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Littérature scientifique sur le sujet « Silicotitanates »

Auteur : Grafiati

Publié le 26 septembre 2023

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Articles de revues sur le sujet "Silicotitanates"

Su, Yali, Mari Lou Balmer et Bruce C. Bunker. « Raman Spectroscopic Studies of Silicotitanates ». Journal of Physical Chemistry B 104, n^o 34 (août 2000) : 8160–69. http://dx.doi.org/10.1021/jp0018807.

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Xu, Hongwu, Alexandra Navrotsky, May D. Nyman et Tina M. Nenoff. « Thermochemistry of microporous silicotitanate phases in the Na2O–Cs2O–SiO2–TiO2–H2O system ». Journal of Materials Research 15, n^o 3 (mars 2000) : 815–23. http://dx.doi.org/10.1557/jmr.2000.0116.

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Microporous silicotitanates can potentially be used as ion exchangers for removal of Cs+ from radioactive waste solutions. The enthalpies of formation from constituent oxides for two series of silicotitanates at 298 K have been determined by drop-solution calorimetry into molten 2PbO · B2O3 at 974 K: the (Na1−xCsx)3Ti4Si3O15(OH) · nH2O (n = 4 to 5) phases with a cubic structure (P43m), and the (Na1−xCsx)3Ti4Si2O13(OH) · nH2O (n = 4 to 5) phases with a tetragonal structure (P42/mcm). The enthalpies of formation from the oxides for the cubic series become more exothermic as Cs/(Na + Cs) increases, whereas those for the tetragonal series become less exothermic. This result indicates that the incorporation of Cs in the cubic phase is somewhat thermodynamically favorable, whereas that in the tetragonal phase is thermodynamically unfavorable and kinetically driven. In addition, the cubic phases are more stable than the corresponding tetragonal phases with the same Cs/Na ratios. These disparities in the energetic behavior between the two series are attributed to their differences in both local bonding configuration and degree of hydration.

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Strelko, V. V., V. V. Milyutin, V. M. Gelis, T. S. Psareva, I. Z. Zhuravlev, T. A. Shaposhnikova, V. G. Mil’grandt et A. I. Bortun. « Sorption of cesium radionuclides onto semicrystalline alkali metal silicotitanates ». Radiochemistry 57, n^o 1 (janvier 2015) : 73–78. http://dx.doi.org/10.1134/s1066362215010117.

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Chitra, S., A. G. Shanmugamani, R. Sudha, S. Kalavathi et Biplob Paul. « Selective removal of cesium and strontium by crystalline silicotitanates ». Journal of Radioanalytical and Nuclear Chemistry 312, n^o 3 (22 avril 2017) : 507–15. http://dx.doi.org/10.1007/s10967-017-5249-3.

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Clearfield, A., A. Tripathi et D. Medvedev. « In situX-ray study of hydrothermally prepared titanates and silicotitanates ». Acta Crystallographica Section A Foundations of Crystallography 61, a1 (23 août 2005) : c3. http://dx.doi.org/10.1107/s0108767305099873.

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Zheng, Z., C. V. Philip, R. G. Anthony, J. L. Krumhansl, D. E. Trudell et J. E. Miller. « Ion Exchange of Group I Metals by Hydrous Crystalline Silicotitanates ». Industrial & ; Engineering Chemistry Research 35, n^o 11 (janvier 1996) : 4246–56. http://dx.doi.org/10.1021/ie960073k.

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Clearfield, A., A. Tripathi, D. Medvedev, A. J. Celestian et J. B. Parise. « In situ type study of hydrothermally prepared titanates and silicotitanates ». Journal of Materials Science 41, n^o 5 (mars 2006) : 1325–33. http://dx.doi.org/10.1007/s10853-006-7317-x.

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Anthony, Rayford G., Robert G. Dosch, Ding Gu et C. V. Philip. « Use of silicotitanates for removing cesium and strontium from defense waste ». Industrial & ; Engineering Chemistry Research 33, n^o 11 (novembre 1994) : 2702–5. http://dx.doi.org/10.1021/ie00035a020.

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Kaminski, M. D., L. Nuñez, M. Pourfarzaneh et C. Negri. « Cesium separation from contaminated milk using magnetic particles containing crystalline silicotitanates ». Separation and Purification Technology 21, n^o 1-2 (novembre 2000) : 1–8. http://dx.doi.org/10.1016/s1383-5866(99)00062-3.

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Chitra, S., S. Viswanathan, S. V. S. Rao et P. K. Sinha. « Uptake of cesium and strontium by crystalline silicotitanates from radioactive wastes ». Journal of Radioanalytical and Nuclear Chemistry 287, n^o 3 (17 octobre 2010) : 955–60. http://dx.doi.org/10.1007/s10967-010-0867-z.

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Thèses sur le sujet "Silicotitanates"

Tratnjek, Toni. « Développement de silicotitanates à porosité hiérarchisée pour la capture du Strontium ». Electronic Thesis or Diss., Montpellier, Ecole nationale supérieure de chimie, 2022. http://www.theses.fr/2022ENCM0022.

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L'idée générale de cette thèse repose sur l'utilisation de matière molle (tensioactifs, micelles, émulsions) pour texturer des matériaux à porosité hiérarchisée. Ces matériaux sont destinés à une utilisation en décontamination des effluents et leur texturation poreuse leur incombe des propriétés réactives augmentées ainsi que la possibilité d'être utilisés en mode continu. Cette méthodologie de texturation est connue et bien documentée pour des squelettes inorganiques en carbone ou en silice alors qu'à notre connaissance, il n'existe pas d'exemples dans la littérature concernant les silicotitanates ou les zéolithes, qui sont des sorbants connus des produits de fission visés. Le principe général de ces synthèses repose sur le mélange de deux émulsions huile-dans-eau (H/E) à haute teneur en phase interne. Lors du mélange des deux émulsions, le réseau inorganique commence à croître dans la phase aqueuse en entourant les gouttes d'huile. La maîtrise des paramètres tels que la température, le pH, ou la pression (autoclave pour une synthèse en milieu hydrothermal) qui régissent directement la réaction de polymérisation du réseau inorganique devrait conduire à l'obtention d'un monolithe. Il ne reste alors plus qu'à laver le matériau pour libérer la porosité du dit monolithe. Les émulsions seront caractérisées par microscopie optique pour évaluer la taille des gouttes d'huile, alors que les matériaux seront caractérisés par adsorption de gaz et SAXS pour connaître les propriétés du réseau de mésopores, par MEB pour évaluer la taille des macropores et par DRX pour évaluer la cristallinité du squelette
The general idea of this thesis is based on the use of soft material (surfactants, micelles, emulsions) to texture materials with hierarchical porosity. These materials are intended for use in decontamination of effluents and their porous texturing is due to increased reactive properties and the possibility of being used in continuous mode. This texturing methodology is known and well documented for inorganic carbon or silica skeletons whereas to our knowledge there are no examples in the literature concerning silicotitanates or zeolites, which are known sorbents of the intended fission products. The general principle of these syntheses is based on the mixing of two oil-in-water (H/E) emulsions with high internal phase content. When the two emulsions are mixed, the inorganic network begins to grow in the aqueous phase by surrounding the oil drops. Control of parameters such as temperature, pH, or pressure (autoclave for hydrothermal synthesis) which directly regulate the polymerization reaction of the inorganic network should lead to the production of a monolith. All that remains then is to wash the material to release the porosity of the monolith. The emulsions will be characterized by optical microscopy to evaluate the size of the oil drops, while the materials will be characterized by gas adsorption and SAXS to know the properties of the mesopores network, by SEM to assess macropore size and by XRD to assess skeletal crystallinity

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Milcent, Théo. « Mise en place d'une nouvelle méthodologie d'évaluation d'un échangeur d'ions minéral du point de vue de sa sélectivité : Cas particulier de l'optimisation structurale et microstructurale d'un silicotitanate cristallin (CST), appliqué à la décontamination d'effluents simultanément contaminés en Sr2+ et Cs+ ». Electronic Thesis or Diss., Montpellier, Ecole nationale supérieure de chimie, 2022. http://www.theses.fr/2022ENCM0010.

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Les alumino, titano et zircono-silicates zéolithiques sont des matériaux présentant des propriétés intéressantes pour de nombreuses applications dans la pétrochimie, l'agriculture, le médical, le stockage d'énergie ainsi que la décontamination d'effluents. Dans le domaine du traitement des effluents radioactifs, leurs propriété d'échange d'ions font de ces matériaux des extractants de radionucléides efficaces avec de bonnes sélectivités (e.g. césium ou strontium). Leurs compositions (le ratio Al/Si, Ti/Si, Zr/Si… ; la nature et la charge des métaux ; la nature, la charge, la concentration et la taille de l'ion échangeable) ainsi que la structure cristalline (amorphe, 2D lamellaire, 3D cage ou tunnel) vont avoir des effets sur les mécanismes d'échange ionique (cinétique, spécificité, stabilité). Ces paramètres vont aussi influencer la capacité de sorption ainsi que la sélectivité que le matériau a pour un ion. Lors de cette thèse, les relations structure/propriété de différents silicates seront étudiées dans le but d'appréhender les mécanismes de sorption. A cette fin, les synthèses de plusieurs silicates seront menées et optimisées. Par la suite, différentes techniques de caractérisation seront misent en place afin d'analyser les propriétés structurales, morphologiques et la composition des silicates. Enfin, ces matériaux seront mis en œuvre pour le traitement d'effluents modèles et d'effluents réels simulés, afin d'évaluer leurs performances et les mettre en lien avec leurs caractéristiques structurales et texturales
Alumino, titano and zircono-silicates zeolitic materials exhibit good performances in applications such as catalysis, gas separation and confinement. In addition, these kind of materials has been successfully used in different fields like petrochemistry, agriculture, medical, energy storage and nuclear decontamination. Their ion exchange properties make them very selective for radionuclides extraction (e.g. cesium or strontium) from wastewater treatment. Their composition (Al/Si, Ti/Si, Zr/Si ratio; “metal” nature and charge; labile ion nature, charge, size and concentration) and their framework structure (amorphous, 3D cage or tunnel) affect the ion exchange mechanism (i.e. kinetics, specificity, stability). These parameters may also modify the sorption capacity and the ion selectivity. In the present PhD, the relationship between structure and properties of several silicates will be studied in order to better understand their sorption mechanisms. To this end, the synthesis of different silicates will be performed and optimized. Then, their structures, morphologies and compositions will be analyzed by the application of different characterization techniques. Finally, this materials will be implemented to effluent treatments (i.e. model effluent and simulate real effluent) to evaluate their performances and find the connection between the structural and textural properties

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Chen, Tzu-Yu. « Immobilisation of caesium from crystalline silicotitanate by hot isostatic pressing ». Thesis, University of Birmingham, 2012. http://etheses.bham.ac.uk//id/eprint/3712/.

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The main aim of this project was to develop a durable ceramic wasteform by HIPing Cs-exchanged crystalline silicotitanate (CST) used for nuclear waste clean-up. The sodium form (Na-CST) and niobium substituted sodium form (Na-Nb/CST) CST were hydrothermally synthesised and characterised. The synthesised CSTs and a commercial CST containing material, IONSIV®, were subjected to ion exchange studies and then the crystal phases present after HIPing were investigated. Cs-IONSIV® was thermally decomposed and converted to two major Cs-containing phases, Cs2TiNb6O18 and Cs2ZrSi6O15, and a series of other phases. Additionally the effect of metal addition on phase formation under HIP conditions was explored. The microstructure and phase assemblage of HIPed Cs-IONSIV® samples as a function of Cs content were examined using XRD, XRF, SEM and TEM/EDX. To understand the Cs bonding environment in these Cs-containing phases, structural characterisation was undertaken using Rietveld analysis of synchrotron X-ray powder diffraction data and neutron diffraction data. The potential of these phases for hosting Cs+ and its decay product Ba2+ was also studied. This thesis is also concerned with determining the aqueous durability of these HIPed samples by carrying out MCC-1 and PCT-B leach tests. These show very low Cs leach rates and the promise of safe long-term immobilisation of Cs from CSTs as well as suggesting these phases are more leach resistant than hollandite - the material targeted for Cs sequestration in Synroc.

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Kim, Sung Hyun. « Ion exchange kinetics of cesium for various reaction designs using crystalline silicotitanate, UOP IONSIV IE-911 ». Texas A&M University, 2003. http://hdl.handle.net/1969.1/282.

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Through collaborative efforts at Texas A&M University and Sandia National Laboratories, a crystalline silicotitanate (CST), which shows extremely high selectivity for radioactive cesium removal in highly concentrated sodium solutions, was synthesized. The effect of hydrogen peroxide on a CST under cesium ion exchange conditions has been investigated. The experimental results with hydrogen peroxide showed that the distribution coefficient of cesium decreased and the tetragonal phase, the major component of CST, slowly dissolved at hydrogen peroxide concentrations greater than 1 M. A simple and novel experimental apparatus for a single-layer ion exchange column was developed to generate experimental data for estimation of the intraparticle effective diffusivity. A mathematical model is presented for estimation of effective diffusivities for a single-layer column of CST granules. The intraparticle effective diffusivity for Cs was estimated as a parameter in the analytical solution. By using the least square method, the effective diffusivities of 1.56 ± 0.14 x 10-11 m2/s and 0.68 ± 0.09x 10-11 m2/s, respectively, were obtained. The difference in the two values was due to the different viscosities of the solutions. A good fit of the experimental data was obtained which supports the use of the homogeneous model for this system. A counter-current ion exchange (CCIX) process was designed to treat nuclear waste at the Savannah River Site. A numerical method based on the orthogonal collocation method was used to simulate the concentration profile of cesium in the CCIX loaded with CST granules. To maximize cesium loading onto the CST and minimize the volume of CST, two design cases of a moving bed, where the fresh CST is pulsed into the column at certain periods or at certain concentration of cesium, were investigated. Simulation results showed that cesium removal behavior in the pilot-scale test of CCIX experiment, where the column length is 22 ft and the CST is pulsed 1 ft in every 24 hours, was well predicted by using the values of the effective diffusivities of 1.0 to 6.0 × 10-11 m2/s.

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Chapitres de livres sur le sujet "Silicotitanates"

Fox, K. M., F. C. Johnson et T. B. Edwards. « Incorporation of Mono Sodium Titanate and Crystalline Silicotitanate Feeds in High Level Nuclear Waste Glass ». Dans Ceramic Transactions Series, 149–60. Hoboken, NJ, USA : John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118144527.ch15.

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Miller, James E., Norman E. Brown, James L. Krumhansl, Daniel E. Trudell, Rayford G. Anthony et C. V. Philip. « Development and Properties of Cesium Selective Crystalline Silicotitanate (CST) Ion Exchangers for Radioactive Waste Applications ». Dans Science and Technology for Disposal of Radioactive Tank Wastes, 269–86. Boston, MA : Springer US, 1998. http://dx.doi.org/10.1007/978-1-4899-1543-6_21.

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Actes de conférences sur le sujet "Silicotitanates"

Mimura, Hitoshi, Minoru Matsukura, Tomoya Kitagawa, Fumio Kurosaki, Akira Kirishima, Daisuke Akiyama et Nobuaki Sato. « Evaluation of Adsorption Properties of U(VI) for Various Inorganic Adsorbents ». Dans 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81338.

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Large amounts of highly contaminated water over 800,000 m3 accumulated in the reactor, turbine building and the trench in the facility were generated from the nuclear accident of Fukushima NPS (BWR) caused by the Great East Japan Earthquake. At present, the cold shutdown is completed stably by the circulating injection cooling system (SARRY, KURION) for the decontamination of radioactive nuclides such as 134Cs and 137Cs using zeolites and crystalline silicotitanate (CST). Further, the Advanced Liquid Processing System (ALPS) is under operation for the decontamination of 62 nuclides such as 90Sr, 129I and 60Co, etc. However, the adsorption behaviors of actinoids through the decontamination systems are complicated, and especially their adsorption properties for zeolites and CST, major inorganic adsorbents, are not yet clarified. In near future, the decontamination of actinoids leached from the crushed fuel debris will be an important subject. In this study, the practical adsorption properties of U(VI) for various inorganic adsorbents were evaluated under different solution conditions. The adsorption properties (distribution behaviors and adsorption kinetics) were evaluated by batch adsorption method; 19 kinds of inorganic adsorbents including zeolites and CST (crystalline silicotitanate) were contacted with U(VI)) solutions. The conditions of 5 kinds of U(VI) solutions were as follows; Solution 1: [U(VI)] = 50 ppm, initial pH = 0.5 ∼ 5.5 Solution 2: [U(VI)] = 50 ppm, [NaCl] = 0.1 M, initial pH = 4.0 Solution 3: [U(VI)] = 50 ppm, [CaCl2] = 0.1 M, initial pH = 4.0 Solution 4: [U(VI)] = 4.84 mM, [NaCl] = 0.1 M, initial pH = 3.18 Solution 5: [U(VI)] = 4.86 mM, 2,994 ppm boric acid/30% seawater, initial pH = 4.25 The uptake (%) and distribution coefficient (Kd. cm3/g) were estimated by counting the radioactivity using NaI(Tl) scintillation counter and liquid scintillation counter. In the simple Solution 1, the Kd values for zeolites increased linearly with equilibrium pH up to pH 7. The Kd value for tin hydroxide had a maximum profile around pH 7 and a relatively large Kd value above 104 cm3/g was obtained. In the presence of NaCl and CaCl2 (Solution 2 and 3), relatively large Kd values above 102 cm3/g were obtained, other than mordenite and clinoptilolite, and the effect of [Ca2+] on U(VI) uptake was larger than that of [Na+]. In Solution 4 containing high concentration of U(VI), the uptake(%) was considerably lowered, while that for zeolite A, X and Y was estimated over 20%. Similar tendency was observed in Solution 5, and, in the case of granulated potassium titanate, yellow precipitate was observed on the surface due to the increase of equilibrium pH up to 5.25. The adsorption behavior of U(VI) on inorganic adsorbents is mainly governed by three steps; ion exchange, surface precipitation of hydrolysis species and sedimentation depending on equilibrium pH, and hence it should be noted the change of U(VI) chemical species. These basic adsorption data are useful for the selection of inorganic adsorbents in the Fukushima NPS decontamination process.

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Denton, Mark S., et Mercouri G. Kanatzidis. « Innovative Highly Selective Removal of Cesium and Strontium Utilizing a Newly Developed Class of Inorganic Ion Specific Media ». Dans ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16221.

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Highly selective removal of Cesium and Strontium is critical for waste treatment and environmental remediation. Cesium-137 is a beta-gamma emitter and Strontium-90 is a beta emitter with respective half-lives of 30 and 29 years. Both elements are present at many nuclear sites. Cesium and Strontium can be found in wastewaters at Washington State’s Hanford Site, as well as in wastestreams of many Magnox reactor sites. Cesium and Strontium are found in the Reactor Coolant System of light water reactors at nuclear power plants. Both elements are also found in spent nuclear fuel and in high-level waste (HLW) at DOE sites. Cesium and Strontium are further major contributors to the activity and the heat load. Therefore, technologies to extract Cesium and Strontium are critical for environmental remediation waste treatment and dose minimization. Radionuclides such as Cesium-137 and Strontium-90 are key drivers of liquid waste classification at light water reactors and within the DOE tank farm complexes. The treatment, storage, and disposal of these wastes represents a major cost for nuclear power plant operators, and comprises one of the most challenging technology-driven projects for the DOE Environmental Management (EM) program. Extraction technologies to remove Cesium and Strontium have been an active field of research. Four notable extraction technologies have been developed so far for HLW: solvent extraction, prussian blue, crystalline silicotitanate (CST) and organic ion-exchangers (e.g., resorcinol formaldehyde and SuperLig). The use of one technology over another depends on the specific application. For example, the waste treatment plant (WTP) at Hanford is planning on using a highly-selective organic ion-exchange resin to remove Cesium and Strontium. Such organic ion-exchangers use molecular recognition to selectively bind to Cesium and Strontium. However, these organic ion-exchangers are synthesized using multi-step organic synthesis. The associated cost to synthesize organic ion-exchangers is prohibitive and seriously limits the scope of applications for organic ion-exchangers. Further issues include resin swelling, potential hydrogen generation and precluding final disposal by vitrification without further issues. An alternative to these issues of organic ion-exchangers is emerging. Inorganic ion-exchangers offer a superior chemical, thermal and radiation stability which is simply not achievable with organic compounds. They can be used to remove both Cesium as well as Strontium with a high level of selectivity under a broad pH range. Inorganic ion-exchangers can operate at acidic pH where protons inhibit ion exchange in alternative technologies such as CST. They can also be used at high pH which is typically found in conditions present in many nuclear waste types. For example, inorganic ion-exchangers have shown significant Strontium uptake from pH 1.9 to 14. In contrast to organic ion-exchangers, inorganic ion-exchangers are not synthesized via complex multi-step organic synthesis. Therefore, inorganic ion-exchangers are substantially more cost-effective when compared to organic ion-exchangers as well as CST. Selective removal of specified isotopes through ion exchange is a common and proven treatment method for liquid waste, yet various aspects of existing technologies leave room for improvement with respect to both cost and effectiveness. We demonstrate a novel class of inorganic ion-exchangers for the selective removal of cesium and strontium (with future work planned for uranium removal), the first of a growing family of patent-pending, potentially elutable, and paramagnetic ion-exchange materials [1]. These highly selective inorganic ion-exchangers display strong chemical, thermal and radiation stability, and can be readily synthesized from low-cost materials, making them a promising alternative to organic ion-exchange resins and crystalline silicotitanate (CST). By nature, these inorganic media lend themselves more readily to volume reduction (VR) by vitrification without the issues faced with organic resins. In fact, with a simple melting of the KMS-1 media at 650–670 deg. C (i.e., well below the volatilization temperature of Cs, Sr, Mn, Fe, Sb, etc.), a VR of 4:1 was achieved. With true pyrolysis at higher temperatures or by vitrification, this VR would be much higher. The introduction of this new family of highly specific ion-exchange agents has potential to both reduce the cost of waste processing, and enable improved waste-classification management in both nuclear power plants (for the separation of Class A from B/C wastes) and DOE tank farms [for the separation of low level waste (LLW) from high level waste (HLW)]. In conclusion, we demonstrate for the first time a novel inorganic ion-exchanger for the selective removal of Cesium and Strontium. These inorganic ion-exchangers are chemical, thermal and radiation stable. These inorganic ion-exchangers can be synthesized in a cost-effective way which makes them significantly more effective than organic ion-exchange resin and CST. Finally, new thermal options are afforded for their final volume reduction, storage and disposal.

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Rapports d'organisations sur le sujet "Silicotitanates"

Balmer, M. L., et B. C. Bunker. Waste forms based on Cs-loaded silicotitanates. Office of Scientific and Technical Information (OSTI), avril 1995. http://dx.doi.org/10.2172/86952.

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Harbour, J. R., et M. K. Andrews. Glass formulation requirements for DWPF coupled operations using crystalline silicotitanates. Office of Scientific and Technical Information (OSTI), janvier 1997. http://dx.doi.org/10.2172/491474.

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Andrews, M. K., et J. R. Harbour. Glass formulation requirements for Hanford coupled operations using crystalline silicotitanates (CST). Office of Scientific and Technical Information (OSTI), mai 1997. http://dx.doi.org/10.2172/554132.

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Dosch, R. G., E. A. Klavetter, H. P. Stephens, N. E. Brown et R. G. Anthony. Crystalline silicotitanates--new ion exchanger for selective removal of cesium and strontium from radwastes. Office of Scientific and Technical Information (OSTI), août 1996. http://dx.doi.org/10.2172/369706.

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McCabe, D. J. Crystalline silicotitanate examination results. Office of Scientific and Technical Information (OSTI), mai 1995. http://dx.doi.org/10.2172/565003.

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DARREL, WALKER. Digestion of Crystalline Silicotitanate (CST). Office of Scientific and Technical Information (OSTI), novembre 2004. http://dx.doi.org/10.2172/837905.

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Schlahta, S. N., R. Carreon et J. A. Gentilucci. Crystalline silicotitanate gate review analysis. Office of Scientific and Technical Information (OSTI), novembre 1997. http://dx.doi.org/10.2172/565556.

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Walker, D. D. Modeling of Crystalline Silicotitanate Ion Exchange Columns. Office of Scientific and Technical Information (OSTI), mars 1999. http://dx.doi.org/10.2172/4975.

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Balmer, Marie Lou, Tina Nenoff et Navrotsky. New Silicotitanate Waste Forms ; Development and Characterization. Office of Scientific and Technical Information (OSTI), juin 1999. http://dx.doi.org/10.2172/829958.

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Balmer, Mari Lou, Tina Nenoff, Alexandra Navrotsky et Yali Su. New Silicotitanate Waste Forms ; Development and Characterization. Office of Scientific and Technical Information (OSTI), juin 2000. http://dx.doi.org/10.2172/829961.

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