Method for treating radioactive waste through plasma

Abstract

The invention discloses a method for treating radioactive waste through plasma, and belongs to the technical field of nuclear waste treatment. The method comprises the following steps: taking glass fibers, boron-containing concentrated solution evaporated salt and a glass additive as raw materials, and adjusting the chemical composition of the raw materials to obtain an adjusted waste material containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide; and carrying out plasma melting and curing treatment on the waste material subjected to chemical composition adjustment. According to the method for treating the radioactive waste through the plasma, the plasma high-temperature melting technology is adopted, the glass fiber, the boron-containing concentrated solution evaporation-dried salt and the glass additive serve as raw materials, and the chemical composition of the raw materials is adjusted, so that the melting temperature of the plasma high-temperature melting technology is reduced, the temperature of glass melt is reduced, and discharging is convenient; and the treatment of the glass fiber and the boron-containing concentrated solution can be realized, so that the volume of the glass fiber and the boron-containing concentrated solution can be reduced to the maximum extent, the addition of glass raw materials can be reduced, and the recycling and minimum treatment of radioactive wastes can be realized.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear waste treatment, and in particular to a method for treating radioactive waste with plasma. Background Art

[0002] A large amount of radioactive solid waste generated during the operation, maintenance and decommissioning of nuclear power plants is divided into process waste and technical waste according to different sources: process waste refers to radioactive solid waste generated during the operation of systems and equipment, including filter elements, resins, concentrates, etc., which are stored in special containers with gamma radiation shielding; technical waste refers to radioactive waste generated during equipment maintenance and mid-term repair activities, such as miscellaneous dry waste including cotton fabrics, paper products, plastics, rubber, thermal insulation materials, etc. This type of radioactive concentrated waste liquid includes evaporation residue obtained from evaporation treatment, sludge after flocculation and precipitation, and regeneration waste liquid from ion exchange process. Although its amount is greatly reduced compared with the original wastewater, it concentrates most of the radioactivity of the original wastewater and has a high radioactivity level. The amount of miscellaneous dry waste is large, generally accounting for more than 60% of the total amount of radioactive waste. It is detained for a long time or even overdue in nuclear power plants, which brings great hidden dangers to the normal operation of nuclear power plants. Therefore, in order to avoid the danger caused by long-term storage, radioactive waste must be properly and safely handled and disposed of.

[0003] At present, the treatment methods of medium and low-level solid waste are mainly divided into incineration, cement solidification, concrete fixation, compression and volume reduction, and plasma glass solidification. Among them, incineration can only treat combustible waste, and secondary pollution is easy to occur during the treatment process, and the solid ash after incineration still needs to be solidified. Cement solidification and concrete fixation are both volume increase operations because there is no incineration and volume reduction, which does not meet the principle of minimization of nuclear waste treatment and disposal. Compression and volume reduction are suitable for treating porous waste. Super compactors and heating devices are required during the treatment process. Radioactive waste liquid and waste gas generated during the compaction process also need to be treated. In addition, compacted waste such as mud cannot be treated well. Compared with these methods, plasma has the characteristics of high energy density and high reactivity. It can convert combustible waste into non-combustible inorganic ash through incineration, pyrolysis and other means. At the same time, high temperatures above 1000 degrees Celsius can directly melt non-combustible wastes such as mud and solidify them into glass. Therefore, it is also applicable to the treatment of non-combustible solid waste. In addition, compared with concrete, the advantages of glass such as low leaching rate, homogeneity, and aging resistance can ensure that the glass solidification of low- and medium-level waste can be disposed of near the surface landfill, thus avoiding expensive deep-site storage. In general, plasma glass solidification technology can meet the requirements of volume reduction and amount reduction in radioactive waste treatment and disposal, and is not limited by the type of radioactive waste. It can also fix radioactive nuclides through glass solidification, so it has obvious technical advantages in volume reduction, amount reduction and solidification treatment of low- and medium-level waste resins and low-level but large-volume miscellaneous dry waste.

[0004] Plasma high-temperature melting technology belongs to high-temperature heat treatment technology, and the treatment center temperature is about 1500℃. Glass fiber occupies a large volume in nuclear waste, and it is generally melted to reduce the volume. Glass fiber itself is a glassy material. Under the heat treatment conditions of 1400-1500℃, the final product of the treatment is transparent glass, but its viscosity is relatively large, which is not conducive to discharging in the glass solidification furnace. Borate solutions usually use cement, asphalt, and plastic as the solidification substrate, but these methods may increase the volume and the treatment process is complicated. Summary of the invention

[0005] The purpose of the present invention is to provide a method for treating radioactive waste with plasma, which solves the problems of difficult discharge and complicated treatment process in the process of treating nuclear waste with plasma high-temperature melting.

[0006] The present invention is achieved through the following technical solutions:

[0007] The present invention provides a method for treating radioactive waste with plasma, the method comprising:

[0008] Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition, and obtain the adjusted waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide;

[0009] The waste material after adjusting the chemical composition is subjected to plasma melting and solidification treatment to be melted into a glass melt;

[0010] Discharging and cooling the molten glass into a shape;

[0011] The formed glass melt is annealed and naturally cooled to room temperature to obtain a radioactive waste glass solidified body after plasma treatment.

[0012] Furthermore, in the method for treating radioactive waste with plasma, the raw materials after adjusting the chemical composition include, by weight percentage:

[0013] Boron oxide 6wt% to 18wt%, calcium oxide 2wt% to 10wt%, aluminum oxide 5wt% to 8wt%, sodium oxide 9wt% to 25wt%, and the remainder is silicon dioxide.

[0014] Furthermore, in the method for treating radioactive waste with plasma, the raw materials after adjusting the chemical composition include, by weight percentage:

[0015] Boron oxide 8wt% to 16wt%, calcium oxide 4wt% to 8wt%, aluminum oxide 6wt% to 7wt%, sodium oxide 10wt% to 22wt%, and the remainder is silicon dioxide.

[0016] Furthermore, in the method for treating radioactive waste with plasma, the raw materials after adjusting the chemical composition include, by weight percentage:

[0017] 10wt% to 14wt% of boron oxide, 5wt% to 7wt% of calcium oxide, 6wt% to 7wt% of aluminum oxide, 15wt% to 20wt% of sodium oxide, and the remainder is silicon dioxide.

[0018] Furthermore, in the method for treating radioactive waste with plasma, the raw materials after adjusting the chemical composition include, by weight percentage:

[0019] 12wt% boron oxide, 6wt% calcium oxide, 6.5wt% aluminum oxide, 18wt% sodium oxide, and the remainder silicon dioxide.

[0020] Furthermore, in the method for plasma treatment of radioactive waste, the temperature for plasma high-temperature melting and solidification treatment is 900°C to 1100°C.

[0021] Furthermore, in the plasma treatment method for radioactive waste, the plasma melting and solidification treatment is performed for 1 hour to 2 hours.

[0022] Furthermore, in the method for treating radioactive waste with plasma, the mold used when discharging the molten glass is preheated to 700° C. to 850° C. in advance.

[0023] Furthermore, in the method for treating radioactive waste with plasma, the temperature for annealing is 400°C to 500°C.

[0024] Furthermore, in the method for treating radioactive waste with plasma, the annealing treatment is performed for 1 hour to 2 hours.

[0025] Compared with the prior art, the present invention has the following advantages and beneficial effects:

[0026] The plasma treatment method for radioactive waste provided by the present invention adopts plasma high-temperature melting technology, uses glass fiber, boron-containing concentrated liquid evaporated salt and glass additives as raw materials, adjusts the chemical composition of the raw materials so as to reduce the melting temperature of the plasma high-temperature melting technology, reduces the temperature of the glass melt to facilitate discharge, and can also achieve the treatment of glass fiber and boron-containing concentrated liquid to maximize their volume reduction, can reduce the addition of glass raw materials, and realize the resource utilization and minimized treatment of radioactive waste.

[0027] The plasma treatment method for radioactive waste provided by the present invention can achieve stable performance of the treated radioactive waste glass solidification body, thus meeting the disposal requirements of final radioactive waste. BRIEF DESCRIPTION OF THE DRAWINGS

[0028] In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the following briefly introduces the drawings required for use in the embodiments. It should be understood that the following drawings only illustrate certain embodiments of the present invention and should not be regarded as limiting the scope. For ordinary technicians in this field, other relevant drawings can be obtained based on these drawings without creative work.

[0029] In the figure:

[0030] Figure 1 A flow chart of the method for plasma treatment of radioactive waste provided by the present invention. DETAILED DESCRIPTION

[0031] In order to make the purpose, technical scheme and advantages of the present invention clearer, the present invention is further described in detail below in conjunction with examples and drawings. The illustrative embodiments of the present invention and their description are only used to explain the present invention and are not intended to limit the present invention. If specific conditions are not specified in the examples, they are carried out according to conventional conditions or conditions recommended by the manufacturer. If the manufacturer is not specified for the reagents or instruments used, they are all conventional products that can be purchased commercially.

[0032] The technical solution of the present invention is:

[0033] Please refer to Figure 1 As shown, the present invention provides a method for plasma treatment of radioactive waste, the method comprising:

[0034] Step S1: adjusting the chemical composition of glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0035] Step S2: subjecting the waste material after adjusting the chemical composition to plasma melting and solidification treatment to melt into a glass melt;

[0036] Step S3: discharging the molten glass and cooling it to form a shape;

[0037] Step S4: annealing the formed glass melt, and naturally cooling it to room temperature to obtain a radioactive waste glass solidified body after plasma treatment.

[0038] The plasma treatment method for radioactive waste provided by the present invention adopts plasma high-temperature melting technology, uses glass fiber, boron-containing concentrated liquid evaporated salt and glass additives as raw materials, adjusts the chemical composition of the raw materials so as to reduce the melting temperature of the plasma high-temperature melting technology, reduces the temperature of the glass melt to facilitate discharge, and can also achieve the treatment of glass fiber and boron-containing concentrated liquid to maximize their volume reduction, can reduce the addition of glass raw materials, and realize the resource utilization and minimized treatment of radioactive waste.

[0039] Furthermore, the raw materials after adjusting the chemical composition include, by weight percentage:

[0040] Boron oxide 6wt% to 18wt%, calcium oxide 2wt% to 10wt%, aluminum oxide 5wt% to 8wt%, sodium oxide 9wt% to 25wt%, and the remainder is silicon dioxide.

[0041] Furthermore, the raw materials after adjusting the chemical composition include, by weight percentage:

[0042] Boron oxide 8wt% to 16wt%, calcium oxide 4wt% to 8wt%, aluminum oxide 6wt% to 7wt%, sodium oxide 10wt% to 22wt%, and the remainder is silicon dioxide.

[0043] Furthermore, the raw materials after adjusting the chemical composition include, by weight percentage:

[0044] 10wt% to 14wt% of boron oxide, 5wt% to 7wt% of calcium oxide, 6wt% to 7wt% of aluminum oxide, 15wt% to 20wt% of sodium oxide, and the remainder is silicon dioxide.

[0045] Furthermore, the raw materials after adjusting the chemical composition include, by weight percentage:

[0046] 12wt% boron oxide, 6wt% calcium oxide, 6.5wt% aluminum oxide, 18wt% sodium oxide, and the remainder silicon dioxide.

[0047] Furthermore, the temperature for the plasma high temperature melt solidification treatment is 900°C to 1100°C.

[0048] Furthermore, the plasma melting solidification treatment is performed for 1 hour to 2 hours.

[0049] Furthermore, the mold used when discharging the molten glass is preheated to 700° C. to 850° C. in advance.

[0050] Furthermore, the annealing treatment is performed at a temperature of 400°C to 500°C.

[0051] Furthermore, in the method for treating radioactive waste with plasma, the annealing treatment is performed for 1 hour to 2 hours.

[0052] In order to further illustrate the present invention, a method for treating radioactive waste with plasma provided by the present invention is described below in conjunction with embodiments. However, it should be understood that these embodiments are implemented on the premise of the technical solution of the present invention, and detailed implementation methods and specific operation processes are given only to further illustrate the features and advantages of the present invention, rather than to limit the claims of the present invention. The protection scope of the present invention is not limited to the following embodiments.

[0053] Example 1

[0054] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0055] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0056] (2) The waste material after adjusting the chemical composition is subjected to plasma high-temperature melting and solidification treatment at a melting temperature of 900° C. for 1 hour to melt into a glass melt.

[0057] The raw materials after adjusting the chemical composition include, by weight percentage:

[0058] Boron oxide 6wt%, calcium oxide 2wt%, aluminum oxide 5wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0059] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 700° C. in advance.

[0060] (4) The formed glass melt is annealed at a temperature of 400° C. for 1 hour, and naturally cooled to room temperature to obtain a radioactive waste glass solidified body after plasma treatment.

[0061] Example 2

[0062] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0063] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0064] (2) The waste material after adjusting the chemical composition is subjected to a plasma high-temperature melting solidification treatment at a melting temperature of 950° C. for 1 hour to melt into a glass melt.

[0065] The raw materials after adjusting the chemical composition include, by weight percentage:

[0066] 8wt% boron oxide, 4wt% calcium oxide, 6wt% aluminum oxide, 10wt% sodium oxide, and the remainder silicon dioxide.

[0067] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 750° C. in advance.

[0068] (4) The formed glass melt is annealed at a temperature of 420° C. for 1 hour, and naturally cooled to room temperature to obtain a radioactive waste glass solidified body after plasma treatment.

[0069] Example 3

[0070] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0071] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0072] (2) The waste material after adjusting the chemical composition is subjected to plasma high temperature melting solidification treatment, with the melting temperature of 950° C. and the time of 1.5 hours, to melt into a glass melt. The raw materials after adjusting the chemical composition include, in terms of weight percentage:

[0073] 10wt% boron oxide, 5wt% calcium oxide, 6wt% aluminum oxide, 15wt% sodium oxide, and the remainder silicon dioxide.

[0074] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 750° C. in advance.

[0075] (4) The formed glass melt is annealed at a temperature of 420° C. for 1.5 h. After naturally cooling to room temperature, a radioactive waste glass solidified body after plasma treatment is obtained.

[0076] Example 4

[0077] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0078] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0079] (2) The waste material after adjusting the chemical composition is subjected to plasma high-temperature melting and solidification treatment at a melting temperature of 1000° C. for 1.5 h to be melted into a glass melt.

[0080] The raw materials after adjusting the chemical composition include, by weight percentage:

[0081] 12wt% boron oxide, 6wt% calcium oxide, 6.5wt% aluminum oxide, 17wt% sodium oxide, and the remainder silicon dioxide.

[0082] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 800° C. in advance.

[0083] (4) The formed glass melt is annealed at a temperature of 450° C. for 1.5 h. After naturally cooling to room temperature, a radioactive waste glass solidified body after plasma treatment is obtained.

[0084] Example 5

[0085] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0086] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0087] (2) subjecting the chemically adjusted waste to plasma high-temperature melting and solidification treatment at a melting temperature of 1050° C. for 1.5 h to melt into a glass melt. The chemically adjusted raw materials include, by weight percentage:

[0088] 14wt% boron oxide, 7wt% calcium oxide, 7wt% aluminum oxide, 20wt% sodium oxide, and the remainder silicon dioxide.

[0089] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 800° C. in advance.

[0090] (4) The formed glass melt is annealed at a temperature of 470° C. for 1.5 h. After naturally cooling to room temperature, a radioactive waste glass solidified body after plasma treatment is obtained.

[0091] Example 6

[0092] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0093] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0094] (2) subjecting the chemically adjusted waste to plasma high-temperature melting and solidification treatment at a melting temperature of 1050° C. for 1.5 h to melt into a glass melt. The chemically adjusted raw materials include, by weight percentage:

[0095] 16wt% boron oxide, 8wt% calcium oxide, 7wt% aluminum oxide, 22wt% sodium oxide, and the remainder silicon dioxide.

[0096] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 800° C. in advance.

[0097] (4) The formed glass melt is annealed at a temperature of 470° C. for 1.5 h. After naturally cooling to room temperature, a radioactive waste glass solidified body after plasma treatment is obtained.

[0098] Example 7

[0099] The plasma treatment method for radioactive waste provided in this embodiment comprises the following steps:

[0100] (1) Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition thereof, and obtain waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide after adjustment;

[0101] (2) The waste materials after chemical composition adjustment are subjected to plasma high temperature melting solidification treatment, with a melting temperature of 1100° C. and a time of 2 hours, to melt into a glass melt. The raw materials after chemical composition adjustment include, in terms of weight percentage:

[0102] 18wt% boron oxide, 10wt% calcium oxide, 8wt% aluminum oxide, 25wt% sodium oxide, and the remainder silicon dioxide.

[0103] (3) The glass melt is discharged and cooled to form a mold. The mold used when discharging the glass melt is preheated to 850° C. in advance.

[0104] (4) The formed glass melt is annealed at a temperature of 500° C. for 2 h. After naturally cooling to room temperature, a radioactive waste glass solidified body after plasma treatment is obtained.

[0105] Comparative Example 1

[0106] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of boron oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0107] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0108] Boron oxide 4wt%, calcium oxide 2wt%, aluminum oxide 5wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0109] Comparative Example 2

[0110] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of boron oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0111] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0112] Boron oxide 20wt%, calcium oxide 2wt%, aluminum oxide 5wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0113] Comparative Example 3

[0114] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of calcium oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0115] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0116] Boron oxide 6wt%, calcium oxide 1wt%, aluminum oxide 5wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0117] Comparative Example 4

[0118] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of calcium oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0119] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0120] Boron oxide 6wt%, calcium oxide 12wt%, aluminum oxide 5wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0121] Comparative Example 5

[0122] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of aluminum oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0123] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0124] Boron oxide 6wt%, calcium oxide 2wt%, aluminum oxide 3wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0125] Comparative Example 6

[0126] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of aluminum oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0127] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0128] Boron oxide 6wt%, calcium oxide 2wt%, aluminum oxide 10wt%, sodium oxide 9wt%, and the remainder is silicon dioxide.

[0129] Comparative Example 7

[0130] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of sodium oxide and silicon dioxide in the raw materials after adjusting the chemical composition are different.

[0131] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0132] Boron oxide 6wt%, calcium oxide 2wt%, aluminum oxide 5wt%, sodium oxide 7wt%, and the remainder is silicon dioxide.

[0133] Comparative Example 8

[0134] The method for treating radioactive waste with plasma in this comparative example is consistent with that in Example 1, except that the contents of sodium oxide and silicon dioxide are different after the chemical composition is adjusted.

[0135] The raw materials after adjusting the chemical composition of this comparative example include, by weight percentage:

[0136] Boron oxide 6wt%, calcium oxide 2wt%, aluminum oxide 5wt%, sodium oxide 27wt%, and the remainder is silicon dioxide.

[0137] The chemical compositions of the raw materials after adjusting the chemical compositions in Examples 1-7 of the present invention and Comparative Example 8 are shown in Table 1 below.

[0138] Table 1

[0139]

[0140]

[0141] The performance indexes of the glass melts obtained by the methods for treating radioactive waste with plasma provided in Examples 1-7 of the present invention and Comparative Examples 1-8 were tested, and the results are shown in Table 2.

[0142] Table 2

[0143]

[0144]

[0145] It can be seen from the results in Table 2 that the glass melts treated by the method provided by the present invention all meet the glass performance requirements.

[0146] The specific implementation methods described above further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above description is only a specific implementation method of the present invention and is not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention should be included in the scope of protection of the present invention.

Claims

1. A method for treating radioactive waste with plasma, characterized in that: The method comprises: Using glass fiber, boron-containing concentrated liquid evaporated salt and glass additive as raw materials to adjust the chemical composition, and obtain the adjusted waste containing boron oxide, calcium oxide, aluminum oxide, sodium oxide and silicon dioxide; The waste material after adjusting the chemical composition is subjected to plasma high temperature melting and solidification treatment to be melted into glass melt; Discharging and cooling the molten glass into a shape; The formed glass melt is annealed and naturally cooled to room temperature to obtain a radioactive waste glass solidified body after plasma treatment.

2. The method for plasma treatment of radioactive waste according to claim 1, characterized in that: The raw materials after adjusting the chemical composition include, by weight percentage: Boron oxide 6wt% to 18wt%, calcium oxide 2wt% to 10wt%, aluminum oxide 5wt% to 8wt%, sodium oxide 9wt% to 25wt%, and the remainder is silicon dioxide.

3. The method for plasma treatment of radioactive waste according to claim 2, characterized in that: The raw materials after adjusting the chemical composition include, by weight percentage: Boron oxide 8wt% to 16wt%, calcium oxide 4wt% to 8wt%, aluminum oxide 6wt% to 7wt%, sodium oxide 10wt% to 22wt%, and the remainder is silicon dioxide.

4. The method for plasma treatment of radioactive waste according to claim 3, characterized in that: The raw materials after adjusting the chemical composition include, by weight percentage: 10wt% to 14wt% of boron oxide, 5wt% to 7wt% of calcium oxide, 6wt% to 7wt% of aluminum oxide, 15wt% to 20wt% of sodium oxide, and the remainder is silicon dioxide.

5. The method for plasma treatment of radioactive waste according to claim 4, characterized in that: The raw materials after adjusting the chemical composition include, by weight percentage: 12wt% boron oxide, 6wt% calcium oxide, 6.5wt% aluminum oxide, 18wt% sodium oxide, and the remainder silicon dioxide.

6. The method for plasma treatment of radioactive waste according to claim 1, characterized in that: The temperature for plasma high temperature melting solidification treatment is 900°C to 1100°C.

7. The method for plasma treatment of radioactive waste according to claim 1, characterized in that: The time for plasma high temperature melting solidification treatment is 1h to 2h.

8. The method for plasma treatment of radioactive waste according to claim 1, characterized in that: The mold used for discharging the molten glass is preheated to 700°C to 850°C in advance.

9. The method for plasma treatment of radioactive waste according to claim 1, characterized in that: The temperature for annealing is 400°C to 500°C.

10. The method for plasma treatment of radioactive waste according to claim 1, characterized in that: The annealing treatment time is 1h to 2h.

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