Method for the treatment of radioactive waste

Abstract

This invention discloses a method for treating radioactive waste, comprising the following steps: (1) mixing radioactive waste concentrate and / or water, radioactive particulate waste, cement, and additives in a preset ratio to obtain a mixed slurry; (2) injecting the mixed slurry into a high-integrity container; (3) sealing the high-integrity container; and (4) curing and solidifying to form a high-integrity container waste bag. This method combines the advantages of high-integrity containers' high radioactivity tolerance and long-term durability with the simplicity of cement solidification processes. It has the advantages of simple process, easy operation, good waste volume reduction effect, and high disposal safety, and can be used for the treatment of various types of radioactive waste.

Description

Technical Field

[0001] This invention belongs to the field of radioactive waste treatment technology, and specifically relates to a method for treating radioactive waste. Background Technology

[0002] The operation and decommissioning of nuclear facilities typically generate various types of radioactive waste, such as waste resin, activated carbon, zeolite and other filter media particles from wastewater treatment, radioactive concentrates, waste filter cartridges and metal parts, glass and concrete blocks, and other miscellaneous waste. These wastes vary greatly in physical form, chemical composition, and radioactivity. Even wastes of the same type (such as concentrates and waste resins) can differ significantly in chemical composition and radioactivity levels depending on the reactor type, source, and even the time of generation. To meet the objectives of safe disposal of radioactive waste, radiation protection, and waste minimization, different treatment methods are usually adopted based on the type, form, and quantity of waste.

[0003] For waste resins and concentrates, two common treatment methods are cement solidification and drying followed by loading into High Integrity Containers (HICs). Cement solidification is a widely adopted radioactive waste treatment technology, offering advantages such as readily available raw materials, simple processes, and a wide range of adjustable production capacity. However, this technology suffers from drawbacks including significant volume expansion, high leaching rates, and poor durability. Furthermore, the high performance standards for cement-solidified bodies and the complex composition of waste, along with numerous factors affecting the solidified body's performance, result in poor applicability of cement solidification formulations. Different formulations are required for different waste types, and the solidification process necessitates the simultaneous control of multiple process parameters with inter-parameter interactions, making product quality control difficult. High Integrity Containers (HICs) possess excellent containment, durability, and mechanical properties. Using HICs to contain radioactive waste eliminates the need for complex waste treatment; the HIC itself alone can meet the standard requirements for the safe disposal performance of radioactive waste packages. Current HIC waste treatment processes follow a step-by-step approach based on waste morphology. For example, waste resin particles are dried in a conical dryer, then placed in 200L steel drums before being added to the HIC system. Concentrated waste is dried into salt blocks using an in-tank dryer before being added to the HIC system. Miscellaneous waste such as waste filter cartridges, metal parts, glass, and concrete blocks are placed in 200L steel drums and fixed with cement slurry. This multi-pathway treatment method is not only complex in terms of processes and equipment, requiring large plant space, and resulting in high energy consumption and low production efficiency, but it also generates a large amount of secondary radioactive waste. Furthermore, due to the significant differences in radioactivity levels among wastes from different sources, the surface dose rate levels of the waste packages generated from the treatment will inevitably vary considerably. For example, the surface dose rate of most waste packages is <2 mSv / h, but for high-activity concentrates, waste resins, and waste filter cartridges generated from primary loop waste liquid treatment, regardless of whether cement solidification / fixation or HIC packaging processes are used, the surface dose rate of the waste packages can reach tens or even hundreds of mSv / h. This leads to a significant increase in protection costs during storage and transportation, and when the acceptance limits at the disposal site are exceeded, it will also affect the off-site transportation and disposal of the waste packages. Summary of the Invention

[0004] The technical problem to be solved by the present invention is to address the above-mentioned deficiencies in the prior art by providing a method for the treatment of radioactive waste. This method is simple and easy to implement, flexible in operation, has a high volume reduction rate, and provides good long-term stability of the waste package.

[0005] The technical solution adopted to solve the technical problem of this invention is to provide a method for treating radioactive waste, comprising the following steps: (1) Mix radioactive waste concentrate and / or water, radioactive particulate waste, cement, and additives in a preset ratio to obtain a mixed slurry; (2) Inject the mixed slurry into a high integrity container; (3) Seal the high-integrity container; (4) After curing and solidification, a high-integrity container waste bag is formed.

[0006] Preferably, step (i) is included before step (1): Dehydrate radioactive particulate waste.

[0007] Preferably, the radioactive particulate waste includes any one or more of the following: radioactive waste resin, radioactive waste activated carbon, and radioactive waste zeolite.

[0008] Preferably, the particle size of the radioactive particulate waste is 0.3 mm to 3.0 mm.

[0009] Preferably, in step (1), the amount of radioactive waste concentrate or water is 30-50 parts by weight, the amount of radioactive particulate waste is 25-60 parts by weight, the amount of cement is 80-100 parts by weight, and the amount of additive is 2-10 parts by weight.

[0010] Preferably, step (j) is included before step (2): Radioactive bulk waste is placed in high-integrity containers, where the volume of a single radioactive bulk waste is larger than the volume of a single radioactive particulate waste.

[0011] Preferably, the total volume of radioactive bulk waste does not exceed 90% of the effective volume of the high integrity container.

[0012] Preferably, when the slurry in the high integrity container in step (2) has been cured and solidified, the process returns to step (j) until the height of the slurry in step (2) reaches the preset height.

[0013] Preferably, the preset height is 85% to 95% of the internal height of the high integrity container.

[0014] Preferably, the radioactive bulk waste includes: radioactive miscellaneous waste and / or radioactive waste filter cartridges.

[0015] Preferably, radioactive miscellaneous waste includes any one or more of the following: radioactive waste metal parts, radioactive waste glass, and radioactive waste concrete.

[0016] Preferably, the additives include any one or more of the following: pH adjuster, water-reducing agent, fly ash, and bentonite.

[0017] Preferably, the pH adjuster includes lime and / or sodium citrate.

[0018] The beneficial effects of the radioactive waste treatment method of the present invention are specifically manifested in that this method combines the advantages of high integrity container's high containment of radioactivity and long-term durability with the simplicity of cement solidification process. It has the advantages of simple process, easy operation, good waste volume reduction effect and high disposal safety, and can be used for the treatment of various types of radioactive waste. Attached Figure Description

[0019] Figure 1 This is a schematic diagram of the radioactive waste treatment process in Embodiment 2 of the present invention; Figure 2 This is a schematic diagram of the radioactive waste treatment process in Embodiment 3 of the present invention; Figure 3 This is a schematic diagram of the radioactive waste treatment process in Embodiment 4 of the present invention; Figure 4 This is a schematic diagram of the radioactive waste treatment process in Embodiment 5 of the present invention. Detailed Implementation

[0020] To enable those skilled in the art to better understand the technical solution of the present invention, the present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.

[0021] Example 1

[0022] This embodiment provides a method for treating radioactive waste, including the following steps: (1) Mix radioactive waste concentrate and / or water, radioactive particulate waste, cement, and additives in a preset ratio to obtain a mixed slurry; (2) Inject the mixed slurry into a high integrity container; (3) Seal the high-integrity container; (4) After curing and solidification, a high-integrity container waste bag is formed.

[0023] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested in that this method combines the advantages of high integrity containers in terms of high radioactivity containment and long-term durability with the simplicity of cement solidification process. It has the advantages of simple process, easy operation, good waste volume reduction effect and high disposal safety, and can be used for the treatment of various types of radioactive waste.

[0024] Example 2

[0025] This embodiment provides a method for treating radioactive waste, including the following steps: (1) Mix radioactive waste concentrate and / or water, radioactive particulate waste, cement, and additives in a preset ratio to obtain a mixed slurry; (2) Inject the mixed slurry into a high integrity container (HIC); (3) Seal the high-integrity container; (4) After curing and solidification, a high-integrity container waste bag is formed.

[0026] Preferably, step (i) is included before step (1): Dehydrate radioactive particulate waste.

[0027] If the waste being treated does not contain radioactive waste concentrate or its water content is insufficient for the solidification reaction, water can be added from external sources.

[0028] Preferably, the radioactive particulate waste includes any one or more of the following: radioactive waste resin, radioactive waste activated carbon, and radioactive waste zeolite.

[0029] Preferably, the particle size of the radioactive particulate waste is 0.3 mm to 3.0 mm.

[0030] Preferably, in step (1), the amount of radioactive waste concentrate or water is 30-50 parts by weight, the amount of radioactive particulate waste is 25-60 parts by weight, the amount of cement is 80-100 parts by weight, and the amount of additive is 2-10 parts by weight.

[0031] Preferably, step (j) is included before step (2): Radioactive bulk waste is placed in high-integrity containers, where the volume of a single radioactive bulk waste is larger than the volume of a single radioactive particulate waste.

[0032] Preferably, the total volume of radioactive bulk waste does not exceed 90% of the effective volume of the high integrity container.

[0033] Preferably, when the slurry in the high integrity container in step (2) has been cured and solidified, the process returns to step (j) until the height of the slurry in step (2) reaches the preset height.

[0034] Preferably, the preset height is 85% to 95% of the internal height of the high integrity container.

[0035] Preferably, the radioactive bulk waste includes: radioactive miscellaneous waste and / or radioactive waste filter cartridges.

[0036] Preferably, radioactive miscellaneous waste includes any one or more of the following: radioactive waste metal parts, radioactive waste glass, and radioactive waste concrete.

[0037] Preferably, the additives include any one or more of the following: pH adjuster, water-reducing agent, fly ash, and bentonite.

[0038] pH adjusters are used to balance the pH value of the hydration reaction system.

[0039] Preferably, the pH adjuster includes lime and / or sodium citrate.

[0040] Specifically, the cement used in this embodiment is ordinary Portland cement.

[0041] The injection of radioactive waste and mixed slurry can be completed in several stages.

[0042] The radioactive waste treatment method in this embodiment uses a high-integrity container as the packaging container, cement as the solidifying agent, and the water contained in the radioactive waste concentrate as the hydration reaction water source in a self-balancing reaction system. It utilizes the mixing and volume reduction effect of items of different scales and controls the surface dose rate level of the waste package by adjusting the proportion of waste with different radioactivity to treat the radioactive waste.

[0043] The purpose of dehydrating radioactive particulate waste is to facilitate accurate measurement of particulate waste and reduce the total water content in the waste, thereby reducing cement consumption and ultimately reducing the volume of the solidified waste.

[0044] The process of injecting the mixed slurry can be carried out in batches, and the filling effect and efficiency can be improved by using vibration equipment. In order to improve the uniformity of the solidified body, radioactive miscellaneous waste and / or radioactive waste filter cartridges can also be added in multiple batches (i.e., first add a portion of radioactive miscellaneous waste and inject an appropriate amount of cement mixed slurry, and after the cement mixed slurry has solidified, add the next batch of radioactive miscellaneous waste and / or radioactive waste filter cartridges, and then inject cement mixed slurry).

[0045] According to GB12711 "Safety Standard for Low and Intermediate Level Radioactive Solid Waste Packages", HIC (High-Intensity Concentrated Ion) waste can be in a dispersed state as a packaging container. Therefore, the solidified waste in this invention does not need to comply with the requirements of GB 14569.1 "Performance Requirements for Solidified Low and Intermediate Level Radioactive Waste - Cement Solidified Body". It is only necessary to control the free water content of the solidified waste according to the requirement in GB12711 that "the free water volume in the waste package should be less than 1% of the solid volume".

[0046] like Figure 1 As shown, specifically, this embodiment provides a method for treating radioactive waste, including the following steps: 1) The water-containing radioactive particulate waste is dehydrated by a dehydration device, which is a filter or a centrifuge. The radioactive particulate waste is radioactive waste resin with a particle size of 0.3 mm.

[0047] 2) Add the radioactive waste concentrate, cement, filler, and drained radioactive waste resin, measured by volume or weight according to the formula, to the mixing tank. The radioactive waste concentrate is 50 parts by weight, the radioactive waste resin is 60 parts by weight, the cement is 90 parts by weight, and the filler is 7 parts by weight. Turn on the agitator to mix the cement slurry. The filler is a pH adjuster, which includes lime and / or sodium citrate.

[0048] 3) Add radioactive bulk waste into the high integrity container (HIC). The radioactive bulk waste includes miscellaneous radioactive waste or radioactive waste filter cartridges. The maximum height of the radioactive miscellaneous waste or radioactive waste filter cartridges added should not affect the reset of the HIC container cover. The total volume of the radioactive miscellaneous waste or radioactive waste filter cartridges should not exceed 90% of the effective volume of the high integrity container.

[0049] 4) Pour the mixed cement slurry into the HIC container, turn on the vibration device, and after the cement slurry has seeped into the bottom of the HIC container, add more cement slurry. After vibrating evenly, add the corresponding volume of cement slurry according to the remaining space to the preset height. The preset height is 90% of the internal height of the high integrity container. Stop the pouring operation.

[0050] 5) After sealing the HIC container with the sealing device, move it to the curing area.

[0051] 6) After the cement mixture slurry is cured, it forms HIC waste bags.

[0052] This waste treatment method can effectively utilize the gaps between miscellaneous wastes as treatment space for waste resin and concentrated cement slurry. Compared to treating miscellaneous waste separately, each volume (pile) of miscellaneous waste can provide an additional space of about 1 / 10 to 1 / 2 of the volume (depending on the type and form of the miscellaneous waste) for the treatment of waste resin and concentrated cement slurry. By co-processing miscellaneous wastes with low activity levels, the radioactivity of solidified waste resin / concentrate cementitious bodies and the surface dose rate level of waste packages can be reduced.

[0053] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or ductile iron have a certain thickness and high density, providing a certain shielding effect. In addition, the activity level of the waste can be controlled by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0054] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0055] Example 3

[0056] like Figure 2 As shown, this embodiment provides a method for treating radioactive waste, including the following steps: (1) The aqueous radioactive waste resin is dehydrated by passing it through a filter or centrifuge. The particle size of the radioactive waste resin is 0.3~0.6mm.

[0057] (2) Add the radioactive waste concentrate, cement, quicklime powder and drained radioactive waste resin, measured by volume or weight according to the formula, to the mixing tank. The radioactive waste concentrate is 40 parts by weight, the radioactive waste resin is 40 parts by weight, the cement is 80 parts by weight, and the quicklime powder is 10 parts by weight. Then turn on the stirring device to stir the cement slurry.

[0058] (3) Pour the mixed cement slurry into the HIC container, turn on the vibration device, and when the rated pouring volume is reached to the preset height, the preset height is 90% of the internal height of the high integrity container, stop the pouring operation.

[0059] (4) After sealing the HIC container with the sealing device, move it to the curing area.

[0060] (5) After the cement mixture slurry is cured, it forms HIC waste bags.

[0061] Compared to the traditional cement curing condensate, which typically has a containment rate of <50%, this waste treatment method can increase the containment rate of the cement curing body to 55-65% of the concentrate, while also additionally containing 30-40% of the volume of waste resin (relative to the entire curing body).

[0062] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0063] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0064] Example 4

[0065] like Figure 3 As shown, this embodiment provides a method for treating radioactive waste, including the following steps: (1) The aqueous radioactive waste resin is dehydrated by passing it through a filter or centrifuge. The particle size of the radioactive waste resin is 0.3~0.6mm.

[0066] (2) Add the cement, filler, and drained radioactive waste resin and tap water or demineralized water according to the formula to the mixing tank. The tap water is 45 parts by mass, the radioactive waste resin is 25 parts by mass, the cement is 100 parts by mass, and the filler is 2 parts by mass. Then turn on the mixing device to mix the cement slurry.

[0067] (3) Add radioactive miscellaneous waste or radioactive waste filter cartridges into the HIC container. The height of adding radioactive miscellaneous waste or radioactive waste filter cartridges should not affect the reset of the HIC container cover. The total volume of radioactive miscellaneous waste or radioactive waste filter cartridges should be 80% of the effective volume of the high integrity container.

[0068] (4) Pour the mixed cement slurry into the HIC container, turn on the vibration device, and after the cement slurry has seeped into the bottom of the HIC container, add cement slurry again. After vibrating evenly, add the corresponding volume of cement slurry according to the remaining space to the preset height. The preset height is 90% of the internal height of the high integrity container. Stop the pouring operation.

[0069] (5) After sealing the HIC container with the sealing device, move it to the maintenance area.

[0070] (6) After the cement mixture slurry is cured, it forms HIC waste bags.

[0071] This waste treatment method is mainly for situations where additional waste resin needs to be treated, but there is no concentrate to be treated.

[0072] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0073] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0074] Example 5

[0075] like Figure 4 As shown, this embodiment provides a method for treating radioactive waste, including the following steps: (1) The aqueous radioactive waste resin is dehydrated by passing it through a filter or centrifuge. The particle size of the radioactive waste resin is ≤0.5mm.

[0076] (2) Add the radioactive waste concentrate, measured by volume or weight according to the formula, into the mixing tank.

[0077] (3) Add a fixed amount of cement, lime and drained radioactive waste resin to the mixing tank. The amount of radioactive waste concentrate is 35 parts by mass, the amount of radioactive waste resin is 30 parts by mass, the amount of cement is 85 parts by mass, and the amount of lime is 4 parts by mass. Then turn on the stirring device.

[0078] (4) Add radioactive miscellaneous waste into the HIC container. The amount of radioactive miscellaneous waste added is determined according to the number of batch operations. The total volume of radioactive miscellaneous waste or radioactive waste filter cartridges is 70% of the effective volume of the high integrity container.

[0079] (5) Pour cement slurry into the HIC container. The amount of cement slurry added should be determined by the volume required to cover the radioactive miscellaneous waste after mixing. At the same time, turn on the vibration device. After the cement slurry has completely penetrated into the voids of the radioactive miscellaneous waste, stop the pouring operation and move it to the curing area for curing and solidification. The curing time needs to be determined according to the specific situation (cement formula and curing conditions).

[0080] (6) Perform the operation of the next HIC container according to steps (4) and (5) until the filling operation of all HIC containers in this batch is completed.

[0081] (7) Prepare cement slurry according to steps (1)-(3).

[0082] (8) Refill the HIC container, which has been cured and solidified with cement slurry at the bottom, with radioactive waste filter cartridges or radioactive miscellaneous waste.

[0083] (9) Re-grouting and curing of HIC containers that have been refilled with radioactive miscellaneous waste.

[0084] (10) Repeat steps (8) and (9) above until the height of the mixed slurry in the HIC container reaches the preset height, which is 90% of the height inside the high integrity container, until the HIC container completes the last pouring.

[0085] (11) After sealing the HIC container with the sealing device, move it to the curing area and cure it to form a high-integrity container waste bag.

[0086] The advantages of adding miscellaneous waste and grouting material in batches are as follows: By reducing the stratification phenomenon caused by density differences between different types of miscellaneous waste and cement slurry, the uniformity of radioactive waste distribution in the entire solidified body space is improved, thereby improving the uniformity of nuclide distribution in the solidified body and the uniformity of dose rate distribution on the outer surface of the waste package, thus reducing the shielding and radiation protection requirements during the storage, transportation and disposal of waste packages. For filter cartridges with high activity levels, they can be added in the middle batches. Through the shielding effect of the relatively low-activity cement solidified body around them and the HIC filter wall, the surface dose rate of the waste package can be effectively reduced.

[0087] Reducing the thickness of miscellaneous waste in a single operation helps increase the filling rate of cement slurry between miscellaneous wastes, thereby further improving the containment rate of radioactive waste and increasing the structural strength of the solidified body.

[0088] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0089] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0090] Example 6

[0091] This embodiment provides a method for treating radioactive waste, which differs from the method in Embodiment 2 in that: The radioactive particulate waste in step 1) is radioactive spent activated carbon. The particle size of the radioactive particulate waste is ≤1.0 mm. In step 2), the amount of radioactive waste concentrate is 45 parts by mass, radioactive particulate waste is 35 parts by mass, cement is 92 parts by mass, and additive is 6 parts by mass. The additive is a pH adjuster, specifically sodium citrate.

[0092] In step 3), the total volume of radioactive bulk waste shall not exceed 50% of the effective volume of the high integrity container, and the radioactive bulk waste includes radioactive waste filter cartridges.

[0093] The preset height in step 4) is 90% of the internal height of the high integrity container.

[0094] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0095] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0096] Example 7

[0097] This embodiment provides a method for treating radioactive waste, which differs from the method in Embodiment 2 in that: The radioactive particulate waste in step 1) consists of radioactive waste resin and radioactive waste activated carbon (mass ratio 2:1). The particle size of the radioactive particulate waste is ≤2mm. In step 2), the amount of radioactive waste concentrate is 32 parts by mass, radioactive particulate waste is 45 parts by mass, cement is 95 parts by mass, and additive is 8 parts by mass. The additive is a pH adjuster. The pH adjuster includes lime and sodium citrate (mass ratio 1:1).

[0098] In step 3), the total volume of radioactive bulk waste is 50% of the effective volume of the high-integrity container. This radioactive bulk waste is classified as miscellaneous radioactive waste. The miscellaneous radioactive waste consists of radioactive scrap metal components.

[0099] The preset height in step 4) is 95% of the internal height of the high integrity container.

[0100] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0101] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0102] Example 8

[0103] This embodiment provides a method for treating radioactive waste, which differs from the method in Embodiment 2 in that: The radioactive particulate waste in step 1) is radioactive waste zeolite. The particle size of the radioactive particulate waste is 2.5 mm.

[0104] Step 2) The radioactive waste concentrate consists of 45 parts by weight, radioactive particulate waste consists of 50 parts by weight, cement consists of 82 parts by weight, and additives consist of 3 parts by weight. The additives include fly ash and bentonite (by weight ratio of 3:2).

[0105] In step 3), the total volume of radioactive bulk waste is 30% of the effective volume of the high integrity container. Radioactive bulk waste includes miscellaneous radioactive waste or radioactive waste filter cartridges.

[0106] Radioactive miscellaneous waste includes radioactive waste glass.

[0107] The preset height in step 4) is 95% of the internal height of the high integrity container.

[0108] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0109] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0110] Example 9

[0111] This embodiment provides a method for treating radioactive waste, which differs from the method in Embodiment 2 in that: In step 2), water, cement, filler, and drained radioactive waste resin, measured by volume or weight according to the formula, are added to the mixing tank. The water is 40 parts by weight, the radioactive particulate waste is 52 parts by weight, the cement is 87 parts by weight, and the filler is 9 parts by weight. The mixing device is then turned on to mix the cement slurry. The filler is a pH adjuster, and the pH adjuster is sodium citrate.

[0112] In step 3), the radioactive miscellaneous waste is radioactive waste concrete.

[0113] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%~50%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0114] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0115] Example 10

[0116] This embodiment provides a method for treating radioactive waste, which differs from the method in Embodiment 2 in that: In step 2), the additives are a pH adjuster and a water-reducing agent, and the pH adjuster is lime.

[0117] In step 3), the radioactive particulate waste consists of radioactive waste resin and radioactive waste carbon (the volume ratio of the two is 2:1).

[0118] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: The mixed volume reduction effect of items of different sizes and the improved containment rate of the solidified body result in a significant reduction in the final waste bag volume (compared to the traditional cement solidification / fixation process, the packaging volume can be reduced by 30%). 4) Better radiation protection: The walls of HIC (High-Intensity Concrete) containers made of concrete or milled cast iron have a certain thickness and high density, providing a certain shielding effect. In addition, by adjusting the ratio between different types and activity levels of radioactive waste and with non-radioactive cement materials, the activity level of the waste can be controlled. This allows the dose rate on the outer surface of the HIC waste package to be controlled within a certain range, meeting the limitations on the dose rate and activity level on the outer surface of the waste package during storage, transportation, and disposal, and reducing additional radiation exposure for workers during waste treatment and disposal.

[0119] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0120] Example 11

[0121] This embodiment provides a method for treating radioactive waste, which differs from the method in Embodiment 2 in that: In step 3), the radioactive waste is a concentrated radioactive waste solution.

[0122] The beneficial effects of the radioactive waste treatment method in this embodiment are specifically manifested as follows: 1) Simple process and equipment: Only one set of mixing and stirring device and high integrity container (HIC) sealing equipment (equivalent to one set of equipment for traditional cement solidification process) are needed to complete the treatment of various wastes; 2) Good operability: Waste solidified bodies using HIC packaging are no longer restricted by the national standard GB14569.1-2011. They only need to comply with the requirements for free water content and do not need to consider the influence of interfering factors such as waste composition and concentration changes. The operation is simple and the product quality is easy to control. 3) Significant volume reduction effect: It eliminates the need to consider standard requirements for the strength and permeability of the cured body, and increases the containment rate of the concentrate from <50% in traditional cement curing processes to 55%~65%; 4) Better radiation protection: The walls of HIC made of concrete or milled cast iron have a certain thickness and high density, which has a certain shielding effect. This can reduce the limitations of dose rate and activity level on the outer surface of the waste package, and reduce the additional radiation exposure to workers during waste handling, storage, transportation and disposal.

[0123] 5) High safety of waste bag disposal: The HIC container provides long-term durability and containment for safe disposal of waste bags. After the cement slurry solidifies, it forms a covering structure and integrates with the HIC, further improving the impact resistance and long-term stability of the waste bag.

[0124] It is understood that the above embodiments are merely exemplary implementations used to illustrate the principles of the present invention, and the present invention is not limited thereto. For those skilled 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 treating radioactive waste, characterized in that, Includes the following steps: (1) Mix radioactive waste concentrate and / or water, radioactive particulate waste, cement, and additives in a preset ratio to obtain a mixed slurry; (2) Inject the mixed slurry into a high integrity container; (3) Seal the high-integrity container; (4) After curing and solidification, a high-integrity container waste bag is formed.

2. The method for treating radioactive waste according to claim 1, characterized in that, The step (i) is preceding step (1): Dehydrate radioactive particulate waste.

3. The method for treating radioactive waste according to claim 1, characterized in that, Radioactive particulate waste includes any one or more of the following: radioactive waste resin, radioactive waste activated carbon, and radioactive waste zeolite.

4. The method for treating radioactive waste according to any one of claims 1 to 3, characterized in that, The particle size of radioactive particulate waste is 0.3 mm to 3.0 mm.

5. The method for treating radioactive waste according to claim 1, characterized in that, In step (1), the amount of radioactive waste concentrate or water is 30-50 parts by weight, the amount of radioactive particulate waste is 25-60 parts by weight, the amount of cement is 80-100 parts by weight, and the amount of additive is 2-10 parts by weight.

6. The method for treating radioactive waste according to claim 1, characterized in that, Step (j) precedes step (2): Radioactive bulk waste is placed in high-integrity containers, where the volume of a single radioactive bulk waste is larger than the volume of a single radioactive particulate waste.

7. The method for treating radioactive waste according to claim 6, characterized in that, The total volume of radioactive bulk waste shall not exceed 90% of the effective volume of a high-integrity container.

8. The method for treating radioactive waste according to claim 6, characterized in that, When the slurry mixture in the high integrity container in step (2) has been cured and solidified, return to step (j) until the height of the slurry mixture in step (2) reaches the preset height.

9. The method for treating radioactive waste according to claim 8, characterized in that, The preset height is 85% to 95% of the internal height of the high integrity container.

10. The method for treating radioactive waste according to claim 6, characterized in that, Radioactive bulk waste includes: radioactive miscellaneous waste and / or radioactive waste filter cartridges.

11. The method for treating radioactive waste according to claim 10, characterized in that, Radioactive miscellaneous waste includes any one or more of the following: radioactive waste metal parts, radioactive waste glass, and radioactive waste concrete.

12. The method for treating radioactive waste according to claim 1, characterized in that, Additives include any one or more of the following: pH adjuster, water reducing agent, fly ash, and bentonite.

13. The method for treating radioactive waste according to claim 12, characterized in that, pH adjusters include: lime and / or sodium citrate.

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