EP2693443A2

EP2693443A2 - Method of disposal of radioactive waste in "synthetic rock"

Info

Publication number: EP2693443A2
Application number: EP13176463.1A
Authority: EP
Inventors: Tomasz Smolinski; Andrzej G. Chmielewski; Andrzej Deptula; Wieslawa Lada; Tadeusz Olczak
Original assignee: Instytut Chemii i Techniki Jadrowej
Current assignee: Instytut Chemii i Techniki Jadrowej
Priority date: 2012-08-03
Filing date: 2013-07-15
Publication date: 2014-02-05
Anticipated expiration: 2033-07-15
Also published as: PL223603B1; EP2693443A3; PL400235A1; EP2693443B1

Abstract

The invention relates to the disposal of radioactive waste by a modified sol-gel method by enclosing it in durable ceramic crystallographic structures of ceramic synroc materials of type perovskite.

The method according to the invention lies in the fact that to the previously prepared chlorine-free solution of colloidal sol, preferably Ti(NO₃)₄, the complexing compound is added, preferably ascorbic acid ASC, relative to the sum of the moles of metal from 0.1 to 0.3 and introduces calcium carbonate and elements included in the high-level radioactive waste, in the form of carbonates or nitrates, especially strontium, cobalt, cesium and neodymium, in a molar ratio of from 2% to 14% of the individual metals (Me), thereby replacing from 2% to 14% by mol of introduced Ca²⁺.The thus obtained sol is evaporated, dried and subjected to heat treatment and is eventually subjected to XRD and IR analysis, then the precursor of the synroc is pelletized and calcined at a temperature of 1200°C for 2h.

Description

Technical Field

The subject of the invention is a method of the disposal of radioactive waste a modified sol-gel method by enclosing them in a stable crystallographic structures of synroc ceramic materials, especially the type of perovskite, otherwise "Synthetic Rock". Actually, in the era of expanding nuclear power controversy raises the problem of security of both nuclear power plants and radioactive waste disposal. The energy generated from nuclear power plants should be considered as safe, not aggravating the environment. To meet these requirements, it is necessary to seek solutions that enable transformation of dangerous radioactive waste into such a form that they can be safely stored. Radioactive wastes are materials containing in their composition of the radioactive elements, which further use is impossible or unprofitable.

Background Art

Generally, waste stored in such a way as to ensure the protection of people and the environment, both in normal conditions, as well as radiological events. The main task of processing technology and soldification of radioactive waste is to reduce their volume and to reduce the radioactivity and striving to obtain a product with the features that are most favorable from the point of view of their long-term storage. The main methods of radioactive waste solidification are: vitrification, asphalting, concreting, solidifying in epoxy resin as well as urea-formaldehyde and in materials type of synroc. A.E. Ringwood, based on previous observations and studies of the rocks, first used the term "synroc materials" that were used to solve the problems of disposal of radioactive waste. *A.E. Ringwood "Safe Immobilization of High Level Nuclear Wastes". Australian National University Press, Canberra, Australia, 1978 ,* A. E. Ringwood "Immobilization of Radioactive Wastes in SYNROC" American Scientist, vol 70, 1982, pp.201-207.
Synroc is a kind of "synthetic Rock" created for the safe storage of radioactive waste. This is an advanced ceramics consisting of geochemical stability of titanium compounds, which naturally occur in the earth's crust. They allow the incorporation in its structure almost all the radioactive the high-level (HLW-High Level Wastes) extracted from spent fuel, depending on the type and form of wastes. Synroc can take various forms. Based on the research highlights, there are some B, C, E, F synroc, depending on the type of ceramic matrix. And so, in the synroc-C there are three components; hollanite, zirconolite and perovskite. This material was designed to disposal of waste from reprocessing of spent fuel elements used in reactors and containing 10% up to 20% of HLW. The literature reference * A.T. Bukat "Application of multiphase ceramic materials to the disposal of radioactive materials", Bioprojectgrup, Via Giuilia 67 Roma, Italia, the basis for the entire family of ceramic multiphase materials type of Synroc is titanium compounds obtained by melting and crystallization.
Frequently described in the literature method of immobilization of HLW waste in materials type Synroc is synthesis in a solid phase - "solid-state reaction" - preparation of titanium compounds, namely a matrix to which are added the radioactive waste elements. The final stage of the process is compressed under high pressure and long hours (20h) conversion of the final product in the high temperature. So it is a very complex, time-consuming and economically unprofitable process.
Searching for alternative solutions in order to eliminate the above-mentioned problems and to reduction of costs in many scientific works, appeared a number of studies based on known literature synthesis involving wet liquid-liquid methods, especially a sol-gel method. * A.E. Ringwood, V.M. Oversby, S.E. Kesson, W. Sinclair, N. Ware, W. Hibberson, A. Major "Immobilization of high-level nuclear reactor wastes in SYNROC: A current appraisal" Nuclear and Chemical Waste Management, Volume 2, Issue 4, 1981, Pages 287-305.
While in available literature, there are no information about the trial recessed radioactive elements to the materials type Synroc - perovskite in the modified synthesis based on the use of ascorbic acid, in other words a complex of the sol-gel-CSGP. This method has been used successfully for the preparation of various compounds but never to synthesize such a complex crystallographic form as Synroc type perovskite with built-in radioactive element in order to dispose of HLW waste. The literature listed below refer to the use of CSGP to receive various types of compounds, but never for the preparation of materials with such a complicated structure as Synroc while disposing of the radioactive waste in this structure [1-4].
It is also known from patent PL198039 (A.Deptula, W.Lada, T.Olczak, A.G.Chmielewski, S.Casadio, C.Alvani, F.Croce , "Method obtain titanium dioxide and Titanium tetrachloride with lithium and tytanite") method of obtaining a sol Ti(NO₃)₄ from a sol constituting a solution of titanium tetrachloride TICl₄, by distillation under vacuum, with the addition of concentrated nitric acid in a volume ratio of 1:1, where then produced, chloride-free colloidal solution of Ti⁴⁺, evaporated to dryness and calcined. This method can be used to obtain the starting sol Ti⁴⁺ and then to obtain perovskite type synroc by method of the invention.
Unexpectedly, the process according to the invention allows for disposal of a radioactive waste type HLW while receiving Synroc perovskite-type, in one of the modified sol-gel synthesis.
Unexpectedly, other studies have shown that the CSGP method can successfully be applied to all elements contained in HLW as well as other contained in the radioactive waste. In the method according to the invention, directly to the crystallographic structure can be incorporated radioactive element already during the formation of the sol, leading to a homogeneous distribution of radioactive elements in the structure of the final product.
Also unexpectedly, the advantage of the method according to the invention, in the preparation of Synroc with integrated radioactive element, is not only the above-mentioned homogeneity, but also reduces of the sintering temperature and the increased resistance of Synroc with integrated radioactive element to external influences, especially to leaching (elution during waste storage).

Summary of invention

A method of the immobilization of radioactive waste in a synthetic Synroc rock type perovskite by incorporating in its structure elements of radioactive waste, according to the invention consists in the fact that to the previously prepared chlorine-free colloidal solution of sol Ti⁴⁺, preferably Ti(NO₃)₄, the complexing compounds is added , preferably ascorbic acid ASC, relative to the sum of the moles of metal from 0.1 to 0.3 and calcium carbonate, preferably in slurry form, and then enters selected radioactive elements contained in the radioactive waste, in the form of carbonates or nitrates, especially strontium, cobalt, cesium and neodymium, in a molar ratio of from 2% to 14% of the individual metals (Me), thereby replacing from 2% to 14% by mol, introduced Ca²⁺, thus obtained sol is evaporated, dried and subjected to thermal treatment.
In the present invention, obtained artificial rock subjected to XRD and IR analysis, and the resulting precursor of synroc is pelletized and calcined at a temperature o 1200°C for 2h.
According to the invention, is preferably used chloride-free colloidal sol Ti(NO₃)₄ obtained from a solution of titanium tetrachloride in concentrated hydrochloric acid, by evaporation chloride several times by vacuum distillation and adding each time after evaporation concentrated nitric acid in a volume ratio 1:1 to half of the original volume of the solution.
According to the invention, preferably to the chloride-free colloidal solution of Ti⁴+, ascorbic acid ASC, relative to the sum of the moles of metal from 0.1 to 0.3, is added.
According to the invention, preferably calcium carbonate is introduced into the sol of titanium, in the form of a slurry with an excess from 1 % to 5%, especially 3% relative to the calculated stoichiometric amount that could arise CaTiO₃ and after replacing part of introduced Ca²⁺ by the radioactive element, obtained sol which is a precursor of synroc perovskite, in the slurry form, is evaporated at 80°C under vacuum for 1 h to obtain a white-yellow gel, which is then dried in an oven at 110°C for 24h and subjected to heat treatment at a temperature of 450°C and 700°C in equal time spent in various temperature for 2h and a heating rate of 2°/min.
The temperature and the time of conversion to synroc type perovskite determined during own research termogravimetrically.
In order to verify the purity and the structure thus obtained synroc was subjected to XRD and IR analysis. Thus obtained precursor powder of synroc type perovskite with integrated calcium was pelleted and sintered at 1200°C for 2h.
A method of the immobilization of radioactive waste in a synthetic rock perovskite type, according to the invention, preferably is carried out in such a way that to the chlorine-free sol Ti(NO₃)₄ is added ascorbic acid ASC, the radioactive elements contained in the radioactive waste in the form of carbonates or nitrates, especially strontium, cobalt, cesium and neodymium in a molar ratio of from 2% to 14%, especially 10% by mol of individual metals (Me), thereby replacing from 2% to 14% by mol, preferably 10% by mol amount of calcium previously introduced into the sol, and sol thus obtained is evaporated, dried and subjected to thermal treatment and subjected to the XRD and IR analysis, and then the precursor of synroc is pelletized and calcined at a temperature of 1200°C for 2h.
In the current energy situation, not only in the Poland but also in the world, when it returns to nuclear energy, one of the most important issues in environmental protection is permanent disposal of radioactive waste type HLW during their utilization and storage as well as minimizing the costs of their disposing for a long period of time (resistance on the impact of external factors). Therefore, undeniable advantage of the present invention is the simplified way of conducting the synthesis of the final product which is perovskite-type synroc, which meets all of the criteria and required above.
Studies of the X-ray structures have shown that in the resulting material are not characteristic range of metal oxides, they are a perovskite-type structures of synroc, and the results of research in the infrared showed no contamination.
All experiments were performed by using surrogates of a high-level radioactive elements contained in HLW waste.

Description of embodiments

The invention is illustrated by the following examples.
Example I.
For the preparation of chloride-free colloidal solution Ti⁴⁺ dechlorination was carried out five times, by measuring out 100ml of 99,9% solution TiCl₄ (from Aldrich Chemical Corporation), in which the titanium concentration was 183g Ti⁴⁺/I, and chlorine was 465g Cl^-/I. The solution was placed in a rotary flask, in a water bath of vacuum device type Rotavapor (Buchi). In order to dechlorinate, was sucked under vacuum portions of 5ml of 200ml of concentrated HNO₃ to solution of TiCl₄ in concentrated hydrochloric acid at 80°C. After entering of all of the nitric acid solution changed its color from yellow to orange. The process continued until 200ml of the solution was evaporated. In the distillate content of chlorides was studied, using a solution of AgNO₃. Precipitation of a white precipitate indicated a high chloride content. Therefore, dechlorination operation was repeated five times, each time by adding 200ml of nitric acid, interrupting each process after obtaining 200ml of distillate. After each stage content of chlorides was checked, until when in the sample was no precipitate formed. Durring the next stages of the the process, solution in the flask became turbid and at the end to get the milky-white color. Thus obtained chloride-free, colloidal solution of Ti(NO₃)₄, which is a starting solution for the preparation of titanates, which are the basis of the family of ceramic multiphase materials type Synroc. Thus obtained colloidal solution of Ti(NO₃)₄ was placed back into the Rotavapor evaporator machine in special container adapted to receive powder, to which was added (by sucking in) ASC ascorbic acid [L-Ascorbic Acid (E300) USP/Ph.Eur.] in an amount of 0.1 relative to the sum of moles of metals dissolved in 50ml of H ₂O. Because colloidal solution of Ti(NO₃)₄ during the addition of ASC is churned very intensely, addition was carried out in small portions with vigorous stirring. Then the calcium carbonate cz.d.a. (Polskie Odczynniki Chemiczne, Gliwice) was added in the form of a slurry of 3% excess over the calculated stoichiometric amount to be able to develop CaTiO₃ i.e. 39.41g in 150mL of H₂O, after calcination at a temperature of 170°C during 24h. Thus obtained sol was dried in vacuum for 1 h at 80°C to give white-yellow gel, which was given to heat treatment after the thermogravimetric analysis, by using Hungarien MOM Derivatograph, intended to provide temperature of each phase transition to the final product. The gel was dried in the oven for 24 h at 110°C, while calcining and sintering was carried out in an oven type CSF 1200 (Carbolitte Furnaces, England) at 450°C, 700°C. The residence time at each temperature is 2h and the speed of heating to the desired temperature was 2°C/min. Physico-chemical properties of the final product was analyzed by scanning microscope (Zeiss DSM 942) diffraction by using Rigaku Miniflex diffractometer with Cu-Kα radiation and a spectrometer for IR test (Bruker-Equinox 55). Thus obtained precursor powder of type perovskite synroc with integrated calcium was pelleted and sintered at 1200°C during 2h and subjected to a leaching water and the acidified water in order to verify resistance to adverse environmental conditions. The study was conducted over 30 days to give a negative result for Ca in the eluate (water leaching), which confirmed that the obtained end product meets the requirements of a materials synroc type.
Example II.
For the preparation of the perovskite-type of synroc with built into its structure model element to radioactive waste which is strontium, in the first stage sol Ti(NO₃)₄ is obtained as described in the Example I, and (in the same amount) ascorbic acid ASC is added, as also described above. To thus obtained starting sol in the form of a slurry is added, (sucks after dissolved in 150ml of H₂O) 35.47 g of calcium carbonate and 5.64g of strontium carbonate SrCO₃ in a molar ratio of 10% by mol of strontium, thereby replacing 10% by mol of calcium. The process is carried out under vacuum for 1 h at 80°C to obtain a white gel and then proceed of thus obtained material as in the Example I. The XRD and IR analysis confirmed that the obtained material is synroc with integrated surrogate of strontium and the research for resistance to adverse environmental conditions, as well as in the Example I, confirmed that the resulting end product meets the requirements of materials type synroc.
Example III
For the preparation of the perovskite-type synroc with built into its structure model element to radioactive waste which is cobalt, in the first stage sol Ti(NO₃)₄ is obtained as described in the Example I, and (in the same amount) ascorbic acid ASC is added, as also described above. To thus obtained starting sol in the form of a slurry is added (sucks after dissolved in 150ml of H₂O) 35.47 g of calcium carbonate and 16.9 ml of cobalt nitrate Co(NO₃)₂ at a concentration of 133.3 g Co/I in a molar ratio of 10% by mol of cobalt, thereby replacing 10% by mol of calcium. The process is carried out under vacuum for 1 h at 80°C to obtain a white-yellow gel and then proceed of thus obtained material as in the examples above. The XRD and IR analysis confirmed that the obtained material is synroc with integrated surrogate of cobalt and the research for resistance to adverse environmental conditions, as well as in the Example I and Example II, confirmed that the resulting end product meets the requirements of materials type synroc.
Example IV
For the preparation of the perovskite-type synroc with built into its structure model element to radioactive waste which is cesium, in the first stage sol Ti(NO₃)₄ is obtained as described in the example above, and (in the same amount) ascorbic acid ASC is added, as also described above. To thus obtained starting sol in the form of a slurry is added (sucks after dissolved in 150ml of H₂O) 35.47 g of calcium carbonate and 14.90 g of cesium nitrate CsNO₃ in a molar ratio of 10% by mol of cesium, thereby replacing 10% by mol of calcium. The process is carried out under vacuum for 1 h at 80°C to obtain a pale-pink gel and then proceed of thus obtained material as in the examples above. The XRD and IR analysis confirmed that the obtained material is synroc with integrated surrogate of cesium and the research for resistance to adverse environmental conditions, as well as in the Examples I-III, confirmed that the resulting end product meets the requirements of materials type synroc.
Example V
For the preparation of the perovskite-type synroc with built into its structure model element to radioactive waste which is neodymium, in the first stage sol Ti(NO₃)₄ is obtained as described in the example above, and (in the same amount) ascorbic acid ASC is added, as also described above. To thus obtained starting sol in the form of a slurry is added (sucks after dissolved in 150ml of H₂O) 35.47 g of calcium carbonate and 4.29 g of neodymium oxide Nd₂O₃ in a molar ratio of 10% by mol of neodymium, thereby replacing 10% by mol of calcium. The process is carried out under vacuum for 1 h at 80°C to obtain a white-beige gel and then proceed of thus obtained material as in the examples above. The XRD and IR analysis confirmed that the obtained material is synroc with integrated surrogate of neodymium and the research for resistance to adverse environmental conditions, as well as in the Examples I-IV, confirmed that the resulting end product meets the requirements of materials type synroc.

Industrial applicability

Citation list

1. A. Deptula, W. Lada, T. Olczak, M. T. Lanagan, S. E. Dorris, K. C.
Goretta and R. B. Poeppel, "Method for Preparing High-Temperature Superconductors," Polish Patent 172618, 1997 ,
2. *A. Deptula, J. Chwastowska, W. Lada, T. Olczak, D.Wawszczak, E. Sterlinska, B. Sartowska and K. C. Goretta, "Sol-Gel-Derived Hydroxyapatite and Its Application to Sorption of Heavy Metals," Adv. Sci. Technol., Vol. 45, 2006, pp. 2198-2203,
3. *A. Deptula, W. Lada, T. Olczak, D. Wawszczak, M. Brykala, F. Zaza and K. C. Goretta, "Novel Sol-Gel Synthesis of LiMn2O4 and LiNixCo1-xO2 Powders," Adv. Sci. Technol., Vol. 63, 2010, pp. 14-23,

4. *A. Deptula, K. C. Goretta, T. Olczak, W. Lada, A. G. Chmielewski, U. Jakubaszek, B. Sartowska, C. Alvani, S. Casadio, and V. Contini, Preparation of Titanium Oxide and Metal Titanates as Powders.

Claims

A method of the immobilization of radioactive waste in a synthetic rock by incorporating in its structure elements included in the high-level radioactive waste, characterized in that to the previously prepared chlorine-free solution of colloidal sol, preferably Ti(NO₃)₄, the complexing compounds is added, preferably ascorbic acid ASC, relative to the sum of the moles of metal from 0.1 to 0.3 and calcium carbonate, preferably in slurry form, and then enters selected radioactive elements contained in the radioactive waste, in the form of carbonates or nitrates, especially strontium, cobalt, cesium and neodymium, in a molar ratio of from 2% to 14% of the individual metals (Me), thereby replacing from 2% to 14% by mol of introduced Ca²⁺, thus obtained sol is evaporated, dried and subjected to thermal treatment and the obtained precursor of synroc with integrated radioactive element, eventually is subjected to XRD and IR analysis, pelletized and calcined at a temperature of 1200°C for 2h.
A method according to claim 1, characterized in that the chloride-free sol Ti(NO₃)₄ obtained from a solution of titanium tetrachloride in concentrated hydrochloric acid, by several times, preferably five times, stripping of chloride by vacuum distillation, with adding in each case concentrated nitric acid in a volume ratio 1:1.
A method according to claim 1, characterized in that to chloride-free colloidal solution of sol Ti(NO₃)₄, preferably ascorbic acid ASC is added in 0.1 to 0.3 relative to the total moles of metals.
A method according to claim 1, characterized in that in the case of calcium carbonate, it is introduced in the form of a slurry with an excess of 1% to 5%, preferably 3% by mol, relative to the calculated stoichiometric amount to be able to develop CaTiO₃ and the resulting sol which is a precursor of perovskite synroc in the form of a slurry, is evaporated at 80°C under vacuum for 1 h to obtain a white-yellow gel, which is then dried in an oven at 110°C for 24h and subjected to heat treatment at 450°C and 700°C in equal time spent in various temperature for 2h and a heating rate of 2°/min.
A method according to claim 1, characterized in that it is carried out in such a way that to chloride-free sol Ti(NO₃)₄ ascorbic acid ASC is added, the radioactive elements contained in the radioactive waste in the form of carbonates or nitrates of: strontium, cobalt, cesium and neodymium in a molar ratio of 2% to 14%, especially 10% by mol of individual metals (Me), thereby replacing of 2% to 14% by mol, preferably 10% by mol of previously introduced amount of calcium, and thus obtained sol is evaporated, dried and subjected to a heat treatment and obtained precursor of synroc with integrated radioactive element, is pelletized and calcined at a temperature of 1200°C for 2h.