A method for preparing a waste source for disposal at the earth's surface

Abstract

The application provides a waste source near-surface disposal preparation method, which comprises the following steps: obtaining waste sources to be prepared; detecting the obtained waste sources to obtain the activity of the waste sources; performing packaging tube filling treatment on the waste sources according to the activity of the waste sources; performing packaging treatment on the waste source-filled packaging tubes; performing welding treatment on the packaging tubes after the packaging treatment; and performing preparation treatment on the packaging tubes after the welding treatment to obtain waste packages. The scheme can realize the disposal preparation of waste sources near the surface, reduce the storage risk of the waste sources, and ensure the long-term safety of the storage of the waste sources.

Description

Technical Field

[0001] This invention relates to the field of near-surface waste treatment technology, and in particular to a near-surface waste treatment preparation method. Background Technology

[0002] Waste radioactive sources are mainly managed through local temporary storage and centralized storage, with a large amount stored in national centralized waste source storage facilities. Waste source disposal is the ultimate way to ensure the long-term safety of waste sources. At the same time, waste source disposal is of great significance in reducing the risks of waste source storage, and is more conducive to resource conservation and environmental friendliness, thus having environmental and social benefits. However, there are currently no relevant methods for near-surface disposal and preparation of waste sources. Summary of the Invention

[0003] This invention provides a method for near-surface disposal and preparation of waste sources, which can realize near-surface disposal and preparation of waste sources, reduce the risk of waste source storage, and ensure the long-term safety of waste source storage.

[0004] To solve the above-mentioned technical problems, the technical solution of the present invention is as follows:

[0005] A method for near-surface disposal and preparation of waste sources includes:

[0006] Acquire the waste source to be prepared;

[0007] The acquired waste sources are tested to obtain their activity levels.

[0008] Waste sources are encapsulated and filled into tubes based on their activity level.

[0009] The encapsulation tube containing waste source is encapsulated.

[0010] The encapsulated tubes that have undergone the encapsulation process are then soldered.

[0011] The packaged tubes that have undergone welding are then prepared to obtain waste packages.

[0012] Optionally, the waste source to be prepared is retrieved from the storage pit and packaged into lead containers inside a negative pressure glove box.

[0013] Optionally, the near-surface treatment preparation method for waste sources further includes:

[0014] Before testing the waste source, leakage prevention measures are taken.

[0015] Optionally, leakage prevention measures may be implemented on the acquired waste source, including:

[0016] The acquired waste source is placed in a liquid membrane container inside the negative pressure glove box, so that the waste source is soaked in the liquid membrane.

[0017] Wrap aluminum foil around the waste source that has been dipped in the liquid film;

[0018] The waste source wrapped in aluminum foil is placed in a tray inside the negative pressure glove box to complete the leak prevention treatment.

[0019] Optionally, the acquired waste source is tested to obtain its activity, including:

[0020] The obtained waste sources are subjected to nuclide classification to obtain the nuclide categories of the waste sources;

[0021] The activity of the waste source is obtained by detecting the nuclide type of the waste source.

[0022] Optionally, the activity of the waste source can be obtained by detecting the nuclide category of the waste source, including:

[0023] The gamma dose rate of the waste source with the nuclide category of gamma source is detected by gamma spectrometer, and the activity of the waste source with the nuclide category of gamma source is obtained based on the gamma dose.

[0024] The activity of waste sources of the α or β nuclide category is obtained by detecting the detection count of waste sources using a surface contamination monitor.

[0025] Optionally, the waste source may be subjected to encapsulation tube filling treatment based on its activity, including:

[0026] If the activity of the waste source meets the encapsulation activity requirements, the waste source is placed in the lower source pipe on the bottom surface of the negative pressure glove box using a clamp, and the waste source is introduced into the encapsulation tube through the lower source pipe.

[0027] Optionally, the encapsulation tube containing the waste source is encapsulated, including:

[0028] The limiter is placed inside the encapsulation tube to limit and fix the waste source inside the encapsulation tube;

[0029] Cement is poured into the encapsulation pipe using a cement pouring device until the pouring is completed.

[0030] Place the cap on the upper opening of the encapsulation tube to complete the encapsulation of the encapsulation tube.

[0031] Optionally, the encapsulated tube undergoes soldering, including:

[0032] The encapsulated tube, after being encapsulated, is fixed to the welding position of the welding device. The welding device is then used to weld the encapsulated tube to the cover, thus completing the welding process of the encapsulated tube.

[0033] Optionally, the packaged tubes that have undergone welding are prepared to obtain a waste package, including:

[0034] Arrange the welded and packaged tubes inside the packaging container;

[0035] The grout is poured into the packaging container to form a waste bag.

[0036] The above-described solution of the present invention has at least the following beneficial effects:

[0037] The above-described solution of the present invention, by acquiring the waste source to be prepared; detecting the acquired waste source to obtain its activity; filling the waste source with a packaging tube according to its activity; packaging the packaging tube filled with the waste source; welding the packaged tube after packaging; and preparing the packaged tube after welding to obtain a waste package, can realize the near-surface disposal and preparation of waste sources, reduce the risk of waste source storage, and ensure the long-term safety of waste source storage. Attached Figure Description

[0038] Figure 1 This is a flowchart of a near-surface waste disposal preparation method provided in an embodiment of the present invention;

[0039] Figure 2 A schematic diagram of the internal layout structure of the negative pressure glove box of the present invention;

[0040] Figure 3 A schematic diagram of the sealing cap of the present invention;

[0041] Figure 4 A schematic diagram of the limiter of the present invention. Detailed Implementation

[0042] Exemplary embodiments of the invention will now be described in more detail with reference to the accompanying drawings. While exemplary embodiments of the invention are shown in the drawings, it should be understood that the invention may be implemented in various forms and should not be limited to the embodiments set forth herein. Rather, these embodiments are provided so that this invention will be thorough and complete, and will fully convey the scope of the invention to those skilled in the art.

[0043] like Figure 1 As shown, an embodiment of the present invention proposes a near-surface treatment preparation method for waste sources, comprising:

[0044] Step 11, obtain the waste source to be prepared;

[0045] Step 12: Detect the obtained waste source to obtain the activity of the waste source;

[0046] Step 13: Fill the waste source with the encapsulation tube 40 according to the activity of the waste source;

[0047] Step 14: Seal the encapsulation tube 40 containing the waste source;

[0048] Step 15: Perform welding on the encapsulation tube 40 after the encapsulation process is completed;

[0049] Step 16: Prepare the encapsulated tube 40 after welding to obtain a waste package.

[0050] In this embodiment, the waste source to be prepared is obtained; the obtained waste source is tested to obtain the activity of the waste source; the waste source is filled into a packaging tube 40 according to the activity of the waste source; the packaging tube 40 filled with waste source is packaged; the packaging tube 40 after the packaging process is welded; and the packaged tube 40 after the welding process is prepared to obtain a waste package; this can realize the near-surface disposal and preparation of waste source, reduce the risk of waste source storage, and ensure the long-term safety of waste source storage.

[0051] In an optional embodiment of the present invention, the waste source to be prepared is a lead container 21 retrieved from the storage pit and packaged in a negative pressure glove box 20.

[0052] In this embodiment, waste sources are retrieved from the centralized storage facility to the operating room. During the retrieval process, clear division of labor is required, including on-site command, radiation monitoring personnel, crane operators, and rigging personnel. Anti-pollution mulch is laid around the waste source retrieval area, personnel access areas, and waste source container placement areas. Before operation, the facility must be ventilated for 30 minutes to remove accumulated radon and other radioactive gases and dust. All personnel must wear full protective gear. The cover plate is hung on the lifting equipment, slowly lifted, and placed on the mulch-covered ground. Personnel should stay as far away from the cover plate as possible. Radiation monitoring personnel should monitor the area thoroughly. The open gap is measured from all directions; radiation monitoring personnel observe and monitor the pit, and after confirming safety, the workers approach the pit opening and use retrieval tools to quickly retrieve the waste source steel box or container; a gantry crane is used to lift the target waste source steel box or container to the receiving area at the entrance of the operating room, and non-target waste source steel boxes or containers are placed in the waste source container placement area and returned after retrieval; for steel boxes or containers corresponding to the waste source to be sealed by the same sealing tube, all should be retrieved in one retrieval activity; depending on the weight of the waste source steel box or container, the waste source steel box or container is transferred to the dismantling workshop by manual labor or forklift;

[0053] Waste source container re-retrieval pollution monitoring: For carbon steel box packaging containers, use professional cutting tools to remove the sealed top cover of the carbon steel box, identify and select waste source packaging containers and monitor their re-retrieval; repeat this step until there are no waste source containers to be disposed of in this project inside the steel box; for steel boxes that still contain waste source containers that will not be disposed of after re-retrieval, reseal the steel box and put it back into the original re-retrieval pit; for steel boxes that have no target waste source containers after re-retrieval, decontaminate and temporarily store the steel boxes; for the re-retrieved waste source containers, use the wiping method to indirectly measure the surface pollution of the container, and if there is surface pollution, perform surface decontamination until the loose surface pollution is removed;

[0054] For waste source container pretreatment, remove the parts used to bind and fix the container, and use rust remover and lubricant as needed to assist in removing bolts and loose lead plugs until the container can be opened normally. For containers that are too heavy or too big to be directly put into the negative pressure glove box 20, use radiation-resistant endoscopes and various types of clamps to load the radioactive source into the lead container 21 in batches, and then transfer the lead container 21 to the negative pressure glove box 20. During the dispensing operation, personnel should wear lead aprons and use protective lead bricks or lead glass for shielding as appropriate.

[0055] Through the above process, the waste source to be prepared is retrieved from the storage pit and distributed into lead containers 21 inside the negative pressure glove box 20. This facilitates the identification and filling of the waste source inside the negative pressure glove box 20, and avoids operators from directly looking at the waste source when identifying and filling it, thus preventing an increase in the radiation dose to the operators.

[0056] In an optional embodiment of the present invention, such as Figure 2 The diagram shows the internal layout of the negative pressure glove box 20. The tool tray 27 inside the negative pressure glove box 20 is equipped with a clamp for picking up waste sources. The display part of the endoscope 23 is located outside the negative pressure glove box 20, and the probe 231 of the endoscope 23 corresponds to the inside of the lead container 21.

[0057] The location of the waste source inside the lead container 21 is obtained by the endoscope 23 inside the negative pressure glove box 20, and the waste source inside the lead container 21 is picked up by the clamps of the endoscope 23. This makes it easy for operators to accurately pick up the waste source inside the lead container 21. The operation is simple and convenient, which helps to improve the operation efficiency and helps to avoid increasing the radiation dose to the operators.

[0058] In an optional embodiment of the present invention, the near-surface treatment preparation method for waste sources further includes:

[0059] Step 120: Before testing the acquired waste source, perform leak prevention treatment on the acquired waste source.

[0060] Further, step 120 includes:

[0061] Step 1201: Place the acquired waste source into the liquid membrane container 24 inside the negative pressure glove box 20, so that the waste source is soaked in the liquid membrane.

[0062] Step 1202: Wrap aluminum foil around the waste source that has been dipped in the liquid film;

[0063] Step 1203: Place the waste source wrapped in aluminum foil into the tray 25 inside the negative pressure glove box 20 to complete the leak prevention treatment.

[0064] In this embodiment, the acquired waste source is placed in the liquid membrane container 24, allowing the waste source to absorb the liquid membrane. The liquid membrane forms a protective film on the surface of the waste source, and aluminum foil is wrapped around the outside of the waste source to complete the leak prevention treatment of the waste source. This can prevent the waste source from being damaged and radioactive contamination from leaking. The position of the tray 25 is observed with the reflector 22 inside the negative pressure glove box 20. The waste source wrapped with aluminum foil is placed in the tray 25 inside the negative pressure glove box 20, which facilitates the subsequent identification of the waste source.

[0065] In an optional embodiment of the present invention, step 12 includes:

[0066] Step 121: Identify the nuclide categories of the acquired waste sources to obtain the nuclide categories of the waste sources;

[0067] Step 122: Detect the waste source according to the nuclide category to obtain the activity of the waste source.

[0068] Further, step 122 includes:

[0069] Step 1221: Detect the γ dose rate of the waste source with the γ nuclide category 29 using a γ spectrometer 29, and obtain the activity of the waste source with the γ nuclide category based on the γ dose.

[0070] Step 1222: Detect the detection count of waste sources with nuclide category α or β using surface contamination monitor 28, and obtain the activity of waste sources with nuclide category α or β based on the detection count.

[0071] In this embodiment, the waste source in the tray 25 is detected and analyzed by the gamma spectrometer 29 to obtain the nuclide category of the waste source, wherein the nuclide category includes gamma source, alpha source and beta source; by identifying the nuclide category of the waste source, it is convenient to perform corresponding detection according to the nuclide category of the waste source in order to obtain the activity of the waste source.

[0072] When the radionuclide category of the waste source is γ source, the γ spectrometer 29 is moved to one side of the lead brick 26, so that the γ spectrometer 29 and the tray 25 are located on both sides of the lead brick 26, and the detection distance between the γ spectrometer 29 and the waste source with the radionuclide category of γ source is 30cm; the γ dose rate of the waste source with the radionuclide category of γ source is measured by the γ spectrometer 29.

[0073] pass The activity of a waste source with the nuclide category γ source is obtained; where A represents the activity (Bq); Γk represents the γ dose rate (μSv / h); Γk represents the air kerma rate constant (Gy·m). 2 ·Bq -1 ·s -1 ); d1 represents the thickness of the lead brick; d f1This refers to the half-shielding thickness of the shielding material for the nuclide; for waste sources of the γ-ray source type, taking Co-60 and Cs-137 sources as examples, the d of Co-60... f1 The value is 1.2cm; d of Cs-137 f1 The value is 0.65cm;

[0074] When the radionuclide category of the waste source is α source or β source, the surface contamination monitor 28 is brought close to the α source or β source for detection, and the distance between the surface contamination monitor 28 and the α source or β source waste source is 5mm; the detection count of the α source or β source waste source is detected by the surface contamination monitor 28.

[0075] pass The activity of a waste source of α or β nuclide type is obtained; where A represents activity (Bq); Count represents detection count (cps); S1 represents effective source area; S0 represents instrument detection area; η represents instrument detection efficiency; taking Sr-90 source as an example, the η value of α source is 0.51; the η value of β source is 0.62.

[0076] The above process enables rapid identification of the nuclide type of the waste source, and the waste source is then tested based on the nuclide type to obtain its activity.

[0077] In an optional embodiment of the present invention, step 13 includes:

[0078] If the activity of the waste source meets the encapsulation activity requirements, the waste source is placed in the lower source pipe 201 on the bottom surface of the negative pressure glove box 20 using a clamp, and the waste source is introduced into the encapsulation tube 40 through the lower source pipe 201.

[0079] In this embodiment, before operation, the encapsulation tube 40 is placed inside the shielding container below the negative pressure glove box 20, and the upper opening of the encapsulation tube 40 corresponds to the lower source pipe 201 on the bottom surface of the negative pressure glove box 20.

[0080] If the activity of the waste source meets the encapsulation activity requirements, the waste source is placed in the lower source pipe 201 on the bottom surface of the negative pressure glove box 20 by a clamp, and the waste source is introduced into the encapsulation tube 40 through the lower source pipe 201 to realize the filling of the waste source.

[0081] When the cumulative activity reaches the single nuclide encapsulation limit or the dose level on the surface of the lead can 21 detected by the gamma spectrometer 29 is close to 2 mSv / h, stop filling the waste source and gently shake the encapsulation tube 40 to make the waste source stack more compact.

[0082] If the inactivity of the waste source meets the encapsulation activity requirements, the waste source is temporarily stored in a temporary shielded container inside the negative pressure glove box 20. After other waste sources whose activities meet the encapsulation activity requirements are filled, the waste sources whose activities do not meet the encapsulation activity requirements are transferred back to the centralized container for storage.

[0083] In an optional embodiment of the present invention, step 14 includes:

[0084] Step 141: Place the limiter 36 inside the encapsulation tube 40 to limit and fix the waste source inside the encapsulation tube 40.

[0085] Step 142: Cement is poured into the encapsulation pipe 40 using a cement pouring device until the pouring is completed;

[0086] Step 143: Place the cover on the upper opening of the encapsulation tube 40 to complete the encapsulation of the encapsulation tube 40.

[0087] In this embodiment, such as Figure 4 As shown, the limiter 36 has a vortex-shaped structure formed by an elastic strip. When the limiter 36 is placed in the encapsulation tube 40, its elasticity allows it to fully contact the inner wall of the encapsulation tube 40, ensuring its stability within the tube. Since the waste source is wrapped in aluminum foil, its overall density is less than that of cement, making it prone to floating during pouring and affecting the encapsulation effect. The limiter 36 can limit and fix the waste source inside the encapsulation tube 40, preventing it from floating during cement injection and affecting the encapsulation effect. The vortex-shaped structure creates gaps on the surface of the limiter 36 that allow cement to pass through, facilitating contact between cement and the waste source and ensuring the encapsulation effect.

[0088] like Figure 3As shown, the cement pouring device includes: a peristaltic pump, the inlet of which is connected to a cement storage tank via a suction pipe, and the outlet of which is connected to an injection pipe 30. The control switch for the peristaltic pump is located near the outlet of the injection pipe 30; a sealing cap 31, the inner diameter of which is adapted to the outer diameter of the sealing tube 40, the sealing cap 31 being connected to the injection pipe 30, the outlet of which penetrates the upper surface of the sealing cap 31 and extends into the interior of the sealing cap 31; and a lifting ring 32 located inside the sealing cap 31. The outlet end of the injection tube 30 passes through the central hole of the lifting ring 32; it also passes through at least one guide hole 34 disposed on the upper surface of the sealing cover 31; a lifting rod 33 is slidably disposed inside the at least one guide hole 34, the bottom end of the lifting rod 33 is connected to the lifting ring 32, and the upper end of the lifting rod 33 is connected to a limiting block 35; when the sealing cover 31 is fitted onto the upper end port of the encapsulation tube 40, under the gravity of the lifting ring 32, the limiting block 35 abuts against the upper surface of the sealing cover 31, and the distance between the lifting ring 32 and the upper end port of the encapsulation tube 40 is a preset distance;

[0089] When pouring cement, when the sealing cap 31 is fitted onto the upper opening of the sealing tube 40, the limiting block 35 abuts against the upper surface of the sealing cap 31 under gravity. At this time, the distance between the lifting ring 32 and the upper opening of the sealing tube 40 is a preset distance. The peristaltic pump operates, injecting cement from the cement storage tank into the sealing tube 40 through the suction pipe and injection pipe 30. As the cement is injected, when the cement comes into contact with the lifting ring 32, the lifting ring 32, under the pushing action of the cement, drives the limiting block 35 to rise through the lifting rod 33, causing the limiting block 35 to detach from the upper surface of the sealing cap 31. At this point, it can be determined that the distance between the cement surface inside the sealing tube 40 and the upper opening of the sealing tube 40 has reached the preset distance, and the cement pouring stops. The injected cement is an ultrafine cement slurry with a water-to-material ratio of 0.3. The preset distance can be 1 cm. The cement pouring device achieves automatic cement pouring, avoiding operators getting too close to the sealing tube 40 and increasing the radiation dose to the operators. The sealing cap 31 is used to... The upper opening of the sealing tube 40 is blocked, and the injection tube 30 extends into the sealing tube 40 to inject cement. This effectively prevents cement residue from remaining at the upper opening of the sealing tube 40, ensuring accurate contact between the cap and the sealing tube 40 and improving the welding effect. By setting a preset distance, and ensuring that the distance between the cement surface inside the sealing tube 40 and the upper opening of the sealing tube 40 reaches the preset distance, the pouring is completed. This ensures the sealing effect of the cement on the waste source while reserving space for the installation of the cap and the sealing tube 40, ensuring full contact between the cap and the sealing tube 40 and improving the welding effect. The lifting ring 32 drives the lifting rod 33 and the limiting block 35 to rise under the pushing action of the cement. By checking whether the limiting block 35 is disengaged from the sealing cap 31, it is determined whether the distance between the cement surface inside the sealing tube 40 and the upper opening of the sealing tube 40 reaches the preset distance. The judgment method is simple and clear, which can improve the accuracy of the preset distance control.

[0090] After pouring is completed, disconnect the sealing cap 31 from the encapsulation tube 40, clean the upper opening of the encapsulation tube 40 and the outer surface of the encapsulation tube 40 to avoid cement residue; let stand until the cement inside the encapsulation tube 40 initially sets, then place the cap on the upper opening of the encapsulation tube 40 to complete the encapsulation of the encapsulation tube 40.

[0091] In an optional embodiment of the present invention, step 15 includes:

[0092] The encapsulated tube 40, after being encapsulated, is fixed to the welding position of the welding device. The encapsulated tube 40 is then welded to the cover using the welding device, thus completing the welding process of the encapsulated tube 40.

[0093] In this embodiment, the welding device includes a welding robot and a rotating platform, wherein the surface of the rotating platform is provided with a three-jaw chuck for fixing the encapsulation tube 40;

[0094] The encapsulation tube 40 is placed on a three-jaw chuck using a clamping tool, and the encapsulation tube 40 is clamped and fixed by the three-jaw chuck. The rotating platform drives the three-jaw chuck to rotate, and the welding robot performs the welding connection between the cover and the encapsulation tube 40. The welding connection between the cover and the encapsulation tube 40 is located on the outer side of the encapsulation tube 40. During the welding process, the outer surface of the cover can be heated evenly, which can effectively prevent the cover from warping and deforming due to uneven heating, and ensure the welding effect and sealing of the cover and the encapsulation tube 40.

[0095] After the welding of the cap and the encapsulation tube 40 is completed, the encapsulation tube 40 is tested for leaks using the vacuum leak detection method to ensure the weld seal between the cap and the encapsulation tube 40. The encapsulation tube 40 with qualified weld seals is placed in a temporary shielding container and transferred to the cement hopper area to await subsequent processing. The encapsulation tube 40 with unqualified weld seals is removed, cleaned, and then welded and leak tested again until the weld seal is qualified.

[0096] In an optional embodiment of the present invention, step 16 includes:

[0097] Step 161: Arrange 40 rows of the completed welding tubes inside the packaging container;

[0098] Step 162: Pour the grout into the packaging container to form a waste bag.

[0099] In this embodiment, a 200L flanged steel drum is selected as the packaging container for the sealing tube 40. The flanged steel drum is placed in the cement filling area, and the fixing bracket for fixing the sealing tube 40 is placed inside the flanged steel drum. The sealing tube 40 is then placed inside the fixing bracket, completing the arrangement of the sealing tube 40. The arrangement position is determined according to the nuclide type, activity, and surface dose rate of different sealing tubes 40. For example, sealing tubes 40 with high surface dose rates are arranged on the inner side, and sealing tubes 40 with low surface dose rates are arranged on the outer side to meet the acceptance limit of the surface dose rate of waste bags in the disposal site. When arranging the sealing tubes 40, the minimum spacing between the sealing tubes 40 at the same height should be greater than 10cm.

[0100] High-strength, non-shrink grout is poured into the flanged steel drum to complete the casting and fixation of the sealing tube 40 inside the drum, forming a waste bag. During pouring, the filling rate of the flanged steel drum should be no less than 90%, and the container should be filled as completely as possible. The maximum dose rate at any point on the outer surface of the flanged steel drum should be ≤2 mSv / h under manual operation conditions and ≤20 mSv / h under remote operation conditions. The surface radioactive non-fixed contamination of the flanged steel drum should meet the following requirements: α < 0.4 Bq / cm², β < 4 Bq / cm². If the surface radioactive non-fixed contamination of the flanged steel drum exceeds the above indicators, the contaminated drum should be decontaminated until the above indicators are met. The surface must be marked with conspicuous, clear, water-resistant, and long-lasting labels, including: serial number, radioactivity symbol, etc. Waste packages must be accompanied by official documentation, which must include (no less than) the following information about the waste source and waste package: type and serial number of the encapsulation tube; the storage unit, serial number, nuclide, activity, and calibration time of the waste source within the encapsulation tube; quantity of waste source; waste package number; weight of the waste package, volume of contents, types of nuclides and their total activity, measurement method, and measurement date; type and characteristics of the packaging container: dimensions, volume, material, and quality certification materials; surface dose rate and measurement date; surface contamination level and measurement date; signature and date of the person in charge of the waste package generating unit; and date of disposal.

[0101] Near-surface disposal preparation process for waste sources:

[0102] Obtain the waste source to be prepared: retrieve the waste source to be prepared from the storage pit and pack it into lead cans 21. Transfer the lead cans 21 containing the waste source into the negative pressure glove box 20. Use the endoscope 23 inside the negative pressure glove box 20 to collect the location of the waste source inside the lead can 21. Use the clamps of the endoscope 23 to pick up the waste source inside the lead can 21.

[0103] Leakage prevention treatment: The acquired waste source is placed in the liquid film container 24 inside the negative pressure glove box 20, allowing the waste source to absorb the liquid film. The liquid film forms a protective film on the surface of the waste source, and aluminum foil is wrapped around the outside of the waste source to complete the leakage prevention treatment. This can prevent the waste source from being damaged and radioactive contamination from leaking out. The position of the tray 25 is observed with the reflector 22 inside the negative pressure glove box 20. The waste source wrapped with aluminum foil is placed in the tray 25 inside the negative pressure glove box 20 to facilitate subsequent identification of the waste source.

[0104] The activity of the waste source is obtained by detecting the waste source: the waste source in the tray 25 is detected and analyzed by the gamma spectrometer 29 to obtain the nuclide category of the waste source, wherein the nuclide category includes gamma source, alpha source and beta source; when the nuclide category of the waste source is gamma source, the gamma spectrometer 29 is moved to one side of the lead brick 26, so that the gamma spectrometer 29 and the tray 25 are located on both sides of the lead brick 26, and the detection distance between the gamma spectrometer 29 and the waste source with the nuclide category of gamma source is 30cm; the gamma dose rate of the waste source with the nuclide category of gamma source is measured by the gamma spectrometer 29; and the activity of the waste source with the nuclide category of gamma source is obtained by A= The activity of the waste source with a nuclide class of γ source is obtained; when the nuclide class of the waste source is α source or β source, the surface contamination monitor 28 is brought close to the α source or β source for detection, and the distance between the surface contamination monitor 28 and the waste source of α source or β source is 5 mm; the detection count of the waste source of α source or β source is detected by the surface contamination monitor 28; through The activity of waste sources with nuclide class α or β is obtained;

[0105] Filling process: If the activity of the waste source meets the encapsulation activity requirements, the waste source is placed in the lower source pipe 201 on the bottom surface of the negative pressure glove box 20 using a clamp, and the waste source is introduced into the encapsulation tube 40 through the lower source pipe 201 to realize the filling of the waste source; when the cumulative activity reaches the single nuclide encapsulation limit or the dose level on the surface of the lead can 21 detected by the gamma spectrometer 29 is close to 2 mSv / h, the filling of the waste source is stopped, and the encapsulation tube 40 is slightly shaken to make the waste source stack more compact; if the inactivity of the waste source meets the encapsulation activity requirements, the waste source is temporarily stored in the temporary storage shielded container in the negative pressure glove box 20. After other waste sources whose activities meet the encapsulation activity requirements are filled, the waste sources whose activities do not meet the encapsulation activity requirements are transferred back to the centralized container for storage;

[0106] Encapsulation process: Place the limiter 36 inside the encapsulation tube 40 to limit and fix the waste source inside the encapsulation tube 40; pour cement into the encapsulation tube 40 using a cement pouring device until the pouring is completed; place the cover at the upper opening of the encapsulation tube 40 to complete the encapsulation of the encapsulation tube 40.

[0107] Welding process: Fix the encapsulated tube 40, which has been encapsulated, to the welding position of the welding device, and weld the encapsulated tube 40 to the cover body through the welding device to complete the welding process of the encapsulated tube 40.

[0108] Preparation and processing to obtain waste bags: 40 rows of welded and packaged tubes are arranged inside the packaging container; grout is poured into the packaging container to form waste bags.

[0109] The above process enables the near-surface treatment and preparation of waste sources, reduces the risks of waste source storage, and ensures the long-term safety of waste source storage.

[0110] The above description represents the preferred embodiments of the present invention. It should be noted that those skilled in the art can make various improvements and modifications without departing from the principles of the present invention, and these improvements and modifications should also be considered within the scope of protection of the present invention.

Claims

1. A method for near-surface treatment and preparation of waste sources, characterized in that, include: Acquire the waste source to be prepared; The acquired waste sources are tested to obtain their activity levels. Waste sources are encapsulated and filled into tubes based on their activity level. The encapsulation tube containing waste source is encapsulated. The encapsulated tubes that have undergone the encapsulation process are then soldered. The packaged tubes that have undergone welding are then processed to obtain waste packages. The acquired waste sources are tested to obtain their activity, including: The acquired waste sources are identified by their nuclide categories to obtain the nuclide categories of the waste sources; specifically, the waste sources in the tray are detected and analyzed by a gamma spectrometer to obtain the nuclide categories of the waste sources, wherein the nuclide categories include gamma sources, alpha sources and beta sources; The activity of the waste source is obtained by detecting the nuclide type of the waste source. The activity of the waste source is obtained by detecting the nuclide type of the waste source, including: The gamma dose rate of the waste source with the nuclide category of gamma source is detected by gamma spectrometer, and the activity of the waste source with the nuclide category of gamma source is obtained based on the gamma dose. Specifically, when the radionuclide category of the waste source is γ source, the γ spectrometer is moved to one side of the lead brick, so that the γ spectrometer and the tray are located on both sides of the lead brick, and the detection distance between the γ spectrometer and the waste source with the radionuclide category of γ source is 30cm; the γ dose rate of the waste source with the radionuclide category of γ source is measured by the γ spectrometer. pass The activity of a waste source with the nuclide category γ source is obtained; where A represents activity and Bq; Γk represents the γ dose rate, μSv / h; Γk represents the air kerma rate constant, Gy·m 2 ·Bq -1 ·s -1 d1 represents the thickness of the lead brick; d f1 The shielding material represents the semi-shielding thickness of the nuclide; the nuclide type is γ-ray source, and the waste source is Co-60 source. f1 The value is 1.2 cm; the nuclide type is γ source, and the waste source is Cs-137 source d. f1 The value is 0.65cm; The activity of waste sources of radionuclide type α or β is obtained by detecting the detection count of waste sources with radionuclide type α or β using a surface contamination monitor. Specifically, when the radionuclide category of the waste source is α source or β source, the surface contamination monitor is brought close to the α source or β source for detection, and the distance between the surface contamination monitor and the α source or β source waste source is 5mm; the detection count of the α source or β source waste source is detected by the surface contamination monitor; pass The activity of a waste source with nuclide type α or β is obtained; where A represents activity, Bq; Count represents detection count, cps; S1 represents effective source area; S0 represents instrument detection area; η represents instrument detection efficiency; η is 0.51 for nuclide type α source; and η is 0.62 for nuclide type β source. The encapsulation process for the packaging tube filled with waste source includes: The limiter is placed inside the encapsulation tube. The limiter is a vortex-shaped structure formed by an elastic strip, which is in full contact with the inner wall of the encapsulation tube to limit and fix the waste source inside the encapsulation tube. Cement is poured into the encapsulation tube using a cement pouring device until the pouring is complete. Specifically, a sealing cap is fitted onto the upper opening of the encapsulation tube. Under gravity, the limiting block abuts against the upper surface of the sealing cap, and the distance between the lifting ring and the upper opening of the encapsulation tube is a preset distance. A peristaltic pump operates, injecting cement from the cement storage tank into the encapsulation tube through a suction pipe and an injection pipe. When the cement comes into contact with the lifting ring, the lifting ring, driven by the cement, raises the limiting block via a lifting rod, causing the limiting block to detach from the upper surface of the sealing cap. This indicates that the distance between the cement surface inside the encapsulation tube and the upper opening of the encapsulation tube has reached the preset distance, at which point the cement pouring stops. Place the cap on the upper opening of the encapsulation tube to complete the encapsulation of the encapsulation tube; The process of soldering the encapsulated tube after it has been encapsulated includes: The encapsulated tube, after the encapsulation process is completed, is fixed to the welding position of the welding device. The welding device then welds the encapsulated tube to the cover, completing the welding process of the encapsulated tube. Specifically, the encapsulated tube is placed on a three-jaw chuck using a clamping tool, and the three-jaw chuck clamps and fixes the encapsulated tube. The rotating platform drives the three-jaw chuck to rotate, and the welding robot then welds the cover to the encapsulated tube. The welding connection between the cover and the encapsulated tube is located on the outer side of the encapsulated tube.

2. The near-surface treatment and preparation method for waste sources according to claim 1, characterized in that, The waste source to be prepared is lead cans retrieved from the storage pit and packaged in negative pressure glove boxes.

3. The near-surface treatment and preparation method for waste sources according to claim 1, characterized in that, Also includes: Before testing the waste source, leakage prevention measures are taken.

4. The near-surface treatment and preparation method for waste sources according to claim 3, characterized in that, Leakage prevention measures are implemented for the acquired waste sources, including: The acquired waste source was placed in a liquid membrane container inside a negative pressure glove box, allowing the waste source to absorb the liquid membrane. Wrap aluminum foil around the waste source that has been dipped in the liquid film; The waste source wrapped in aluminum foil is placed in a tray inside the negative pressure glove box to complete the leak prevention treatment.

5. The near-surface treatment and preparation method for waste sources according to claim 1, characterized in that, The waste source is encapsulated and filled into a tube according to its activity level, including: If the activity of the waste source meets the encapsulation activity requirements, the waste source is placed in the lower source pipe on the bottom surface of the negative pressure glove box using a clamp, and then the waste source is introduced into the encapsulation tube through the lower source pipe.

6. The near-surface treatment and preparation method for waste sources according to claim 1, characterized in that, The packaged tubes that have undergone welding are processed to obtain a waste package, which includes: Arrange the welded tubes inside the packaging container; The grout is poured into the packaging container to form a waste bag.

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