RU2282906C2 - Method for decontaminating radioactive aqueous solutions - Google Patents

Abstract

FIELD: environment control including environment protection in atomic industry.

SUBSTANCE: proposed method for decontaminating radioactive aqueous solutions from radionuclides includes at least one contact of solution with complexing sorbent that has solid-medium immobilized active polymeric layer condensed with chelates. Medium is chosen from following group: activated cellulose; synthetic copolymers with divinyl benzene, activated chloromethyl or hydroxymethyl, or chlorosulfonic groups. Active sorbing layer has ethylenediamine or diethylene tridiamine, or tetraethylene pentaamine, or polyethylene polyamine with copolymers; chelates are chosen from group incorporating carboxyl-containing chelates, phosphonic-group chelates, and hydroxyl-containing chelates. Proposed method enables extraction of radionuclides both in ionic and colloidal condition from solutions doped with highly concentrated impurities; sorbent used for the purpose retains its sorbing properties upon repeated regenerations and is capable of decontaminating solutions both in dynamic and static modes with different pH of solutions being decontaminated.

EFFECT: enlarged functional capabilities.

11 cl, 3 tbl

Description

The invention relates to the field of ecology and environmental protection, specifically to the ecology of the nuclear industry.

The invention can be most effectively used in the processing of liquid radioactive waste (LRW) generated during the operation of nuclear power plants (NPPs) of the nuclear fleet (AF), nuclear power plants (NPPs), including loop, decontamination water, water from the reactor holding pools and protective tanks energy compartment of nuclear submarines and bottoms of special water treatment of nuclear power plants to extract radionuclides from the aqueous phase.

LRW are classified by specific activity and chemical composition, for example, depending on the salt content of water, they can be low-salt, salt, and high-salt.

In AF, due to the peculiarity of accumulation and storage, the salt background can be determined by the content of sea water and LRW differ in the content of hardness cations: 4-6 mEq / l in low-salt, 10 mEq / l in salt and 100 mEq / l in high salt waters, while the total salt content exceeds 20 g / l.

At NPPs, the salinity of LRW in low-salt waters does not exceed 1 g / l (loop water), in saline waters it is up to 40 g / l (decontamination water), and in high-salt waters (still bottoms) it exceeds 300 g / l.

By origin, LRW AF are approximately equal in proportion to the contour drainage water and decontamination water. More than 90% of the volume of these waters, with a specific beta activity of up to 370 kBq / l, are classified as weakly active LRW. In percentage terms, the radionuclide composition of typical LRW includes: cesium-137 (134) - up to 70; strontium-90 and yttrium-90 - up to 40; rare earth radionuclides: europium-154, cerium-144, etc. - up to 10, as well as antimony-124 (125), cobalt-60, manganese-54, zirconium-95, niobium-95, ruthenium-106 in total - up to 10. In atypical waters, the radionuclides of rare and rare-earth elements can account for more than 90% of the specific radioactivity, and strontium and cesium - up to 10%.

Typical radioactive solutions of nuclear power plants are low-salt water, in particular loop water, pool water, distillate evaporators and high-salt still bottoms of evaporators. Unlike AF radioactive waters, these waters contain almost no hardness salts. The main salt background of still bottoms of evaporators are nitrates, borates and sulfates of metals of the first group, the content of which can reach 400 g / l.

The radionuclide composition and salinity of LRW of nuclear submarines, after fuel unloading and prolonged stay in the sludge, as a rule, exceed the established operational requirements [V.A. Avramenko, I. S. Burkov, V. V. Zheleznov, K. A. Khokhlov Sorption -reagent processing of liquid radioactive waste from utilized nuclear submarines, Atomic Energy, 2002, vol. 92, issue 6, p. 456-459]. Pacific Fleet LRW contain 70-80% (Cs-137 + Cs-134), about 10-20% Sr-90, 5-10% (Zr-95, Nb-95, Rh-106, Co-60 and REE) . The total salinity reaches 5-10 g / l.

Among the main factors determining the state and form of the radionuclides in an aqueous solution is the pH value. The radionuclides of cesium-137 and strontium-90 in the entire range of LRW acidity are in ionic form, while cobalt-60 at pH> 7.5 is present in the form of stable colloids. Quantitatively soluble and insoluble forms of cobalt-60 are distributed approximately equally.

To ensure deep purification of radioactive water, depending on the radionuclide and chemical composition, various processing methods are used. At FSUE AF LRW, they are processed using the method described in patent RU, 2050027. The main volume of LRW of nuclear power plants is evaporated, then the distillate undergoes ion-exchange treatment, in which sorbents are periodically regenerated, and bottoms after evaporation are processed according to the method described in RU patent, 2050027. The water-chemical regime of transport nuclear power plants is provided using ion-exchange resins without material regeneration. For the processing of LRW in nuclear submarines, the baromembrane method is used, followed by purification on ion-exchange resins or selective sorbents, the method of coagulation and coprecipitation on hydroxides, followed by ion exchange, or simply sorption purification on selective sorbents.

There is a method of galvanic chemical treatment of radioactive solutions formed at the enterprises of the nuclear industry, which consists in the fact that air or an ozone-air mixture is dispersed in the solution being treated, after which a galvanic pair of iron - coke or cast iron - coke is passed through a vibrating boil, the pH of the medium is adjusted alkali with the addition of montmorillonite clay, and then the solid phase is separated [RU, 2147777, G 21 F 9/06].

A known method of purification of liquid radioactive waste from radionuclides, including processing by ozonation at pH 7-8 to change the pH by 0.2-0.6, followed by filtration through clinoptilolite [RU, 2083009, G 21 F 9/06].

A known method of processing liquid waste containing radionuclides by ozonizing in the presence of a catalyst an oxidation process and / or a collector for extracting radionuclides at a temperature of 30-80 ° C and a solution pH of 10-13, using sparingly soluble transition metal sulfides, mainly cobalt, as a precipitant [RU , 2122753, G 21 F 9/06].

A known method of purification of solutions from radionuclides, consisting of two successive stages of selective extraction of radionuclides: on the first - passing LRW solutions through a composite ferrocyanide sorbent based on a porous silicate or aluminosilicate carrier and copper or nickel ferrocyanide to separate cesium radionuclides, and on the second - a solution of LRW , having passed the first stage, is passed through type A zeolite or a tetravalent metal hydroxide, which is used as zirconium, titanium or manganese hydroxide tsa, additionally containing an inert binder, for the extraction of strontium radionuclides [RU, 2050027, G 21 F 9/12].

The disadvantages of the known methods for cleaning LRW, regardless of the nature of their origin, are the significant influence of impurities of alkaline-earth metals (elements of the second group of the Periodic system) on the efficiency of extraction of radionuclides, insufficiently high coefficient of purification of LRW with high salinity, low degree of purification of LRW from radionuclides in water in the form of stable colloids, as well as the inability to regenerate the sorbent.

Increasing the efficiency of the sorption properties of materials when cleaning LRW containing interfering impurities by known methods requires a preliminary reduction in their concentration, and the extraction of non-absorbable radionuclides, such as cobalt-60 and yttrium-90, requires the organization of additional purification stages: coagulation, ozonation with ultrafiltration, etc.

The closest is the method for extracting metal ions and the complexing structure described in [WO 02/18050 A1], in which a solution containing ions is passed through a complexing structure containing a substrate onto which a polymer or copolymer organic, electrically neutral film capable of forming complexes with ions. As a substrate, a material consisting entirely of a conductor or a semiconductor of electricity was selected, representatives of various classes of organic compounds were selected as complexing structures, and 4-vinylpyridine, vinylbipyridine, thiophene, vinylferrocene and vinyldiferrocene were used as monomers to form a polymer film.

The disadvantages of this method are the limited assortment of recoverable ions, the impossibility of extracting elements in a colloidal state, as well as the lack of selectivity of ion extraction against the background of a high concentration of interfering impurities.

The aim of the present invention is to increase the efficiency of cleaning various types of radioactive aqueous solutions from radionuclides in the presence of hardness salts.

The goal was solved by developing a method for cleaning aqueous solutions of radionuclides, including contacting the aqueous solution with a complexing sorbent, in which the carrier is made of pre-epoxidized cellulose or a synthetic copolymer of styrene with divinylbenzene, preactivated with chloromethyl or hydroxymethyl, or chlorosulfonic, or phenol-formaldehyde groups pre-activated sulfo groups, and the active sorbent polymer layer contains polymer condensed with complexones.

Moreover, according to the invention, in the complexing sorbent, the polymer of the active sorbent layer is a polymer selected from the group consisting of ethylene diamine or diethylene triamine or triethylenetetraamine or tetraethylene pentamine or a polymer amine or ethylene diamine condensed with copolymers.

Moreover, according to the invention, in the complexing sorbent, the polymeric amine is polyethyleneimine.

Moreover, according to the invention, in a complexing sorbent, the solid carrier comprises cellulose selected from the group consisting of microcrystalline cellulose or fibrous cellulose, or waste from processing plant materials.

Moreover, according to the invention, in a complexing sorbent, the solid carrier comprises a composition of activated synthetic polymers.

Moreover, according to the invention, in the complexing sorbent, the polymer of the active sorbent layer is condensed with the same complexons.

Moreover, according to the invention, in the complexing sorbent, the polymer of the active sorbent layer is condensed with various complexones.

Moreover, according to the invention, the complexones in the complexing sorbent are selected from the group consisting of carboxyl-containing complexones with the fragment —NHCH ₂ COOH, —N (CH ₂ COOH) ₂ , complexones with phosphonic groups —N (CH ₂ PO ₃ H ₂ ) ₂ , hydroxyl-containing complexones with fragments: = NCH ₂ CH ₂ OH, HOCH ₂ CH ₂ -N-CH ₂ COOH, HOCH ₂ CH ₂ -N-CH ₂ PO (OH) ₂ .

Moreover, according to the invention, in the complexing sorbent, the active sorbent layer contains complexones in any combination and in any quantitative ratio.

Moreover, according to the invention, in the complexing sorbent, the active sorbent layer contains a polymer amine as a polymer, which is selected from the group consisting of polyethyleneimine with an average molecular weight of from about 250 to about 50,000.

In addition, according to the invention, after contacting with an aqueous solution, the spent complex-forming sorbent is regenerated with mineral acid.

Moreover, according to the invention, the mineral acid is selected from the group comprising nitric acid, hydrochloric acid, sulfuric acid.

In addition, according to the invention, the contacting of the aqueous solution is carried out with a regenerated complexing sorbent.

The invention is further illustrated by examples of the method according to the invention, however, not limiting the scope of the present invention, in which complexing sorbents according to the invention, the composition of which are presented in Table 1, were used to purify radioactive aqueous solutions of various compositions.

Table 1 Sorbent number Description of the sorbent one Sulfochlorinated copolymer of styrene with divinylbenzene, sequentially treated with polyethyleneimine with an average molecular weight of 5000, then derivatives of diethylene triamine N, N, N, N, N-pentaacetic acid 2 Chloromethylated styrene-divinylbenzene copolymer sequentially treated with polyethyleneimine with an average molecular weight of 250, then N, N, N, N-tetraacetic acid derivatives of ethylenediamine 3 Sulfonated phenol-formaldehyde resin sequentially treated with polyethyleneimine with an average molecular weight of 50,000, then derivatives of 1-hydroxyethylene diphosphonic acid four An oxymethylated styrene-divinylbenzene copolymer sequentially treated with polyethyleneimine with an average molecular weight of 12,000, then with a mixture of N- (2-hydroxyethyl) glycine derivatives and N, N, N, N-tetraacetic acid ethylenediamine 5 Microcrystalline cellulose of the Avicel brand, E. Merk company (Germany), sequentially treated with epichlorohydrin, polyethyleneimine with an average molecular weight of 1,500, then derivatives of aminodiacetomethylene phosphonic acid 6 Fibrous cellulose sequentially treated with epichlorohydrin, polyethyleneimine with an average molecular weight of 20,000, then N- (2-hydroxyethyl) glycine 7 Sawdust of coniferous trees sequentially treated with epichlorohydrin, polyethyleneimine with an average molecular weight of 7000, then with a mixture of iminodimethylenephosphonic acid derivatives 8 Sawdust of deciduous trees sequentially treated with ethylenediamine, then with a mixture of iminodimethylenephosphonic acid derivatives and ethylenediamine-N, N, N, N-tetraacetic acid 9 Sulfonated phenol-formaldehyde resin sequentially treated with a copolymer of propylene with ethyleneimine with an average molecular weight of 3000, then glycine phosphonic acid. 10 Sulfochlorinated copolymer of styrene with divinylbenzene, sequentially treated with tetraethylene pentamine, then aminodiacetomethylene phosphonic acid eleven Chloromethylated styrene-divinylbenzene copolymer, sequentially treated with diethylene triamine, then with a mixture of N- (2-hydroxyethyl) aminoacetic acid derivatives and 1-hydroxyethylidene diphosphonic acid.

The study of the properties of the sorbents according to the invention was carried out in dynamic and static conditions in the saturation mode according to GOST 20255-84 from solutions of various compositions and under various modes.

The radionuclide composition of the solutions was determined on a tested DSA-1000 LGN spectrometer with a semiconductor detector, and the instrument was calibrated using standard samples.

All batches of LRW before the study were purified from cesium-137 (134) on nickel ferrocyanide.

Methods of spectrometric measurements and passports of calibration samples were developed by VNIIM. Mendeleev. The content of strontium-90, yttrium-90 radionuclides after purification was determined radiometrically on a KRK instrument, cobalt-60 on a DSA-1000, according to standard methods. The concentration of stiffness cations was determined trilonometrically according to GOST 4151-77.

Under dynamic conditions, sorbent was loaded into laboratory glass columns in an amount providing a ratio of the loading height to the loading diameter equal to 1: 5. The studied sample of the sorbent was washed with water, kept for swelling, then the water was drained and from the pressure tank with the solution in the direction from top to bottom, a stream of the solution to be purified was applied at a constant speed equal to 15 column volumes per hour.

The Koc purification coefficient was calculated as the ratio of the initial concentration of radionuclides to the concentration in the sample after the column. The value of the sorbent resource was calculated according to GOST 20255.2 p.5.1 according to the volume of the solution, expressed in units of volume of air-dry sorbent (column volume - Cob) with a density of 0.8 g / ml (for sorbents based on synthetic polymers), passed through the sorbent until radionuclides in the filtrate.

Regeneration of the sorbent was carried out by passing two column volumes of diluted mineral acids, then washing the sorbent with distilled water until the neutral reaction of wash water. After regeneration, the sorbent resource decreased by about 20%.

The distribution coefficients of radionuclides in static conditions were determined at pH values from 5.5 to 11.0. The work was carried out according to the standard method described, for example, in TU 95-2726-99 for ferrocyanide material. To perform the experiment under static conditions, 100 ml of LRW was added to a 0.25 g sorbent sample. The mixture was stirred on a magnetic stirrer for 30 minutes, the sorbent was filtered on a Schott filter, the filtrate was analyzed for radionuclide content by known methods.

The calculation of the distribution coefficient was carried out according to the formula:

Kd = (C ₁ -C ₂ ) / C ₂ × V / m, ml / g,

where C ₁ is the concentration of radionuclides in the initial solution;

C ₂ is the concentration of radionuclides in the solution after contact with the sorbent;

V is the volume of the solution in contact with the sorbent, ml;

m - sorbent mass, g.

The filtered sorbent was transferred to a flask, 10 ml of 2 molar nitric or hydrochloric or sulfuric acid was added, stirred for 15 minutes and filtered on a Schott filter, washed with distilled water until the washings were neutral and used again.

To study the sorbents proposed in the method, real LRW of transport nuclear power plants were used, in which the content of hardness cations, as well as simulation solutions, were changed by adding salts.

The compositions of LRW taken for cleaning, including their radionuclide composition and total salt composition, are given in Table 2.

table 2 No. of the purified solution Radionuclide composition of LRW * Saline composition of LRW ** Note one Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95, Rb-106, Eu-152, Eu-154 Y-90 Ammonia ~ 0.05 g / l A mixture of decontamination LRW AF. Nitrates ~ 0.2 g / l Phosphates ~ 0.2 g / l Sulphates ~ 0.8 g / l Suspension ~ 0.15 g / l Chlorides ~ 1.2 g / l Oil products ~ 2.5 mg / l 2 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95 Rb-106, Eu-152, Eu-154, Y-90 Hydrazine Hydrate ~ 0.1 g / L A mixture of contour and decontamination LRW. Chlorides ~ 1.2 g / l Nitrates ~ 0.2 g / l Phosphates ~ 0.2 g / l Sulphates ~ 0.8 g / l Suspension ~ 0.15 g / l 3 Sr-89, Sr-90, Co-58, Co-59, Co-60, Mn-54, Sb-125 Hydrazine Hydrate ~ 0.2 g / L Drained and flushing water of technological circuits. Ammonia ~ 0.05 g / l Dense residue ~ 10 mg / L four Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95 Ammonia ~ 10 mg / L A mixture of decontamination LRW. Nitrates ~ 0.2 g / l Phosphates ~ 0.3 g / l Borates ~ 2.3 g / l 5 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95, Eu- Ammonia ~ 40 mg / L, A mixture of decontamination LRW. Nitrates ~ 0.6 g / l Surfactant ~ 500 mg / l

152, Eu-154, Eu-155 Oil products ~ 5.5 mg / l 6 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95, Cr-51 Ammonia ~ 40 mg / L, A mixture of decontamination LRW. Nitrates ~ 0.6 g / l Surfactant ~ 500 mg / l Oil products ~ 5.5 mg / l Trilon B ~ 150 mg / L 7 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95, Cr-51 Ammonia ~ 10 mg / l LRW simulation solution Nitrates ~ 0.4 g / l Sulphates ~ 0.15 g / l Surfactant ~ 0.5 g / l Oil products ~ 5.5 mg / l 8 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-55, Fe-59, Zr-95, Nb-95 Nitrates ~ 0.2 g / l LRW simulation solution Phosphates ~ 0.3 g / l Borates ~ 4.3 g / l Chlorides ~ 0.2 g / l Surfactant ~ 2.5 g / l Oil products ~ 7.5 mg / l 9 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-55, Fe-59, Zr-95, Nb-95 Ammonia ~ 10 mg / l A mixture of decontamination LRW. Nitrates ~ 0.4 g / l Sulphates ~ 0.15 g / l Surfactant ~ 0.5 g / l Oil products ~ 5.5 mg / l 10 Sr-89, Sr-90, Co-60, Mn-54 Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95, Eu-152, Eu-154, Eu-155 Ammonia ~ 40 mg / L, A mixture of decontamination LRW. Nitrates ~ 0.6 g / l Surfactant ~ 0.5 g / l Oil products ~ 5.5 mg / l eleven Sr-89, Sr-90, Co-60, Mn-54 Hydrazine Hydrate ~ 100 mg / L Imitation

Ce-141, Ce-144, Sb-125, Fe-59, Zr-95, Nb-95, Eu-152, Eu-154, Eu-155 Chlorides ~ 0.2 g / l
Oil products ~ 5.5 mg / l
Surfactant ~ 200 mg / l solution * The main radionuclides are presented.
** The main anions are presented.

The results of LRW treatment are presented in table 3

Table 3 The number of the solution to be purified, sorbent No. Mode The initial specific activity of Bq / l Salinity g / l The concentration of total hardness (the sum of the cations of calcium and magnesium) mEq. / L pH K.och amounts of radionuclides in dynamic mode or distribution coefficient Kd in static mode. Sorption capacity for hardness cations (calcium and magnesium, mEq. / G 1,1 dynamic 1.2 × 10 ⁸ 5,0 5,4 7.5 an average of about 2500, a resource of about 2600 k.ob. about 3800 1.3 dynamic 1.2 × 10 ⁸ 5,0 5,4 7.5 about 2400, resource about 2300 about 3600 2.2 dynamic 3.4 × 10 ⁸ 4.2 3.2 8.7 about 2400, resource about 2800 about 3400

cob. 3.3 dynamic 7.5 × 10 ⁷ 0.1 - 8.0 about 2700, resource about 2350 k.ob. about 3000 3.11 dynamic 7.5 × 10 ⁷ 0.1 8.0 about 2850, resource about 2430 k.ob. about 3200 4.4 dynamic 4.6 × 10 ⁷ 0.5 5.3 6.0 about 2300, a resource of about 2500 k.ob. about 2800 5.5 static 6.7 × 10 ⁸ 5,4 5,0 11.0 Kd 1.0 × 10 ⁴ for magnesium - about 3700, for calcium - about 3600 5.7 static 6.7 × 10 ⁸ 5,4 5,0 11.0 Kd 1.0 × 10 ³ For magnesium about 2800, for calcium - about 2300 6.6 static 5.1 × 10 ⁷ 4.0 15.0 11.0 Kd 8.8 × 10 ³ about 3000 7.7 static 5.1 × 10 ⁸ 4.0 14.0 7.0 Kd 9.0 × 10 ³ about 3200 8.8 static 6.3 × 10 ⁷ 15.0 8.0 5.5 Kd about

sky 1.4 × 10 ⁴ 3100 8.10 dynamic 6.3 × 10 ⁷ 15.0 8.0 5.5 about 3100, resource about 2600 about 2800 9.9 dynamic 7.4 × 10 ⁸ 3.0 1,5 7.7 about 2700, resource about 2600 k.ob. about 3500 10.10 dynamic 7.4 × 10 ⁸ 0.1 0.5 9.0 about 3000, resource about 2400 about 2800 11.11 dynamic 1.2 × 10 ⁹ 40,0 8.0 8.0 about 1800, resource about 1600 about 2000

As follows from the above examples, the purification of radioactive aqueous solutions by the method according to the invention allows to extract radionuclides of different groups of the Periodic system, which are in solution both in ionic and in colloidal state, from solutions having a high concentration of interfering impurities. Moreover, the complexing sorbent used in the method according to the invention retains its sorption properties after repeated regenerations, while the sorption capacity of cellulose-based sorbents decreased by 12-15%, and the sorption capacity based on synthetic polymers decreased by 20-22%. The method according to the invention allows the purification of radionuclides in both dynamic and static modes, at different pH of the solutions being cleaned.

Although the present invention has been described in connection with preferred embodiments, it is understood that there may be changes and variations to the purification method without departing from the spirit and scope of the invention.

Professionals working in the field of LRW processing should understand that this method may contain additional stages, in particular, preliminary chemical treatment of radioactive solutions, which provides greater cleaning efficiency.

The complexing sorbents used in the method according to the invention can be manufactured on an industrial scale using inexpensive raw materials using low-waste technologies.

Claims (12)

1. The method of purification of aqueous solutions of radionuclides, comprising at least once contacting the solution with a complexing sorbent containing an active sorbent polymer layer immobilized on an activated solid carrier, characterized in that the contacting is carried out with a sorbent in which the carrier is made of activated cellulose or a synthetic styrene-divinylbenzene copolymer preactivated with chloromethyl or hydroxymethyl or chlorosulfonic groups, or a hair dryer lformaldegidnoy resin previously activated sulfonic and the active sorbent layer comprises a polymer condensed with chelators. 2. The method according to claim 1, characterized in that in the complexing sorbent, the polymer of the active sorbent layer is a polymer selected from the group consisting of ethylene diamine, or diethylene triamine, or triethylene tetraamine, or tetraethylene pentamine, or a polymer amine, or ethylene diamine condensed with copolymers. 3. The method according to claim 1, characterized in that in the complexing sorbent, the polymer is a polymer amine, and the polymer amine is polyethyleneimine. 4. The method according to claim 1, characterized in that in the complexing sorbent, the active sorbent layer contains as a polymer a polymer amine selected from the group consisting of polyethyleneimine with an average molecular weight of from about 250 to about 50,000. 5. The method according to claim 1, characterized in that in the complexing sorbent, the solid carrier comprises cellulose selected from the group comprising microcrystalline cellulose, fibrous cellulose or waste from processing plant materials. 6. The method according to claim 1, characterized in that in the complexing sorbent, the solid carrier comprises a composition of activated synthetic polymers. 7. The method according to claim 1, characterized in that in the complexing sorbent, the polymer of the active sorbent layer is condensed with the same complexons. 8. The method according to claim 1, characterized in that in the complexing sorbent, the polymer of the active sorbent layer is condensed with various chelators. 9. The method according to claim 1, characterized in that in the complexing sorbent, the complexones are selected from the group consisting of carboxyl-containing complexones with the fragment —NHCH ₂ COOH, —N (CH ₂ COOH) ₂ , complexones with phosphonic groups —N (CH ₂ PO ₃ H ₂ ) ₂ , hydroxyl-containing complexons with fragments = NCH ₂ CH ₂ OH,

10. The method according to claim 8, characterized in that in the complexing sorbent, the active sorbent layer contains complexones selected from the group consisting of carboxyl-containing complexones with a fragment —NHCH ₂ COOH, —N (CH ₂ COOH) ₂ , complexones with phosphonic groups —N (CH ₂ PO ₃ H ₂ ) ₂ , hydroxyl-containing complexons with fragments = NCH ₂ CH ₂ OH,

in any combination and any quantitative ratio. 11. The method according to claim 1, characterized in that after contacting with the aqueous solution, the spent complexing sorbent is regenerated with mineral acid. 12. The method according to claim 11, characterized in that the mineral acid is selected from the group comprising nitric acid, hydrochloric acid, sulfuric acid.