JP2014142336A - Glassification body of radioactive waste and formation method thereof - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a glassification body that glassifies sludge mainly comprising barium sulfate and is excellent in chemical durability without an enclosed radioactive substance flowing out to the outside of the glassification body.SOLUTION: A glassification body contains a radioactive waste comprising sludge containing barium sulfate occurring when contaminated water containing a radioactive substance is treated by an agglutination precipitation method using barium sulfate as agglutinant, at a composition ratio of the residual material of sludge, in which FeOis omitted, of 16-30%, the residual material of sludge, in which POis omitted, of 30-63%, and the residual material of sludge, in which a sulfur constituent is omitted, of 7-50%, in terms of mol%.

Description

  The present invention vitrifies vitrified radioactive waste, particularly sludge containing, as a main component, barium sulfate generated when contaminated water containing radioactive material is treated by a coagulation-precipitation method for producing barium sulfate as a flocculant. The present invention relates to a solidified body and a method for forming the same.

  Currently, various efforts are being made to converge the accident at the Fukushima Daiichi Nuclear Power Station, and one of the important issues is the high concentration of radioactive materials in the Unit 1-4 buildings. It is the removal and storage of radioactive material contained in stagnant water. As a method for removing radioactive substances from the staying water, a sorption method or a coagulation precipitation method is used.

  As a method for removing radioactive substances from the accumulated water, a method according to Non-Patent Document 1 is known. In this method, as a first step, antimony and α radioactive element contained in the stagnant water are precipitated and separated from the stagnant water, cesium is removed as a second step, ruthenium is removed as a third step, As a fourth step, strontium is removed. In the fourth step, strontium is removed by a coagulation precipitation method. This coagulation sedimentation method uses a method (for example, Non-Patent Document 2) in which strontium in staying water is coprecipitated with barium sulfate.

In the second step, potassium insoluble ferrocyanides residence water (hexacyano nickel (II) iron (II) acid _{(K 2-x Ni x /} 2 [NiFe (CN) 6] · nH 2 O, and abbreviation KNiFC The cesium in the retained water is adsorbed on the insoluble ferrocyanide, and then left to settle to remove cesium from the retained water.

  In the coagulation sedimentation method, a slurry-like waste liquid in which barium sulfate and strontium (Sr) are co-precipitated is called sludge. This sludge must be managed and stored until the radioactivity is reduced. However, since this sludge is a slurry-like liquid, it is difficult to handle and is preferably converted into a solidified product. Examples of such a solidified product include a glass solidified product.

  Further, in the above-described method for removing radioactive substances from stagnant water, sludge may be formed in a state in which the sludge is mixed with precipitates generated in the first step, the second step, and the third step. Conceivable.

  The stagnant water contains seawater components injected into the reactor during the process of cooling the reactor, and the sludge may contain seawater components.

  Conventionally, research on vitrification of radioactive waste has been continued in order to stably store spent fuel generated at nuclear power plants and radioactive waste generated at reprocessing facilities for a long period of time. And borosilicate glass was used as glass of the vitrification body of a radioactive waste.

Moreover, as a method using other than borosilicate glass, PbO—B ₂ O ₃ —ZnO-based, PbO—B ₂ O ₃ —SiO ₂ -based glass (Patent Document 1), and magnesium phosphate-based glass (Patent Document 2). , Method of solidifying waste liquid mainly composed of sodium nitrate after reprocessing of spent fuel with iron phosphate glass (Non-patent Document 3), Method of solidifying high-level radioactive waste with iron phosphate glass (Non-Patent Document 4) has been proposed.

SGN, ANDRA, “Waste Treatment at the La Hague and Marquesite Sites”, ES / WM-49 (1995). Tsutsui Tenson et al., "Processing of high salinity radioactive liquid waste by chemical coprecipitation (I)", Health Physics, 15, 33-39 (1980) R. D. Leessen, Iron Phosphorate Glass for the Vitrification of INEEL Sodium Bearding Waste and Hanford Low Activity Waste, University of Missouri 2 (Roll). Ippei Amamoto et al. “Radioactive waste solidification technology using phosphate glass”, NEW GLASS Vol. 22, no. 2, p21-26 (2007)

JP 2003-050297 A Japanese Patent Laid-Open No. 2005-207885

  As described above, the vitrification technology of radioactive waste has been mainly performed for radioactive waste generated during reprocessing of spent fuel. However, most methods have been studied for vitrifying sludge generated when coagulating and precipitating radioactive materials contained in contaminated water such as stagnant water accumulated in the reactor building and radioactive wastewater discharged from nuclear facilities. Not.

Borosilicate glass has a problem that it is difficult to confine a large amount of waste in a vitrified body, and when there are many ions and phosphate components in the waste, the leaching rate for water increases. . In addition, if the filling rate of radioactive waste components is greater than 25 wt%, a phase separation phenomenon in which precipitates containing the waste components as a main component occurs, resulting in a decrease in the performance of confining the radioactive waste components in the vitrified body. There was a problem to do. Moreover, when sulfur oxides such as SO ₂ , phosphates such as P ₂ O ₅ , and chlorides such as NaCl increase in the radioactive waste, the phase separation tendency of the glass is promoted, There was a problem that the stability of the vitrified body was lowered.

  Furthermore, when vitrifying the sludge containing sulfate generated when the contaminated water containing radioactive material is processed by the coagulation sedimentation method that generates barium sulfate in the contaminated water, when using borosilicate glass, There was a problem that the solubility of the sulfuric acid component in the glass was low, and the sulfate was deposited on the surface of the vitrified body.

  An object of the present invention is to provide a solidified body excellent in chemical durability by vitrifying the sludge containing the sulfate with a high filling effect.

The present invention relates to a vitrified material obtained by vitrifying radioactive waste with iron phosphate glass containing Fe ₂ O ₃ and P ₂ O _5, and sludge containing the barium sulfate is vitrified and confined in the vitrified body. An object of the present invention is to provide a vitrified body capable of stably storing radioactive materials contained in the sludge so as not to leak to the outside, and a vitrification method for the sludge.

  That is, in the present invention, in the process of heating and melting the sludge containing barium sulfate with iron phosphate glass, barium sulfate decomposes and sulfur components gasify and fly. As a result, a glass solid with a uniform structure that does not precipitate on the surface is formed, a structurally stable glass solid is obtained, and it is possible to prevent the radioactive material confined as the glass solid from flowing out to the outside. it can.

  In the present invention, not only barium sulfate but also strontium coprecipitated with barium sulfate can be vitrified in a structurally stable state.

In the above-mentioned vitrification method, the iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ is mixed with the sludge containing the barium sulfate and then heated to melt the glass together with the sludge, or The iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ and the barium sulfate are heated while being supplied to a melting furnace, mixed in the melting process, and the sulfur component is removed by volatilization. Then, it is cooled and solidified. At this time, the composition ratio of the residue of sludge from which the Fe ₂ O ₃ , P ₂ O ₅ and sulfur components are removed is 16% to 30%: 30% to 63%: 7% to 50% in mol%. The glass composition, the mixing ratio of glass and sludge, the heating temperature, and the heating time are adjusted so that the glass solidified body is constituted. When the sludge is vitrified by the vitrification method of the present invention, it is preferable that a compositionally stable vitrified body can be obtained by making such a composition ratio.

Moreover, in the above-mentioned vitrification processing method, the composition ratio of the residue of sludge from which Fe ₂ O ₃ , P ₂ O ₅ and sulfur components are removed is 25% to 32%: 40% to 53%: 20 in mol%. You may make it a vitrified body be comprised by% -32%. From the viewpoint of securing storage space, it is preferable to vitrify so that the composition ratio of the residue of sludge from which the sulfur component has escaped is larger than 32%, but when a large amount of sludge is confined in the vitrified body, There is a possibility that the long-term stability of the vitrified body may be lowered, and further, the decay heat of the radioactive material contained in the sludge is generated, which may impair the stability of the vitrified body structure. In order to avoid this possibility, it is more preferable to set the composition ratio of the residue of sludge from which the sulfur component has been removed in the vitrified body within such a range.

  In the above-mentioned vitrification method, the sludge may further contain an insoluble ferrocyanide, and the sludge residue of the vitrified body contains an oxide derived from the insoluble ferrocyanide. It may be.

The oxide derived from the insoluble ferrocyanide is mixed with iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ and the sludge, and then heated in an atmosphere containing sufficient oxygen. In the process of melting, the cyano group constituting the insoluble ferrocyanide is decomposed, and the nickel, iron, and potassium constituting the insoluble ferrocyanide are mainly oxidized. Even if the oxide derived from such an insoluble ferrocyanide is contained in the sludge residue of the vitrified body, a structurally stable vitrified body can be obtained.

Moreover, the said sludge may contain the component derived from seawater further, and the oxide derived from the said seawater may be contained in the sludge residue of this glass solidified body. The oxide derived from seawater contains NaCl, MgCl contained in seawater components when iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ and the sludge are mixed, heated and melted. ₂ , MgSO ₄ , CaSO _4, etc. are produced in the process of oxidation. Even if such an oxide derived from seawater is contained in the sludge residue of the vitrified body, a structurally stable vitrified body can be obtained.

  According to the present invention, sludge containing barium sulfate as a main component can be confined and vitrified in a vitrified body without depositing a sulfur compound on the vitrified body surface, and a structurally stable phase separator. It is possible to provide a homogeneous solidified glass body, so that radioactive materials confined in the solidified glass body are excellent in chemical durability without flowing out of the solidified glass body. It becomes possible.

  Details of the present invention will be described below.

<Components of iron phosphate glass used in the present invention>
The iron phosphate glass itself used in the present invention is a kind of known glass and refers to a glass mainly composed of Fe ₂ O ₃ and P ₂ O ₅ . This glass is a network that is governed by easily _P 2 _O ^{7 4-,} hydrolysis, by taking a structure in which Fe (II) -Fe (III) polyhedron -O _n is chained, less prone to hydrolysis A chemically stable Fe-OP network can be formed.

When the glass is composed of two components, Fe ₂ O ₃ and P ₂ O ₅ , Fe ₂ O ₃ absorbs moisture in the air in the P ₂ O ₅ glass and has a property of taking a stable structure. It is a component that is essential for stabilizing the glass and is desirably contained in the range of 10 to 50 mol%. P ₂ O ₅ is a main component of glass and is an essential component for efficiently solidifying sludge, and is desirably contained in a range of 40 to 80 mol%.

As other components, in order to improve the heat resistance and chemical stability of the glass, the total amount of (Al ₂ O ₃ + B ₂ O ₃ + SiO ₂ + TiO ₂ + ZrO ₂ ) is within a range of 10 mol% or less, and In order to obtain a vitrified body without improving crystallization by improving meltability and by improving workability, the total amount of R ₂ O (Li ₂ O + Na ₂ O + K ₂ O) is 15 In order to improve the heat resistance and chemical stability while further improving the meltability of the glass in the range of mol% or less, the total amount of R′O (MgO + CaO + SrO + BaO + ZnO) is contained in the range of 15 mol% or less. It doesn't matter. In addition to this, F ₂ , Cl _2, etc. may be added up to 5 mol% within a range not impairing the above properties.

Here, _Fe in 2 _{O 3} is less than 10 mol% is insufficient improvement in the hygroscopicity, while easily crystallized exceeds 50%, the vitrification becomes difficult, _Fe 2 _{O 3} is 10 to The range is 50%, preferably 10 to 40%, more preferably 20 to 40%. Since P ₂ O ₅ is the main component of glass, if it is less than 40%, it becomes difficult to form glass. On the other hand, if it exceeds 80%, the moisture resistance of the glass is remarkably deteriorated, so P ₂ O ₅ is 40 to 80%. , Preferably 50 to 80%, more preferably 55 to 75%. Further, the mole percentage of Fe ₂ O ₃ may be 10 to 50%, and the mole percentage of P ₂ O ₅ may be 40 to 90%.

In the present invention, iron phosphate glass containing such Fe ₂ O ₃ and P ₂ O ₅ and sludge mainly composed of barium sulfate are mixed, and then heated and melted to remove sulfur components. A residue mainly composed of barium oxide that remains later is taken into the network structure without breaking the network to obtain a vitrified body.

<The manufacturing method of the iron phosphate glass of this invention>
The production of iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ is as follows. (1) Iron oxide is used as the Fe ₂ O ₃ source, normal phosphoric acid, diammonium hydrogen phosphate, or ammonium dihydrogen phosphate is used as the P ₂ O ₅ source, and they are mixed in a predetermined ratio. The mixture is charged into a melting furnace formed of silicon carbide or zirconia boride having excellent conductivity and heat resistance, or alumina or zirconia having non-conductivity and excellent heat resistance, and heated and melted.

  (2) The glass melt is produced by pouring the melt onto a carbon mold or passing the melt through a water-cooled roll. (3) The said glass lump is crushed finely and iron phosphate glass is produced.

Here, the melting temperature is adjusted between 1000 ° C. and 1400 ° C. so that a homogeneous melt can be obtained. The temperature is adjusted within this temperature range because melting of the mixture is difficult at a temperature lower than 1000 ° C., and a homogeneous glass melt cannot be obtained. On the other hand, when the temperature exceeds 1400 ° C., P ₂ O ₅ This is because volatilization of the glass becomes remarkable, and it becomes difficult to form a glass solid having a desired glass composition.

  In addition, the melting time requires a time sufficient to obtain a homogeneous melt, and depends on the amount of the mixture to be melted in one batch and the energy to be charged to heat the mixture. 5 to 5 hours is a guide.

  Here, if one lump is crushed to 30 mm or less, the iron phosphate glass is easily melted when heated and melted, and a homogeneous melt can be obtained in a shorter time. However, the iron phosphate glass used in the present invention is mixed with the sludge and then heated and melted, or mixed with the sludge and heated while being supplied to the melting furnace, respectively. As long as it is suitable, it can take the form of scales, powders, fibers, etc. regardless of the shape.

<Sludge vitrified by the vitrification method of the present invention>
The sludge to be vitrified by the vitrification method of the present invention adds barium nitrate and sulfuric acid as coagulants to water containing radioactive substance ions and fine particles generated in the process of coagulating and precipitating radioactive substances such as strontium. In this way, barium sulfate that is sparingly soluble in water is formed, and the barium sulfate and the ions contained in the water are combined with sulfate ions to form a sulfate compound such as sparingly soluble strontium sulfate. Is caused by The composition of the sludge is mostly barium sulfate used as a flocculant. In the case of waste water containing a small amount of a sulfate compound such as strontium sulfate and salt, a small amount of calcium sulfate is included.

<Chemical change during heating and melting of iron phosphate glass and sludge>
In the vitrification method of the present invention, the iron phosphate glass and the sludge containing barium sulfate are uniformly mixed with the iron phosphate glass and the sludge containing barium sulfate by a mixing device such as a rotary rocking powder mixer. Then, the mixture is heated in an air atmosphere to melt the glass and sludge, and mixed to form a uniform melt. The melting point of iron phosphate glass depends on the composition, but is 950 ° C. or higher, preferably vitrified uniformly by heating to 1100 ° C. or higher.

  In this melting process, the sulfur component of barium sulfate is decomposed when it reaches a high temperature of 900 ° C. or more, and escapes as a gas, and barium sulfate becomes barium oxide. In addition, when the sludge contains a sulfuric acid compound such as strontium sulfate, the sulfur component decomposes and escapes as a gas as in the case of barium sulfate. For example, strontium sulfate is converted to strontium oxide. Without the precipitation of sulfate on the surface of the solidified body, sludge residue from which the sulfur component is eliminated, that is, barium oxide and / or strontium oxide, is confined and filled in the Fe-OP network.

Sulfur component barium sulfate and strontium sulfate, escapes as SO _2. As it escapes, the melt foams. The time when the foaming has subsided is a measure of the elimination of the sulfur component. The sulfur content when this melt is made into a glass solid is 0.3 mol% or less. Such a state is considered that the sulfur component has been lost. Therefore, if the sulfur content of the vitrified body is about 1 mol% or less, the chemically solidified vitrified body is obtained.

In this melting process, when the heating temperature is less than 900 ° C., barium sulfate and strontium sulfate contained in the sludge are not decomposed and sulfur components are not completely removed. Since it precipitates as a component or a sulfate, the structural stability of the vitrified body is deteriorated and it is difficult to stably store it. Further, if the heating temperature exceeds 1400 ° C., the volatilization of P ₂ O ₅ becomes remarkable, and it becomes difficult to form a glass solid having a desired glass composition, so that it is preferable not to exceed 1400 ° C.

  In order to melt the mixture of the iron phosphate glass and the sludge, the conductive and heat-resistant silicon carbide or zirconia boride or the like, or non-conductive and heat-resistant alumina or zirconia or the like The mixture can be put into a formed melting furnace and heated. Alternatively, the iron phosphate glass and the sludge may be heated while being supplied to the melting furnace and mixed in the course of melting.

  In addition, since sludge usually contains a lot of moisture, it may be calcined in a rotary kiln furnace or the like before being heated and melted together with iron phosphate glass to form powder. When iron phosphate glass is used in the form of glass fibers, the glass fibers may be combined into a lump, and sludge may be impregnated into the lump and then supplied to the melting furnace.

  The melt heated and melted in this way can be poured into a carbon mold or a metal container and solidified by cooling.

<Chemical change of insoluble ferrocyanide when insoluble ferrocyanide is contained in sludge during heating and melting process of iron phosphate glass and sludge>
In the vitrification method of the present invention, the sludge may contain an insoluble ferrocyanide. In the insoluble ferrocyanide, the cyano group is decomposed in the range of 200 ° C. to 400 ° C. in an atmosphere sufficiently containing oxygen, and nickel, iron and potassium constituting the insoluble ferrocyanide are oxidized, and the insoluble ferrocyanide is oxidized. Oxides derived from Russian compounds.

  Since the melting point of the iron phosphate glass used in the present invention is generally 950 ° C. or higher and it is necessary to heat to 900 ° C. or higher in order to remove the sulfur component from the barium sulfate constituting the sludge, the insoluble Fe glass is used. The cyanide is oxidized to nickel oxide, iron oxide and potassium oxide as the cyano group decomposes.

  Nickel oxide, iron oxide, and potassium oxide are confined and filled in the Fe-OP network of iron phosphate glass together with barium oxide and / or strontium oxide. Iron oxide may be confined in the Fe—OP network or may form an Fe—OP network.

<About the composition of the vitrified body produced by the method of the present invention>
The vitrified body produced by the vitrification method of the present invention is a mixture of iron phosphate glass composed of Fe ₂ O ₃ and P ₂ O ₅ and sludge mainly composed of barium sulfate, heated and Barium sulfate changes to barium oxide in the process of melting, and it can be vitrified in a state where barium oxide is stably held in iron phosphate glass.

  Moreover, even when the strontium sulfate is contained in the sludge, the strontium sulfate becomes strontium oxide and vitrifies in the process of mixing and heating and melting the sludge together with the iron phosphate glass. be able to.

Further, in the vitrification method of the present invention, as shown in Samples ₂ to 6, 8 to 12, and 16 to 22 in Table 1, the residual sludge from which Fe ₂ O ₃ , P ₂ O ₅ and sulfur components are removed is obtained. When the vitrified body is constituted with a composition ratio of 16% to 30%: 30% to 63%: 7% to 50% in mol%, 7% of the sludge residue from which the sulfur component is removed A structurally stable vitrified body containing -50% can be obtained. Here, the sludge residue from which the sulfur component has been removed means that the sulfur component of sulfate such as strontium sulfate and barium sulfate is gasified by heating and melting out of the components contained in the sludge, strontium oxide, This refers to oxides such as barium oxide.

Further, in the vitrification method of the present invention, as shown in Samples 4 to 6, 10 to 12, and 16 to 22 in Table 1, Fe ₂ O ₃ , P ₂ O ₅ and residual sludge from which sulfur components have been removed. The composition ratio of the product is 16% to 33% in mol%, 30% to 50%: 20% to 50%, and the vitrified solid is constituted so that the residue of sludge from which the sulfur component is removed is 20% or more. Then, the residue of the sludge from which the sulfur component is removed can be stably held at a high density, which is more preferable for reducing the volume of the vitrified body to be stored.

Further, in the vitrification method of the present invention, as shown in Samples 5, 6, 11, 12, and _{17 of} Table 1, Fe ₂ O ₃ , P ₂ O ₅ and sludge residue from which sulfur components are removed The vitrified body is constituted with a composition ratio of 16% to 32%: 30% to 41%: 30% to 50% in terms of mol%, and the residue of sludge from which the sulfur component is removed is 30% or more. Then, the residue of the sludge from which the sulfur component has been removed can be stably maintained at a high density, which is further preferable for further reducing the volume of the vitrified body to be stored.

Further, in the vitrification method of the present invention, as shown in Samples 5, 6, 11, and 12 of Table 1, the composition ratio of the residue of sludge from which Fe ₂ O ₃ , P ₂ O ₅ and the sulfur component are removed. However, when the vitrified body is composed of 16% to 22%: 30% to 41%: 40% to 50% in mol%, and the residue of sludge from which the sulfur component is removed is 40% or more, The sludge residue from which the sulfur component is removed can be stably retained at a high density, which is preferable in reducing the volume of the vitrified body to be stored.

In the vitrification method of the present invention, as shown in Samples 4, 10, and 16 to 22 in Table 1, the composition ratio of the residue of sludge from which Fe ₂ O ₃ , P ₂ O ₅ and the sulfur component are removed. Is 25% to 32% in mol%: 40% to 53%: 20% to 32%, so that the vitrified solid is composed of 20% to 32% of the sludge residue from which the sulfur component is removed. In this case, it is more preferable to confine the sludge residue from which sulfur has been removed in the vitrified body to ensure long-term stability.

  The range of 20% to 32% of the sludge residue from which the sulfur component has been removed, that is, the vitrification is performed so that the composition ratio of the sludge residue from which the sulfur component has been removed increases. However, if a large amount of sludge is confined in the vitrified body, a large amount of decay heat of the radioactive material contained in the sludge is generated, which may impair the stability of the structure of the vitrified body. It is. Therefore, it is more preferable to set the composition ratio in the vitrified body of the sludge residue from which the sulfur component is removed in such a range.

  The residue of the sludge from which the sulfur component has been removed is barium oxide and strontium oxide, although molecules composed of other elements, barium sulfate that could not be changed, and strontium sulfate unavoidably contained in trace amounts. I do not care.

  Moreover, since barium and strontium contained in the sludge are both alkaline earth metals, their chemical characteristics are similar, so that even if the ratio of barium and strontium changes somewhat, a vitrified body can be obtained in the same way. Can do.

<About the form of the vitrified body of the present invention>
Generally, the vitrified body in the radioactive waste treatment generally refers to a solidified material that is poured into a melt can in a stainless canister. However, in the present invention, it is not necessary to stick to the stainless steel container, and it is made of a material resistant to corrosion so that the container is corroded by long-term storage and the vitrified body inside does not come out. It only has to be stored in a separate container. Furthermore, it is not necessary to inject into the container in the form of a melt. For example, a solidified and solidified product may be finely crushed so as to enter the container and stored in the container.

  Hereinafter, Example 1 of the vitrification processing method of this invention is shown.

<Preparation of sample>
Tables 1 to 4 show Example 1 of the present invention. Table 1 shows Samples 1 to 6, Table 2 shows Samples 7 to 12, Table 3 shows Samples 13 to 17, and Table 4 shows Samples 18 to 22.

  The iron phosphate glass used as the sample of Example 1 was produced as follows.

Fe ₂ O ₃ : P ₂ O ₅ = 30: 70, 35:65, and 40:60 (mol%). As a Fe ₂ O ₃ source, a reagent iron oxide (manufactured by Kanto Chemical) was used, and as a P ₂ O ₅ source, regular phosphoric acid (manufactured by Kishida Chemical) was used. A predetermined amount of the iron oxide and the regular phosphoric acid were weighed and mixed so that the vitrification amount was 500 g. The mixture is put into a platinum crucible and heated and melted at 1300 ° C. for samples 1 to 6 and 1200 ° C. for samples 7 to 22 for 1 hour in an electric heating furnace in an air atmosphere to obtain a uniform melt. It was. The reason why the heating temperature differs depending on the sample is that the melting temperature differs depending on the composition ratio. The molten glass was poured into a carbon mold and air-cooled to produce a glass. Next, the produced glass was pulverized with an alumina mortar so as to be less than 850 μm to obtain powdered iron phosphate glass.

  In Example 1, not a real sludge, but a barium sulfate reagent added with a barium sulfate reagent (Kishida Chemical) or a strontium sulfate reagent (Kishida Chemical) was used as a simulated sludge simulating sludge.

  Then, the powdered iron phosphate glass and the simulated sludge are mixed at a mixing ratio (wt%) shown in Tables 1 to 4, and the mixture is put into a platinum crucible, and the atmosphere is heated in an electric heating furnace. The mixture was heated and melted at 1250 ° C. for 0.5 hours in an atmosphere to obtain a uniform melt. Then, the melt was poured into a carbon mold, and a glass solid sample was produced by air cooling.

<Evaluation criteria and evaluation method for the prepared sample>
For each sample thus prepared, confirmation of vitrification, density, glass transition point / softening point, and chemical durability of the sample were evaluated.

  Confirmation that the sample is vitrified uses a powder X-ray diffractometer Ultima IV (manufactured by Rigaku Corporation) to confirm the presence of a unique halo pattern indicating that it is in an amorphous state and crystals. It was done by confirming that there was no.

  The measurement of the density of the sample was performed using a precision top electronic balance ER-180A (manufactured by A and D). The measurement was performed by the Archimedes method using ultrapure water as the solvent.

  The glass transition point and softening point of the sample were measured using a differential thermal analyzer TG8120 (manufactured by Rigaku Corporation). In the measurement, each sample was pulverized in an alumina mortar, and about 10 mg of the powder was put in a platinum pan, and the temperature was raised from room temperature to 1000 ° C. at a rate of 10 ° C./min.

The structural stability of the vitrified body is evaluated by the following chemical durability test of the sample. That is, the samples were cut into 10 mm × 10 mm × 5-10 mm shapes, the entire surface was polished with a # 800 file, the length and weight of the three sides were measured, and then immersed in pure water at 90 ° C. for 3 days. The components leached in the immersion liquid were analyzed with a fluorescent X-ray analyzer AXIOS advanced (manufactured by PANalytical BV) and inductively coupled plasma emission spectrometer SPS-3000 (manufactured by Seiko Instruments). Evaluation is based on the calculated normalized leaching rate (g / cm ² / day).

The structural stability of each sample was determined in accordance with MCC-1 of the durability evaluation test formulated by MCC (Material Characterization Center) of the United States, and the leaching rate with respect to water was 10 ⁻⁵ g / cm ² / Those having a day or less were considered to have excellent chemical durability.

  Moreover, it was measured by XRF (fluorescence X-ray analysis) whether each glass solidified body produced as a sample contained a sulfur component. And when it became less than a detection lower limit, the sulfur component was not contained in each said glass solidified body.

<Components of each sample>
Samples 1 to 6 in Table 1, Samples 7 to 12 in Table 2, Samples 13 to 17 in Table 3, and Samples 18 to 22 in Table 4 are Fe ₆ O in glass composition of iron phosphate glass, respectively. ₃ : P ₂ O ₅ = 30: 70, 35:65, 40:60, 35:65.

  Samples 1 to 6 are iron phosphate glass and barium sulfate, which is simulated sludge, in% by weight, and iron phosphate glass: barium sulfate = 100: 0, 90:10, 80:20, 70: Mixed at 30, 50:50, 40:60. Similarly, Samples 7 to 12 were iron phosphate glass and barium sulfate, which is a simulated sludge, in% by weight, and iron phosphate glass: barium sulfate = 100: 0, 90:10, 80: It was mixed at 20, 70:30, 50:50, 40:60. And samples 12-17 are iron phosphate glass and barium sulfate which is simulated sludge by weight%, respectively, and iron phosphate glass: barium sulfate = 100: 0, 90:10, 80:20, 70: 30, 40:60.

  In Samples 18 to 22, the simulated sludge is composed of barium sulfate and strontium sulfate, and iron phosphate glass and simulated sludge, barium sulfate and strontium sulfate, are each iron phosphate in weight%. Glass: Barium sulfate: Strontium sulfate = 70: 30: 0, 70: 29: 1, 70: 27: 3, 70: 25: 5, and 70:20:10 were mixed.

Each sample is heated, melted, and cooled, and its composition is as shown in Table 1. As for samples 1 to 18, Fe ₂ O ₃ , P ₂ O ₅ , and BaO as the main components are used as Na ₂ O. , SrO is contained in a very small amount. Samples 19 to 22 are mainly composed of Fe ₂ O ₃ , P ₂ O ₅ , BaO, and SrO and contain a trace amount of Na ₂ O. The reason why Na ₂ O and SrO are contained in all the samples in this manner is that the components used as the simulated sludge originally contained the components that are their sources. Except for sample 12, the sulfur component of each sample was XRF (it was less than 0.1 mol%, which is the lower limit of detection in fluorescent X-ray analysis). Moreover, the sulfur component contained in Sample 12 was 0.3 mol%.

<Measurement and evaluation of each sample>
Regarding the presence or absence of vitrification of the samples, it was confirmed that all the samples 1 to 22 were vitrified. Therefore, it can be seen that the sample is composed of a chemically stable Fe—OP network structure.

Regarding the glass density, the composition of the sample is about 3 g / cm ³ in Sample 1, Sample 7 and Sample 13 not containing BaO, whereas Samples 1 to 6 containing BaO and / or SrO in the composition, Samples 8 to 12 and Samples 14 to 22 have a higher density than those, and a large amount of BaO and / or SrO is incorporated into the chemically stable Fe—OP network structure of the sample to vitrify. You can see that

  Regarding the glass transition point and softening point, it was 500 ° C. or higher for all samples, and it was confirmed that the sample was thermally stable. Moreover, when Table 1-Table 3 is seen, it turns out that the temperature of a glass transition point is rising as the mixing ratio of the simulated sludge with respect to iron phosphate glass is raised. From this fact, at least within the range of the composition shown here, a glass solid that is thermally stable can be obtained as the mixing ratio of the simulated sludge is increased.

Regarding the chemical stability of the sample, it was measured in Samples 4, 8, 9, 10, and 16, and the total weight reduction rate indicating the leaching rate with respect to water was smaller than 10 ⁻⁵ g / cm ² / day. It was confirmed that the structure is stable.

  Moreover, when XRF of each glass-solidified material produced as a sample was performed, except for the sample 12, the sulfur component was less than the detection lower limit of 0.1 mol%. Sample 12 contained 0.3 mol% sulfur, but was not so large as to affect the chemical stability of the sample.

  Hereinafter, Example 2 of the vitrification processing method of this invention is shown.

<Evaluation criteria / evaluation method of sample and prepared sample>
The iron phosphate glass used as the sample of the example was produced as follows.

Fe ₂ O ₃ : P ₂ O ₅ = 30: 70, 35:65 (mol%). As the Fe ₂ O ₃ source and the P ₂ O ₅ source, reagents iron oxide (manufactured by Kanto Chemical) and orthophosphoric acid (manufactured by Kishida Chemical) were used in the same manner as in Example 1. A predetermined amount of the iron oxide and the regular phosphoric acid were weighed and mixed so that the vitrification amount was 500 g. The mixture is put into a platinum crucible and heated and melted at 1300 ° C. for samples 23 to 27 and 1200 ° C. for samples 28 to 35 for 1 hour in an electric heating furnace in an air atmosphere to obtain a uniform melt. It was. The reason why the heating temperature differs depending on the sample is that the melting temperature differs depending on the composition ratio. The molten glass was poured into a carbon mold and air-cooled to produce a glass. Next, the produced glass was pulverized in an alumina mortar so as to be less than 850 μm in the same manner as in Example 1 to obtain powdered iron phosphate glass.

  As the simulated sludge, a barium sulfate reagent (Kishida Chemical) or a barium sulfate reagent added with a strontium sulfate reagent (Kishida Chemical) was used in the same manner as in Example 1.

Furthermore, insoluble ferrocyanide (hexacyanonickel (II) iron (II) potassium (K ₂ -2) used for cesium sorption in the second step of the method described as the method for removing radioactive substances from the stagnant water described above. _x Ni _{x / 2} [NiFe (CN) ₆ ] · nH ₂ O (hereinafter referred to as KNiFC) is simulated as a reagent iron oxide (manufactured by Kanto Chemical), a reagent nickel oxide (manufactured by Kishida Chemical) and a reagent Potassium carbonate (manufactured by Kishida Chemical Co., Ltd.) was used by mixing so that the ratio of the number of each atom constituting the insoluble ferrocyanide KNiFC was the same, and as a simulation of adsorbed cesium, The reagent cesium carbonate (manufactured by Kishida Chemical) was used.

  Furthermore, as a simulation of the seawater component contained in the sludge, the reagent sodium chloride (manufactured by Kishida Chemical), the reagent magnesium oxide (manufactured by Kishida Chemical), the reagent calcium carbonate (manufactured by Kishida Chemical), It was mixed and used so that it might become a ratio.

  Regarding the evaluation standard / evaluation method of the prepared sample, the same evaluation standard / evaluation method as in Example 1 was used.

<Components of each sample>
Samples 23 to 27 in Table 5, Samples 28 to 30 in Table 6, and Samples 31 to 35 in Table 7 are each in mol% of the glass composition of iron phosphate glass, Fe ₂ O ₃ : P ₂ O ₅ = 30. : 70, 35:65, and 35:65.

Each sample was produced by heating, melting, and cooling. Samples 23 to 27 shown in Table 5 and Samples 28 to 30 shown in Table 6 simulate that the sludge contains insoluble ferrocyanide KNiFC that adsorbs cesium in addition to barium sulfate. The composition ratios of the respective samples are shown in Tables 5 and 6 in mol%. In Tables 5 and 6, nickel oxide (NiO) is included in an amount of about 5% to 11%, and potassium oxide (K ₂ O) is included in an amount of about 2.6% to 5.2%. About 0.1% of cesium oxide (Cs ₂ O) is contained.

Samples 31 and 32 shown in Table 7 simulate that the sludge contains only the seawater component. Samples 33 to 34 contain not only the seawater component but also barium sulfate and cesium in the sludge. This is a simulation of the presence of adsorbed insoluble ferrocyanide KNiFC. The composition ratio of Samples 31 to 35 is mol%, nickel oxide (NiO) is about 0% to 1.5%, potassium oxide (K ₂ O) is about 0% to 0.7%, cesium About 0.1% of oxide (Cs ₂ O) is contained, 4% to 8.3% of sodium oxide (Na ₂ O), and 0.6% to of magnesium oxide (MgO) About 1.9%, calcium oxide (CaO) is about 1.3% to 3.6%, and chlorine is about 0.2% to 2.1%.

<Measurement and evaluation of each sample>
Regarding the presence or absence of vitrification of the samples, it was confirmed that all the samples 23 to 35 were vitrified. Therefore, it can be seen that the sample is composed of a chemically stable Fe—OP network structure.

  Regarding the glass transition point and the softening point, all the samples were around 500 ° C. or 500 ° C. or more, and it was confirmed that they were thermally stable.

  Moreover, when XRF of each glass solidified body produced as a sample was performed, the sulfur component was less than 0.1 mol% which is a detection lower limit value.

  As described above, it was found from Samples 23 to 30 and Samples 33 to 35 that a chemically stable glass solid can be produced even when nickel oxide, potassium oxide, and cesium oxide are contained. This shows that a chemically stable vitrified body can be formed even if the sludge contains ferrocyanide KNiFC in which cesium is adsorbed.

The insoluble ferrocyanide capable of adsorbing cesium is not limited to KNiFC. An insoluble ferrocyanide is a compound generally represented by (M) ⁴⁺ [Fe (II) (CN) ₆ ] ⁴⁻ , and M includes a transition metal such as iron, nickel, cobalt, copper, zinc, etc. enter. Therefore, when the nickel of this example is changed to iron, cobalt, copper, or zinc, the chemical stability does not change greatly.

  Furthermore, from samples 31 to 35, it was found that a chemically stable vitrified body can be formed even if sodium chloride, magnesium oxide and calcium carbonate simulating seawater components are contained.

Incidentally, solidification processing method of the present invention is not limited to the embodiment described above, the gist of the present invention, iron phosphate glass containing Fe ₂ O ₃ and P ₂ O _5, barium sulfate The procedure and type are not limited as long as they do not deviate from the processing method of mixing, melting, and then cooling and solidifying the sludge.

Claims (8)

In a vitrified solid body of radioactive waste using an iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ ,
The radioactive waste is composed of sludge containing barium sulfate generated when the contaminated water containing radioactive material is treated by a coagulation sedimentation method that generates barium sulfate in the contaminated water.
The vitrified body is
An iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ and a residue of sludge from which sulfur components have been removed during vitrification,
The residue of sludge from which Fe ₂ O ₃ , P ₂ O ₅ and sulfur components have been removed is contained in a molar ratio of 16% to 33%: 30% to 63%: 7% to 50%. A solidified vitrified radioactive waste. In a vitrified solid body of radioactive waste using an iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ ,
The radioactive waste is composed of sludge containing barium sulfate generated when the contaminated water containing radioactive material is treated by a coagulation sedimentation method that generates barium sulfate in the contaminated water.
The vitrified body is
An iron phosphate glass containing Fe ₂ O ₃ and P ₂ O ₅ and a residue of sludge from which sulfur components have been removed during vitrification,
The residue of sludge from which Fe ₂ O ₃ , P ₂ O ₅ and sulfur components are removed is contained in a molar ratio of 25% to 32%: 40% to 53%: 20% to 32%. A solidified vitrified radioactive waste. The sludge further contains insoluble ferrocyanide,
The vitrified solid body of radioactive waste according to claim 1 or 2, wherein the sludge residue of the vitrified body contains an oxide derived from the insoluble ferrocyanide.   The vitrified product of radioactive waste according to claim 3, wherein the oxides derived from the insoluble ferrocyanide are potassium oxide and nickel oxide. The sludge further contains seawater-derived components,
The radioactive waste vitrified body according to any one of claims 1 to 4, wherein the sludge residue of the vitrified body contains an oxide derived from the seawater. The sludge containing barium sulfate generated when the contaminated water containing radioactive material is treated by the coagulation precipitation method that generates barium sulfate in the contaminated water on the iron phosphate glass containing 10 to 50 mol% Fe ₂ O ₃ The mixture is then heated to 1100 ° C or higher to produce a glass melt, and the sulfur component contained in the sludge is vaporized and removed, and then cooled and solidified. A method for forming a vitrified radioactive waste. Iron phosphate glasses containing 10-50 mole% Fe ₂ O _3, and sludge containing barium sulphate occurring upon treating contaminated water containing radioactive materials by coagulation precipitation method to produce a barium sulfate contaminated water Each is heated to 1100 ° C. or more while being supplied to a melting furnace, mixed in the process of melting, a glass melt is generated, sulfur components contained in the sludge are removed by evaporation, and then cooled and solidified. A method for forming a vitrified body of a radioactive waste according to any one of claims 1 to 5.   The method for forming a vitrified body of radioactive waste according to claim 3 or 4, wherein the radioactive substance is cesium and / or strontium.