RU2342721C1 - Method of treating liquid radioactive wastes of atomic power stations (versions) - Google Patents

Abstract

FIELD: physics; nuclear technology.

SUBSTANCE: present group of inventions pertains to treatment of liquid radioactive wastes, and particularly to methods of concentrating, drying and solidifying an evaporate concentrate. The method of treating liquid radioactive wastes involves concentrating wastes through evaporation at 105-150°C by adding glycerine to liquid radioactive wastes, at ratio of 1:9-1:1 in the evaporation zone. A glycerine evaporate concentrate is obtained from the process of concentrating liquid radioactive wastes. This concentrate is subjected to thermal treatment at 150°-200°C. The glycerine concentrate formed as a result is returned to the liquid radioactive wastes treatment cycle. The porous anhydrous salt product obtained after distillation of glycerine is solidified by adding portions of a binding substance to it until formation of a homogenous in situ block. After adding each portion of binding substance, the product is cooled to 85°-95°C. The next portion of binding substance is added after heating the product to 105-150°C. The proposed group of inventions is aimed at simplifying the technology of neutralisation of liquid radioactive wastes, reduction of the amount of glycerine used when concentrating the wastes, and improving the environmental situation at places of permanent disposal of radioactive wastes.

EFFECT: simplification of the technology of neutralisation of liquid radioactive wastes, reduction of the amount of glycerine used when concentrating the wastes, and improvement of the environmental situation at places of permanent disposal of radioactive wastes.

3 cl, 1 tbl

Description

The invention relates to the field of processing (disposal) of liquid radioactive waste (LRW), and in particular to methods of concentration, drying and curing of salt concentrate (bottom residue).

The main tasks to be solved within the framework of the LRW disposal problem are the purification of the bulk of the waste from radionuclides and the concentration of the latter in a minimum volume with the subsequent solidification (monolithization) of the radioactive salt concentrates in the form of a product that excludes the release of radionuclides into the environment during its long-term storage.

In practice, traditional precipitation, thermal, sorption and membrane methods are usually used to solve these problems at the stages of treatment and concentration of LRW. The monolithic treatment of LRW salt concentrates is usually carried out after their thermal or mechanical drying by incorporation into inert matrices (bitumen, cement, thermosetting resins, etc.) [A.S. Nikifirov, V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat, Moscow, 1985, p.13-115].

All the methods discussed above are individual without exception and can solve no more than one or two tasks in the technological cycle of LRW disposal, which requires the development of specific equipment at each stage of the technological process for processing LRW.

From the point of view of the maximum concentration of LRW in the technological cycle of their disposal, the most rational way is considered to be the method of thermal distillation (evaporation) of LRW. Despite the relatively high energy consumption, the thermal method has found wide application in the practice of evaporating LRW and drying salt concentrates due to its technological advantages [A.S. Nikifirov, V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat, Moscow, 1985, p.14].

A known method of processing LRW, including: concentration of LRW by evaporation of bottoms (salt concentrates) with a salinity of 130-150 g / l in nitric acid at pH 3.5-4.0 in evaporators operating in the mode of heat transfer through a heat transfer surface, followed by storing highly concentrated bottoms with a salinity of 600-800 g / l in temporary storage tanks, or curing them using bitumen, cementing, etc. [A.S. 654010 (USSR). The method of concentration of liquid radioactive waste. M.I.Zhikharev, L.Ch. Kemularia. Publ. in BI, 1980, No. 3].

The disadvantages of this method are:

- inlay (precipitation of salts) of the heating surfaces, which leads to a decrease in the productivity of the process and requires periodic chemical washing of the evaporator;

- foaming of LRW in the presence of detergents (surfactants) in them, which significantly complicates the evaporation process;

- corrosiveness of salt nitrate concentrate with respect to structural materials used in the equipment LRW neutralization cycle;

- a relatively low degree of concentration of salts (not more than 600-800 g / l);

- with deep evaporation of LRW to a salinity of 600-800 g / l or more, difficulties arise in the subsequent treatment of the bottom residue due to the precipitation of crystalline hydrates of salts in pipelines and tanks for temporary storage, which complicates their transportation and eliminates the possibility of complete buildup of tanks in an emergency and the emptying of containers after the guaranteed shelf life of LRW concentrates has expired and, therefore, creates the risk of radionuclides entering the environment [A.S. Nikifirov, V.V. Kulichenko, M.I. Neutralization of liquid radioactive waste. Enogoatomizdat, Moscow, 1985, pp. 109-112].

There is a method of processing LRW, which consists in concentrating the waste by evaporation in direct contact of liquid radioactive waste with glycerin at a temperature of 105-150 ° C and the ratio of liquid radioactive waste and glycerin in the evaporation zone 1: 9-1: 1 [RF Patent No. 2168222, G21F 9/08, 1999, Bull. No. 15]. This method is selected as a prototype as the closest to the claimed method in technical essence and the achieved results.

Despite its undeniable advantages, such as: increasing the degree of evaporation of LRW; prevention of incrustation of heating surfaces by scaling; eliminating the possibility of developing local corrosion of stainless steel; prevention of foaming of evaporated solutions in the presence of detergents in LRW; simplification of operations for subsequent treatment with bottom residue, etc., the prototype method, like its counterpart, does not provide the conditions for reliable, long-term storage of salt concentrates, which exclude the release of radionuclides into the environment in the event of emergency depressurization of storage tanks of LRW concentrates and contact of concentrates with water.

Typically, in domestic and foreign nuclear power plants, liquid radioactive waste concentrates are converted into solid form by the inclusion of concentrates in thermoplastic (bitumen, etc.), inorganic (cement, gypsum, etc.) or thermoset (polyester, urea, etc. resins) binders. [A.S. Nikifirov, V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Enoatomizdat, Moscow, 1985, p. 115].

When processing LRW according to the prototype method, the end product is anhydrous glycerol salt concentrate (brine), for which, as laboratory experiments have shown, traditional curing methods are unacceptable for the following reasons:

- glycerol salt concentrate is incompatible with bitumen and cement, which does not allow to obtain a homogeneous solid product suitable for long-term storage;

- the use of thermosetting resins in monolithic glycerol-salt concentrate in the practice of LRW neutralization was not used due to the specificity of the component composition of the final product.

The objective of the present invention is to provide a method for processing liquid radioactive waste, which allows to reduce the amount of glycerin used in the concentration of LRW, to increase the degree of inclusion of salts in the proposed matrix, to reduce the area of seized territory during long-term storage of solidified LRW and to improve the environmental situation in places of long-term storage of radioactive waste.

The problem is solved by the proposed method of LRW processing, implemented in two versions.

To achieve the specified technical result in the first method of processing liquid radioactive waste, which consists in concentrating LRW by evaporation at a temperature of 105-150 ° C by feeding liquid radioactive waste into glycerin with a ratio in the evaporation zone of 1: 9-1: 1, it is proposed:

- obtained in the process of concentrating LRW salt glycerin concentrate is subjected to heat treatment at a temperature of 150 ° -200 ° C;

- the condensate of glycerol and the products of its thermochemical decomposition formed during this process shall be returned to the liquid radioactive waste processing cycle;

- in the obtained, after distillation of glycerol, a porous anhydrous salt product (cake) in portions to introduce a binder;

- after entering each portion of the binder, cool to a temperature of 85-95 ° C;

- enter a subsequent portion of the binder to carry out after heating the product to a temperature of 105-150 ° C.

In the particular case of the first method, it is proposed to use, for example, bitumen or polymeric materials as a binder.

To achieve the technical result in the second method of processing liquid radioactive waste, which consists in concentrating LRW by evaporation at a temperature of 105-150 ° C by supplying liquid radioactive waste to glycerin with a ratio in the evaporation zone of 1: 9-1: 1, it is proposed:

- to add an additive in the amount of 1-3 grams of reagent per 1 gram of free glycerol to saline glycerin concentrate;

- mix the resulting mixture at a temperature of 150-180 ° C until the additive is completely dissolved;

- the resulting product is subjected to stirring with heat treatment at a temperature of 180-220 ° C until a homogeneous mass is formed, which is a glyphthalic resin with crystals of radioactive salts included in it;

- the resulting polymer product is cooled to a temperature of 20-40 ° C until a molten, solid, water-insoluble monolith is formed;

- use phthalic anhydride or phthalic acid as an additive.

In addition, it is proposed that the processes of concentration and curing of salt glycerin concentrate be carried out in a device of the simplest construction consisting of a heated container (for example, a drum or barrel), which, after completion of the curing process, is supplied for long-term storage, and a gas treatment system for volatile gaseous products.

The process of concentrating LRW and hardening of salt concentrate according to the proposed method can significantly simplify the technology of disposal of LRW by conducting the entire cycle of their processing in one tank and to obtain solid, water-insoluble monoliths included in a storage tank suitable for long-term disposal at the final stage of disposal of LRW improve the environmental situation in places of long-term storage of radioactive waste. In addition, it is possible to increase the degree of inclusion of salts in the proposed matrices (up to 50% or more), for example, in comparison with the method of curing salt water concentrates with cement (the degree of inclusion of salts in the cement mass is only 5-6%) [A.S. Nikiforov , V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat. Moscow, 1985, p.131], will significantly reduce the area of the seized territory during long-term storage of cured LRW, packaged in containers and placed in protective protective containers.

In support of the proposed method, laboratory experiments were carried out to determine the main technological parameters of the process of thermal distillation of glycerol and products of its thermochemical decomposition from glycerol-salt concentrate, and the possibility of their secondary use in the technological cycle of LRW processing at the concentration stage (experiment 1) and transformation of glycerol salt concentrate into a solid porous product with monolithization of the latter with bitumen (experiment 2).

Experiment No. 1.

Stage stripping from brine of glycerol and high-boiling, volatile products of its thermochemical decomposition.

25 ml (weight 36.0 g) of glycerol-salt concentrate (product 1) obtained by the prototype method in the process of concentrating LRW corresponding to the chemical composition of LRW type 3 (Table 1) is subjected to heat treatment in a quartz flask with an air cooler at a temperature of 150-200 ° C for 5 hours. The resulting pairs of glycerol and its thermochemical decomposition products (product 2) are condensed in an air refrigerator (at a temperature of 25-30 ° C) and collected in a calibrated condensate collector.

As a result of heat treatment of the brine, 8.5 cm ^{3 of} product 2 was driven out of it (product weight 10.5 g, density ρ-1.23 g / cm ³ ). After cooling, a porous product 3 was formed in the reaction flask (porosity 0.5 cm ³ / cm ^{3 of} product), which was dehydrated salt crystals bound in the product structure by non-volatile components of the thermochemical decomposition of glycerol (resinous substances, carbon, etc.).

Next, the product 3 is poured with distilled water and boiled for 1 hour, after which the distillate is drained from the flask and the water-soluble (product 4) and water-insoluble (product 5) parts of product 3 are determined, which are 16.5 and 8.5 grams, respectively.

It has been established that carrying out the proposed stage of LRW processing allows reducing glycerol consumption by at least 30% and obtaining a porous anhydrous salt cake containing up to 34 wt.% Water-insoluble components of the thermochemical destruction of glycerol in the structure.

Stage reuse of product 2 in the cycle of disposal of LRW.

The solution corresponding to the chemical composition of LRW type 3 in accordance with Table 1 is evaporated in a quartz distiller with samples of 12X18H10T austenitic steel at a temperature of 105-150 ° C (according to the prototype) by feeding LRW into pure glycerin and into a mixture consisting of 8 , 5 cm ^{3 of} product 2 and 16.5 cm ^{3 of} pure glycerin (the claimed method). The evaporation rate of the initial solution (the ratio of the volume of the solution fed to the distiller to the volume of the bottom residue) and the crystallization of salts are controlled.

It was established that the processes of evaporation and crystallization of salts in both cases proceed identically, and the resulting product has, as in the case of evaporation in pure glycerin (prototype method), mobility and fluidity.

The implementation of this proposal in practice will reduce the consumption of glycerol by 30-35% and reduce the amount of newly formed LRW by returning product-2 to the processing cycle of aqueous saline solutions of LRW.

Experiment number 2.

Stages of thermochemical transformation of glycerol-salt concentrate into a solid porous product and monolithization of the latter with bitumen in a heated drum (barrel).

10 cm ³ (15.0 g) of glycerol-salt concentrate (product 1) obtained in the process of concentrating LRW using the prototype method is subjected to heat treatment in an open porcelain crucible (crucible capacity 10 cm ³ , empty crucible weight 11 g) at a temperature 150-200 ° C for 5 hours, after which the crucible with product 3 is cooled to room temperature, the volatile (product 2) and non-volatile (product 3) weights are calculated. It was found that during the thermal transformation of product 1, about 6.5 g of glycerol and the volatile products of its thermochemical decomposition were removed from it, and 8.5 g of porous solid cake was obtained (product 3).

Next, the crucible with product 3 is heated to a temperature of 100-150 ° C and pieces of solid bitumen are introduced in portions until it melts on the surface of the hot product 3. After melting the bitumen and holding the crucible with the product at a temperature of 100-150 ° C for 10 minutes, the crucible with the product is cooled in air to a temperature of 85-95 ° C, while due to the vacuum effect that occurs in the pores of the product when it is cooled, it is impregnated with bitumen. To obtain a monolithic non-porous bitumen-salt product (product 6), 4 cycles of impregnation of the product with 3 bitumen were carried out with its portioned input into the salt product of 1.0 each; 1.3; 1.1 and 0.5 g. A total of 3.9 g of bitumen was added. The final monolith volume was 10 cm ³ . The total weight of product 3 with bitumen is 12.4 g. The weight percent filling of bitumen with salts was 68.5%.

The process of processing liquid radioactive waste at the concentration stage usually does not end. Storage of LRW concentrates in containers cannot be considered a reliable way of their final disposal. Therefore, an important link in the technology of handling (neutralizing) LRW of medium and low activity levels is the conversion of liquid concentrates into a solid and chemically inert form suitable for long-term storage [V.P.Shvedov, V.M.Sedov, I.L. Rybalchenko and other nuclear technology. Atomizdat, Moscow, 1979, p.224]. Moreover, almost all known methods of curing require deep dehydration of salt pulps.

There is a known thermal method for dehydration of LRW concentrates by evaporation to obtain a liquor (bottoms) containing a significant amount of salts and water. The content of free adsorbed and crystallization water in such concentrates can vary from 30 to 80%. For the thermal removal of free water, it is sufficient to provide the boiling point of saturated solutions of the compounds that make up the waste. In most cases, free and adsorbed moisture can practically be removed at temperatures below 150 ° C. Crystallization water is removed in a wide temperature range. If water molecules are introduced into the crystallization lattice and bind to salt molecules only by van der Waals forces, and if the structure of the crystal lattice is not determined by the specific position of the water molecules, dehydration can be carried out at temperatures up to 500 ° С. More complex processes occur when constitutional water is removed [A.S. Nikiforov, V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat, Moscow, 1985, pp. 72-73].

In practice, methods of freezing, centrifugation, etc. are also used at the stage of dehydration of LRW concentrates [V.P.Shvedov, V.M.Sedov, I.L. Rybalchenko, and others. Nuclear technology. Atomizdat, Moscow, 1979, p. 225-227] and [A.S. Nikiforov, V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat, Moscow, 1985, p.112-115]. Moreover, the methods of freezing and centrifugation do not provide complete dehydration of the pulps (the water content in the final product using centrifugation is 40-80%), and thermal dehydration allows the final product to be obtained with a moisture content of 9.0-22.0%. Deeper thermal dehydration (up to 1-2%) requires the use of complex vacuum dryers or high temperatures (350-400 ° C) [A.S. Nikiforov, V.V. Kulichenko, M.I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat, Moscow, 1985, p.112-115].

The proposed method, which is based on the thermal method, allows you to get almost anhydrous salt cake at the stage of concentration of LRW at temperatures of 150-200 ° C. A specific feature of the process of deep thermal concentration of bottoms by the proposed method is that the process of removing from the LRW all forms of water occurs in a hydrophobic coolant (glycerin). At the same time, both water and salts go through the stage of their dissolution in glycerol, followed by distillation of the water and the precipitation of anhydrous salt crystals, which is confirmed by the results of experiment No. 3.

Experiment number 3.

Stage of deep dehydration of LRW and drying of salt concentrate.

Experiments to assess the completeness of removal of free and crystallization water from model aqueous solutions of salts by the proposed method were carried out using salts of crystalline hydrates: sodium tetraborate Na ₂ B ₄ O ₇ 10H ₂ O (borax) and trisubstituted sodium orthophosphate Na ₃ PO ₄ 12H ₂ O, in open quartz glasses, at a temperature of 100-130 ° C (temperature, implemented in practice, when carrying out deep evaporation on standard equipment of nuclear power plants).

A predetermined amount of glycerol is introduced into a pre-weighed glass, then glycerin is heated to a temperature of 100-130 ° C and saturated aqueous salt solution is introduced into it in portions. In this case, the weight of anhydrous salt and the total weight of water are calculated: free water taken to prepare the solution, and crystallization water, which is part of the crystalline hydrate. After the experiment is completed, the glycerol-salt product formed in the glass is weighed and the material balance is calculated.

As a result of repeated experiments, it was shown that, under conditions of evaporation of aqueous solutions of salts in glycerol at temperatures of 100-130 ° С, an anhydrous, free of free and crystallization water, glycerol-salt product is formed (glycerin - salt crystals of Na ₃ PO ₄ , glycerin - salt crystals Na ₂ B ₄ O ₇ ).

In comparison with simple thermal evaporation, for example, of a borax solution to an anhydrous salt (Na ₂ B ₄ O ₇ , mp 741 ° C), heating of crystalline hydrate to a temperature above 400 ° C is required [B.N. Nekrasov. Fundamentals of General Chemistry, v.2. Chemistry, Moscow, 1967, p.169], which, of course, requires large energy costs.

The results of experiments No. 1-3 showed that glycerin - salt product obtained by the method - prototype, is a complex mixture of organic and inorganic substances, consisting of: pure (excess) glycerin; saturated, anhydrous glycerin solution of salts and water-insoluble products of partial thermochemical decomposition of glycerol.

The possibility of implementing the proposed method for curing glycerol-salt concentrate obtained by the prototype method by the method of its thermochemical transformation (synthesis) follows from the known chemical properties of glycerol and its use in the national economy. For example, it is known that the polyesters of glycerol and aromatic dibasic acid (phthalic acid) are of great practical importance. These polyesters are glycerol-phthalic resins, which are also called glyptals, are widely used for the manufacture of varnishes [A.A. Petrov, H.V. Balyan, A.T. Troshchenko. Organic chemistry. Higher School, Moscow, 1973, p.139]. The technology for producing glyptals from glycerol and phthalic anhydride (the number of components, synthesis temperature, time, etc.) is described in detail in [A.P. Grigoriev, O.Ya. Fedotova. Laboratory workshop on technology of plastic masses, part 2. Higher school, Moscow, 1977, p.93].

It is also known that phthalic acid is used in technology mainly in the form of phthalic anhydride to produce polyester resins [A.A. Petrov, H.V. Balyan, A.T. Troshchenko. Organic chemistry. Higher School, Moscow, 1973, p. 479].

Experiment No. 4

Stage of curing glycerin - salt concentrate by the method of its thermochemical transformation (synthesis of glyphthalic resin from phthalic acid and glycerin).

In an open quartz crucible heated to a temperature of 150 ° C with glycerol-salt concentrate (brine volume - 2.5 cm ³ , weight - 3.5 g, ρ-1.4 g / cm ³ ) phthalic acid is added in portions in an amount of 2 , 5 grams of acid per 1 gram of free glycerol (the amount of free glycerol and dry salts in brine is determined based on the results of experiment No. 1 and is about 1.05 g of glycerol and 2.45 g of dry salts), the resulting mixture is stirred in a crucible at a temperature 150-180 ° С until the phthalic acid is completely dissolved and a homogeneous mixture is obtained (salt crystals - solution f Alev acid in glycerol), and the mixture is subjected to agitation in a batch heat treatment at a temperature of 180-220 ° C for 4.5 hours, after which the product in the crucible was cooled to room temperature. Next, determine the volume of the formed monolith (5.0 cm ³ ), its weight (4.2 g) and calculate the% filling of the product with salts, which amounted to about 58 wt.% (Salt / product) and 50% vol. (brine / product).

The proposed method for the disposal of LRW of low and medium levels of activity has significant differences and advantages in comparison with the known technologies for their processing.

1. The method allows:

- carry out deep evaporation (concentration) of saline bottoms of LRW, their curing in the simplest in design apparatus, consisting of a heated tank (drum or barrel), and a gas treatment system for volatile gaseous products;

- the method does not require pre-conditioning of the original LRW;

- allows you to get a mobile (transportable) product at the finish stage of deep evaporation of LRW and drying glycerol-salt concentrate;

- at the stage of thermochemical transformation of glycerol-salt concentrate, return more than 30% of glycerol to the LRW processing cycle and at the finish receive a porous salt cake containing up to 34% of water-insoluble products of thermochemical decomposition of glycerol.

2. The curing process of radioactive salt concentrates (cake) is based on the previously unused method of impregnating a porous product with a wide range of known binders, and the impregnation process, which occurs due to the vacuum effect that occurs in the pores of the product when it is cooled, in comparison with the known methods, technological and energy-saving, does not require preheating of the used binder, and the process of monolithic salts is carried out at temperatures of 85 ° -150 ° C. For example, in the case of traditional bitumen using complex and metal-intensive screw sectional or rotary film bitumenizers, the bitumen temperatures are 140 ° -180 ° С and 230 ° -240 ° С, respectively [A.S. Nikiforov, V.V. Kulichenko, M .I. Zhikharev. Neutralization of liquid radioactive waste. Energoatomizdat, Moscow, 1985, p.126].

3. The fundamental difference between the curing of radioactive salt concentrates using organic polymer materials is that in the present method, it is proposed to use glycerol remaining in brine after carrying out the deep evaporation and drying stage of the LRW as one of the components in the synthesis of the polymer, which reduces its consumption in the processing cycle LRW also provides a high degree (58 wt.% And above) of the inclusion of radioactive salts in the matrix based on glyphthalic resin.

In addition, the inventive method for processing LRW can significantly simplify the entire process by eliminating the need for pre-conditioning of the original LRW (coagulation, sediment, filtering), the use of energy-intensive, cumbersome and structurally complex equipment and to obtain solid LRW disposal cycle at the end of the process monoliths packaged in containers (drums or barrels) for long-term storage.

The chemical and radionuclide composition of LRW generated during the operation and disposal of ships with nuclear power plants [R.A. Penzin, V.S. Sheptunov, V.K. Bulygin. RF patent No. 2112289. G21F 9/04, B01J 20/02, C02F 9 / 00.1998, Bull. No. 15, p.13-14] Structure Salt Free (Type 1) Water Decontamination (Type 2) Navy salt waste (type 3) Drainage water Water from SFA holding channels pH 7-12 7-12 6-12 6-9 salinity up to 0.1 g / l up to 0.1 g / l 0.5-4 up to 15 insoluble precipitate, g / l up to 0.05 up to 0.05 up to 0.015 up to 0.3 hydrazine, mg / l traces traces - Ca - up to 0.2 g / l; Mg - up to 0.2 g / l; Na - up to 0.2 g / l; Sr - up to 0.2 g / l ammonia, mg / l up to 50 up to 50 up to 50 Trilon B, mg / L - - up to 100 - chlorides, g / l traces traces up to 8 up to 8 nitrate, g / l traces traces up to 0.2 up to 0.2 sulfate, g / l - - - up to 0.8 phosphate, g / l traces traces up to 0.2 up to 0.2 oxalate, g / l - - up to 0.5 - Surfactant, mg / l - - up to 0.02 up to 0.02 petroleum products, mg / l - - until 3 until 3 total β-activity, Ku / g 10-5-10-6 10-5-10-7 10-5-10-7 (10-6-80%) 10-5-10-7 (10-6-80%) cesium (137 + 134),% 5-10 up to 70 up to 70 up to 70 strontium-90,% 5-10 up to 20 up to 20 up to 20 other active isotopes,% up to 70 (Ce-144) to 10 to 10 to 10 specific volume of the total amount of waste,% 13.5 1,5 51 34 amount of waste, m ³ / year 675 75 2550 1700

Claims (3)

1. A method of processing liquid radioactive waste, which consists in concentrating the waste by evaporation at a temperature of 105-150 ° C by feeding liquid radioactive waste into glycerin with a ratio in the evaporation zone of 1: 9-1: 1, characterized in that it is obtained in the process of concentration of liquid of radioactive waste salt glycerin concentrate is subjected to heat treatment at a temperature of 150-200 ° C, the resulting condensate of glycerol is returned to the processing cycle of liquid radioactive waste, and obtained after distillation of glycine The porous anhydrous salt product is solidified by introducing portions of the binder into it until a homogeneous monolithic block is formed, and after entering each portion of the binder, the product is cooled to a temperature of 85-95 ° C, and the subsequent portion of the binder is introduced after heating the product to a temperature of 105-150 ° C . 2. The processing method according to claim 1, characterized in that, for example, bitumen or polymeric materials are used as a binder. 3. A method of processing liquid radioactive waste, which consists in concentrating the waste by evaporation at a temperature of 105-150 ° C by feeding liquid radioactive waste into glycerin with a ratio in the evaporation zone of 1: 9-1: 1, characterized in that it is obtained in the process of concentration of liquid radioactive waste salt glycerin concentrate is cured by adding an additive in an amount of 1-3 g of reagent per 1 g of free glycerol, the resulting mixture is stirred at a temperature of 150-180 ° C until the additive is completely dissolved, then mixed and the mixture was subjected to heat treatment at a temperature of 180-220 ° C, then cooled to a temperature of 20-40 ° C to form a monolithic polymer product, and is used as an additive phthalic anhydride or phthalic acid.