated, so that some metal wastes meet the standards for clean release after smelting. Metal wastes that cannot be decontaminated or still do not meet the standards after decontamination can use packaging containers with smaller capacity than the existing technology due to the reduction in total amount and volume, thereby reducing the number of final waste packages and the preparation volume of waste packages, thereby achieving the purpose of reducing disposal costs and improving the level of waste minimization; through the identification code, real-time tracking of each link of the transfer barrel or transfer box can be achieved, so that it is convenient to judge the treatment method of the transfer barrel or transfer box according to the information of the transfer barrel or transfer box, which is convenient for staff to manage the transfer barrel or transfer box and improve the automation level of radioactive waste treatment.

[0104] Embodiment 2:

[0105] An embodiment of the present invention also provides a radioactive waste conditioning system, which is used in a solid waste treatment plant of a post-processing plant, and the radioactive waste includes decomposable waste. The radioactive waste conditioning system includes a disassembly device, a waste detection device, and a recovery and conditioning device. The disassembly device is used to disassemble the decomposable waste in the radioactive waste into disassembly products to reduce the space occupied by the decomposable waste. The waste detection device is used to receive the disassembly products and detect the radioactivity level of the disassembly products. The recovery and conditioning device is used to receive the disassembly products detected in the waste detection device, and according to the radioactivity level and compression characteristics of the disassembly products, respectively recover, condition, or compress and condition the disassembly products.

[0106] Exemplarily, a transfer device is provided between the dismantling device and the waste detection device, and between the waste detection device and the recovery and preparation device, to facilitate the transfer of radioactive waste.

[0107] It is understandable that, usually, the shape of disassembled waste is irregular, the overall size of disassembled waste is large, and it occupies more space. After the disassembled waste is loaded into the transfer barrel or preparation container, the gap between the disassembled waste and the side wall of the preparation container is large. The amount of disassembled waste that can be transported in a transfer barrel or preparation container is limited, which is not conducive to transportation. In addition, the final preparation volume is also large, and the internal filling rate is not high, which is not conducive to waste minimization. After the disassembled waste is disassembled, the size of the disassembled product is smaller and the space occupied is also less. In addition, the gap between the disassembled products and the gap between the disassembled products and the side wall of the transfer barrel or preparation container can be reduced, thereby reducing the space occupied by the disassembled waste after disassembly, which is convenient for subsequent transportation and preparation.

[0108] By setting up a disassembly device, the disassemblyable waste in the radioactive waste can be disassembled into disassembly products. Compared with the disassemblyable waste before disassembly, the gaps between the disassembly products and the gaps between the disassembly products and the side walls of the transfer barrel or preparation container can be reduced, thereby reducing the space occupied by the disassemblyable waste after disassembly, which is convenient for subsequent transportation and preparation; the radioactivity level of the disassembly product is detected by the waste detection device, and the disassembly product is recovered, prepared or compressed and prepared according to the radioactivity level and compression characteristics of the disassembly product by the recovery and preparation device, so that part of the radioactive waste can be recovered, waste can be reduced, and the total amount of radioactive waste that needs to be prepared in the end can be reduced; by compressing and preparing the remaining part of the radioactive waste, the gaps between the radioactive waste that needs to be prepared in the end can be reduced, thereby reducing the volume occupied by the radioactive waste that needs to be prepared in the end, and improving the filling rate of the radioactive waste after preparation, which is conducive to ultimately improving the level of waste minimization.

[0109] In some embodiments, the disassembled waste includes a ventilation filter element, and the ventilation filter element includes a square filter element; the disassembled products are metal plates and filter materials. The disassembly device includes a ventilation filter element disassembly device, and the ventilation filter element disassembly device is used to disassemble the square filter element into a square frame and filter materials, and further decompose the square frame into metal plates.

[0110] Exemplarily, the ventilation filter element disassembly device can spray 50MPa high-pressure water to flush the square filter element, so as to separate the filter material of the square filter element from the square frame; and the ventilation filter element disassembly device can dehydrate and dry the flushed filter material, and disassemble the square frame into metal plates.

[0111] Through the above arrangement, the square filter element can be disassembled into metal plates and filter materials to reduce the space occupied by the square filter element, making it easier to subsequently recover, prepare or compress the metal plates and filter materials.

[0112] In some embodiments, the disassembled waste includes a ground-penetrating valve, and the disassembled product is a ground-penetrating valve segment. The disassembly device includes a ground-penetrating valve disassembly device, which is used to disassemble the ground-penetrating valve into a plurality of ground-penetrating valve segments.

[0113] It is understandable that the ground-penetrating valve is relatively large in size and difficult to transport, recover and maintain, and the ground-penetrating valve section after disassembly is relatively small in size.

[0114] By providing a ground-penetrating valve disassembling device, a longer ground-penetrating valve can be disassembled into several shorter ground-penetrating valve sections, thereby facilitating the subsequent transportation, recovery and preparation of the ground-penetrating valve sections.

[0115] Embodiment 3:

[0116] like Figure 8As shown, an embodiment of the present invention also provides another radioactive waste conditioning system, which is used in a solid waste treatment plant of a post-processing plant. The radioactive waste conditioning system includes a waste receiving device, a waste detection device 1, a waste identification and tracking component and a conditioning device.

[0117] like Figure 8 As shown, the waste receiving device is used to receive a ventilation filter element (or ventilation filter element), barreled metal waste (such as the above-mentioned transfer barrel containing non-disassembled metal waste), a ground-penetrating valve core (or ground-penetrating valve) and a pump core.

[0118] Exemplarily, the waste receiving device includes a roller conveyor, a crane, and a sling. The roller conveyor is used to transport waste packaging containers (e.g., containers containing non-disassembled metal waste, transfer barrels, transfer boxes, etc.), and the crane is used to lift the waste packaging containers and lift the waste packaging containers onto the roller conveyor or the disassembly device. The sling is connected to the crane and is used to lift the waste packaging containers. By replacing different slings, different waste packaging containers can be lifted.

[0119] Exemplarily, the waste detection device 1 includes a radiation probe, which is installed in a waste detection room and is used to detect the radioactivity level of the received waste packaging container. The staff can then determine whether subsequent preparation is required based on the radioactivity level of the waste packaging container.

[0120] The waste identification and tracking component includes a coding device, a waste identification and tracking device 1, a tracking module and a rotating roller. The coding device is arranged at the waste generation end, and the waste identification and tracking device 1 is installed next to the rotating roller. The coding device is arranged at the waste generation end (for example, the tail end of the waste identification and tracking device 1), and can mark the identification code containing the waste packaging container information on the surface of the waste packaging container and upload the coding result to the tracking module. The rotating roller can rotate the waste packaging container with the identification code to reach a position that can be identified by the waste identification and tracking device 1. The waste identification and tracking device 1 and the tracking module can identify the identification code on the waste packaging container, thereby identifying the relevant information of the waste packaging container and uploading it to the tracking module. The tracking module can be a computer running a tracking program, and the tracking module can also control the roller according to the relevant information of the waste packaging container, so as to send the waste packaging container to the corresponding processing link and track the subsequent direction, so as to realize the real-time tracking of the link of the waste packaging container during recycling or preparation.

[0121] The preparation equipment includes an overpressure machine, an electric hoist, cement fixing equipment, a packaging container capping equipment and a crane. The overpressure machine is used to compress the compressible waste packaging container into a compressed barrel cake (or compacted barrel cake), the electric hoist is used to load the compressed barrel cake into a 400L steel drum, and the cement fixing equipment is used to cement fix the 400L steel drum containing the compressed barrel cake and the waste packaging container (such as a steel box) with a pump core. The packaging container capping equipment is used to cap the steel drum and waste packaging container after cement fixation to form the final packaging container cement fixed body. The crane is used to lift the final packaging container cement fixed body to the maintenance area for maintenance.

[0122] In some examples, such as Figure 8 As shown, a filter element disassembling device and a waste identification and tracking device 2 are provided between the waste receiving device and the waste detection device 1. The filter element disassembling device is used to disassemble the ventilation filter element. The waste identification and tracking device 2 has the same function as the waste identification and tracking device 1.

[0123] The filter element disassembly device is provided with filter preparation equipment, high-pressure water flushing equipment and non-metallic waste dehydration equipment. The filter preparation equipment is arranged at the front section of the filter element disassembly device, and is used to remove the screws used to fix the metal frame of the ventilation filter element. The high-pressure water flushing equipment is arranged in the middle section of the filter element disassembly device, and is used to flush the filter material from the metal frame and clean the solid glue used to bond the filter material to the metal frame. The non-metallic waste dehydration equipment is arranged at the lower part of the high-pressure water flushing equipment, and the filter material flushed by high-pressure water is flushed into this equipment for dehydration. After dehydration, the filter material is packaged and sent to the waste detection device 1 for detection. If qualified, it can be temporarily stored and subsequently sent to extremely low-lying landfill. The filter material that fails the detection is sent to the preparation device for subsequent processing.

[0124] In other examples, such as Figure 8 As shown, a ground-penetrating valve disassembly device, a waste detection device 2 and a decontamination device are arranged between the waste receiving device and the waste detection device 1. The ground-penetrating valve disassembly device is used to disassemble the ground-penetrating valve core. The waste detection device 2 is used to detect the radioactivity level of radioactive waste.

[0125] The disassembly device of the ground-penetrating valve is provided with an operating mechanism and a disassembly tool. The operating mechanism is used to realize the long-distance reception of the ground-penetrating valve core. According to the multi-stage structural characteristics of the ground-penetrating valve core, the automatic disengagement of the steel ball buckle mechanism between the middle section of the ground-penetrating valve core and the lower section of the ground-penetrating valve core can be realized through the relative movement of the operating mechanism. The disassembly tool is operated by the staff and can be used to disassemble the axial pin connection between the valve sections, so as to realize the disassembly of the upper section of the ground-penetrating valve core and the middle section of the ground-penetrating valve core. The decontamination device is composed of an ultrasonic-chemical combined decontamination section and a high-pressure water flushing decontamination section. The ultrasonic-chemical combined decontamination section is used for preliminary decontamination of the ground-penetrating valve section and the pump core suitable for decontamination. High-pressure water flushing decontamination is used for secondary decontamination of the ground-penetrating valve section and the pump core after ultrasonic-chemical decontamination. The waste detection device 2 includes a radiation probe, which is installed in the waste treatment hot chamber to perform pre-decontamination detection on the disassembled penetrating valve section and the received pump core, and perform secondary radioactivity level detection on the penetrating valve section and the pump core after decontamination, so as to determine whether the penetrating valve section and the pump core are qualified for decontamination.

[0126] Through the above arrangement, ventilation filter elements (i.e. the ventilation filter elements mentioned above), barreled metal waste (i.e. the transfer barrel containing non-disassembled metal waste mentioned above), ground-penetrating valve cores (i.e. the ground-penetrating valves mentioned above) and pump cores can be classified and processed, thereby improving the level of refined processing of radioactive waste.

[0127] It is to be understood that the above embodiments are merely exemplary embodiments used to illustrate the principles of the present invention, but the present invention is not limited thereto. For those of ordinary skill in the art, various modifications and improvements can be made without departing from the spirit and essence of the present invention, and these modifications and improvements are also considered to be within the scope of protection of the present invention.

Claims

1. A method for conditioning radioactive waste, characterized in that: Radioactive waste includes degradable waste; The preparation method comprises: S1. Disassembling the disassembled waste in the radioactive waste into disassembly products to reduce the space occupied by the disassembled waste; S2. detecting the radioactivity level of the disassembly product; S3. Recover, condition or compress and condition the dismantling products according to the radioactivity level and compression characteristics of the dismantling products.

2. The method for preparing radioactive waste according to claim 1, characterized in that: The disassembled waste includes a ventilation filter element, and the ventilation filter element includes a square filter element; the disassembled products are metal plates and filter materials; The step S1 comprises: The square filter element is disassembled into a square frame and filter material, and the square frame is further decomposed into metal plates.

3. The method for preparing radioactive waste according to claim 2, characterized in that: After step S1 and before step S2, the preparation method further includes: placing the metal plate and the filter material into different transfer barrels respectively; The step S2 specifically includes: detecting the radioactivity level of each transfer barrel; The step S3 specifically includes: according to the relationship between the radioactivity level of each transfer barrel and the preset recovery value, and the compression characteristics of the radioactive waste loaded in the transfer barrel, the radioactive waste loaded in each transfer barrel is recovered, conditioned or compressed and conditioned.

4. The method for preparing radioactive waste according to claim 3, characterized in that: The radioactive waste also includes non-dismantling waste, and the non-dismantling waste includes non-dismantling metal waste; Before the step S2, the preparation method further includes: loading the non-disassembled metal waste into different transfer barrels according to the compression characteristics of the non-disassembled metal waste.

5. The method for preparing radioactive waste according to claim 1, characterized in that: The decomposable waste includes a ground-penetrating valve; the decomposition product is a ground-penetrating valve segment; Then the step S1 specifically includes: Disassembling the ground-penetrating valve into a plurality of ground-penetrating valve sections; The step S2 specifically includes: S21, detecting the radioactivity level of each of the ground-penetrating valve sections, and removing the ground-penetrating valve sections whose radioactivity level is greater than a preset cleaning value; S22, cleaning the remaining ground-penetrating valve sections; S23, detecting the radioactivity level of the cleaned through-the-ground valve section; S24, classifying the cleaned penetrating valve section into a recoverable penetrating valve section and a penetrating valve section requiring maintenance according to the relationship between the radioactivity level of the cleaned penetrating valve section and a preset recovery value; S25. Place the ground-penetrating valve sections whose radioactivity levels are greater than the preset cleaning value and the ground-penetrating valve sections that need to be repaired into the same transfer barrel, and place the recoverable ground-penetrating valve sections into another transfer barrel; the radioactivity level of the ground-penetrating valve sections placed in each transfer barrel is used as the radioactivity level of the corresponding transfer barrel.

6. The method for preparing radioactive waste according to claim 5, characterized in that: Radioactive waste also includes non-dismantling waste, which includes pump cores; The step S21 further comprises: detecting the radioactivity level of each pump core, and removing the pump core whose radioactivity level is greater than a preset cleaning value; The step S22 further includes: cleaning the remaining pump cores; The step S23 further comprises: detecting the radioactivity level of the pump core after cleaning; The step S24 further includes: classifying the cleaned pump core into a recyclable pump core and a pump core to be repaired according to the relationship between the radioactivity level of the cleaned pump core and the preset recycling value; The step S25 further includes: placing the pump cores with radioactivity levels greater than the preset cleaning value and the pump cores to be conditioned into the same transfer box, and placing the recyclable pump cores into another transfer box; and taking the radioactivity level of the pump cores in each transfer box as the radioactivity level of the corresponding transfer box; The step S3 also includes: according to the relationship between the radioactivity level of each transfer box and the preset recovery value, and the compression characteristics of the radioactive waste loaded in the transfer box, the radioactive waste loaded in each transfer box is recycled, conditioned or compressed and conditioned.

7. The method for conditioning radioactive waste according to claim 3, 4 or 6, characterized in that: After step S2 and before step S3, the preparation method further includes: According to the radioactivity level of each transfer barrel or transfer box obtained by detection, and the compression characteristics of the radioactive waste loaded in the transfer barrel or transfer box, adding a corresponding identification code to each transfer barrel or transfer box; The identification code on each transfer barrel or transfer box is read to obtain the radioactivity level of the corresponding transfer barrel or transfer box, and the compression characteristics of the radioactive waste loaded in the transfer barrel or transfer box.

8. The method for conditioning radioactive waste according to claim 3, 4 or 6, characterized in that: The step S3 is specifically as follows: Comparing the radioactivity level of each transfer barrel or transfer box with the recovery preset value, and obtaining a comparison result; If the radioactivity level of the transfer barrel or the transfer box is less than or equal to a preset recycling value, the radioactive waste in the transfer barrel or the transfer box is recycled; If the radioactivity level of the transfer barrel or the transfer box is greater than the preset recycling value, and the radioactive waste in the transfer barrel or the transfer box is compressible, compress the corresponding transfer barrel or the transfer box and put it into the waste preparation packaging container, and pour cement into the waste preparation packaging container for sealing; If the radioactivity level of the transfer barrel or the transfer box is greater than the preset recycling value, and the radioactive waste in the transfer barrel or the transfer box is incompressible, cement is poured into the corresponding transfer barrel or the transfer box for sealing.

9. A radioactive waste conditioning system, characterized in that: Radioactive waste includes degradable waste; The radioactive waste conditioning system includes: A disassembly device, used for disassembling the disassemblyable waste in the radioactive waste into disassembly products, so as to reduce the space occupied by the disassemblyable waste; a waste detection device, used for receiving the dismantling products and detecting the radioactivity level of the dismantling products; and, The recovery and conditioning device is used to receive the dismantling products detected by the waste detection device, and then recover, condition or compress and condition the dismantling products according to the radioactivity level and compression characteristics of the dismantling products.

10. The radioactive waste conditioning system according to claim 9, characterized in that: The disassembled waste includes a ventilation filter element, and the ventilation filter element includes a square filter element; the disassembled products are metal plates and filter materials; The disassembling device comprises a ventilation filter element disassembling device, and the ventilation filter element disassembling device is used to disassemble the square filter element into a square frame and filter material, and further decompose the square frame into metal plates; or, The decomposable waste includes a ground-penetrating valve; the decomposition product is a ground-penetrating valve segment; The disassembling device comprises a ground-penetrating valve disassembling device, and the ground-penetrating valve disassembling device is used to disassemble the ground-penetrating valve into a plurality of ground-penetrating valve sections.

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