Relevant bibliographies by topics / Radioactive wastes – Thermal properties

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers

Academic literature on the topic 'Radioactive wastes – Thermal properties'

Author: Grafiati
Published: 4 June 2021
Last updated: 16 February 2022

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Journal articles on the topic "Radioactive wastes – Thermal properties"

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El-Didamony, H., T. A. Bayoumi, and M. I. Sayed. "Evaluation of the Properties of Cemented Liquid Scintillator Wastes under Flooding Scenario in Various Aqueous Media." ISRN Chemical Engineering 2012 (December 26, 2012): 1–11. http://dx.doi.org/10.5402/2012/373795.

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Experiments simulating flooding scenario in various aqueous media for a long period were carried out to determine the adequacy of cement-clay composite for solidification/stabilization of spent organic radioactive liquid scintillator wastes. The final cement waste form blocks were immersed in three aqueous media, namely, seawater, groundwater, and tapwater. The immersion process lasted for increasing periods up to 540 days. Following each predetermined interval period, physical and mechanical evaluations of the immersed blocks were determined. In addition, the change in the hydration products was followed by X-ray diffraction and infrared spectroscopy as nondestructive analyses to recognize the deterioration in the microstructure that may occur due to the flooding event. Thermal analysis and scanning electron microscopy were performed to confirm the data obtained.
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Mallants, Dirk, Karl Travis, Neil Chapman, Patrick V. Brady, and Hefin Griffiths. "The State of the Science and Technology in Deep Borehole Disposal of Nuclear Waste." Energies 13, no. 4 (February 14, 2020): 833. http://dx.doi.org/10.3390/en13040833.

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This Special Issue of the Energies Journal on Deep Borehole Disposal of Nuclear Waste has delivered a timely update on the science and technology of borehole disposal and the types of radioactive wastes it could potentially accommodate. The Special Issue papers discuss (i) circumstances under which a national waste management programme might wish to consider deep borehole disposal; (ii) a status report of deep borehole disposal options in Germany; (iii) the analysis of corrosion performance of engineered barrier systems; (iv) a review of the potential cementing systems suitable for deep borehole disposal; (v) the thermal evolution around heat-generating waste for a wide range of material properties and disposal configurations; (vi) a geochemical analysis of deep brines focussed on fluid-rock interactions; (vii) post-closure performance assessment calculations for deep borehole disposal of Cs/Sr capsules and an example safety case for (viii) horizontal and (ix) vertical deep borehole disposal of nuclear wastes.
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Jiang, Zao, Zhong Hui Xu, Qin Shuai, Ping Li, and Ya Hong Xu. "Thermal Stability of Geopolymer - Sr Contaminated Zeolite A Blends." Key Engineering Materials 727 (January 2017): 1089–97. http://dx.doi.org/10.4028/www.scientific.net/kem.727.1089.

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Geopolymer have gradually become an alternative materials for hazardous and radioactive waste immobilization. However, the compatibility between radioactive waste and geopolymer in various extreme conditions are still not clear. In this study, the thermal stability of geopolymer solidified product of Sr contaminated zeolite A was investigated. For this purpose, the specimens after standard curing were subjected to temperatures of 600, 700 and 800 degrees C for 2h. Freeze-thaw cycles were also employed to test the thermal stability of geopolymer matrices. Meanwhile, changes in the leaching characteristics and physical properties were analyzed. Analysis showed that geopolymer - Sr contaminated zeolite A blends exhibited excellent thermal stability. Although elevated temperature and freeze-thaw cycles led to the deterioration of geopolymer matrices, the leaching rate and mechanical properties of solidified product were still acceptable. The resluts obtained indicated that geopolymer appeared to be very suitable for radioactive waste immobilization.
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Woignier, Thierry, Juan Primera, and Jerôme Reynes. "Nanoporous Glasses for Nuclear Waste Containment." Journal of Nanomaterials 2016 (2016): 1–10. http://dx.doi.org/10.1155/2016/4043632.

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Research is in progress to incorporate nuclear waste in new matrices with high structural stability, resistance to thermal shock, and high chemical durability. Interactions with water are important for materials used as a containment matrix for the radio nuclides. It is indispensable to improve their chemical durability to limit the possible release of radioactive chemical species, if the glass structure is attacked by corrosion. By associating high structural stability and high chemical durability, silica glass optimizes the properties of a suitable host matrix. According to an easy sintering stage, nanoporous glasses such as xerogels, aerogels, and composite gels are alternative ways to synthesize silica glass at relatively low temperatures (≈1,000–1,200°C). Nuclear wastes exist as aqueous salt solutions and we propose using the open pore structure of the nanoporous glass to enable migration of the solution throughout the solid volume. The loaded material is then sintered, thereby trapping the radioactive chemical species. The structure of the sintered materials (glass ceramics) is that of nanocomposites: actinide phases (~100 nm) embedded in a vitreous silica matrix. Our results showed a large improvement in the chemical durability of glass ceramic over conventional nuclear glass.
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Vejmelkova, E., M. Cachova, L. Scheinherrova, P. Konvalinka, M. Keppert, P. Bezdicka, and R. Cerny. "Mechanical and thermal properties of concrete suitable for radioactive waste disposal sites." IOP Conference Series: Materials Science and Engineering 385 (July 2018): 012061. http://dx.doi.org/10.1088/1757-899x/385/1/012061.

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Ghattas, N. K., N. E. Ikladious, and H. A. Shatta. "Radioactive Waste from Nuclear Power Plants Part II. Thermal Properties of Waste/Polymer Products." Isotopenpraxis Isotopes in Environmental and Health Studies 25, no. 3 (January 1989): 98–101. http://dx.doi.org/10.1080/10256018908624068.

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Kuznetsov, D. G., V. V. Ivanov, I. B. Popov, and B. G. Ershov. "Effect of thermal annealing on properties of borobasalt systems containing radioactive waste fractions." Radiochemistry 54, no. 2 (April 2012): 193–97. http://dx.doi.org/10.1134/s1066362212020178.

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Koťátková, Jaroslava, Monika Čáchová, Petr Bezdička, Eva Vejmelková, Petr Konvalinka, Lucie Zemanová, and Robert Černý. "Influence of Supplementary Cementitious Materials on the Properties of Concrete for Secondary Protection Barrier in Radioactive Waste Repositories." Key Engineering Materials 760 (January 2018): 96–101. http://dx.doi.org/10.4028/www.scientific.net/kem.760.96.

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The paper studies the basic physical, mechanical and thermal properties of concrete with three types of supplementary materials for use in waste repositories. The used supplementary materials were natural zeolite, brick dust and metashale. These have pozzolanic properties which modify the parameters of resulting matrix and the unreacted part of the material offers sites for sorption of hazardous species. Results showed rather negative influence of natural zeolite on compressive strength and porosity, as well as thermal properties when compared to brick dust and metashale.
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Bamonte, Patrick, and Pietro Gambarova. "Properties of Concrete Subjected to Extreme Thermal Conditions." Journal of Structural Fire Engineering 5, no. 1 (March 1, 2014): 47–62. http://dx.doi.org/10.1260/2040-2317.5.1.47.

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Durability, high-temperature resistance, impact and blast resilience, radiation-shielding properties, irradiation endurance and - of course - good mechanical properties are required of the cementitious composites to be used in a variety of high-performance structures. Among these, tall buildings, road and railway tunnels, off-shore platforms, gasification plants, wind and solar mills for the production of "clean" energy should be mentioned, as well as nuclear power plants, and radioactive- and hazardous-waste repositories. Hence, understanding, measuring and modelling concrete behavior under extreme environmental conditions is instrumental in making concrete structures safer and more efficient. To this end, the hot and residual properties associated with the exposure to high temperature, fire and thermal shock are treated in this paper. Reference is made to ordinary vibrated concrete (Normal-Strength Concrete - NSC), as well as to a number of innovative cementitious composites, such as Fiber-Reinforced Concrete - FRC, High-Performance/High-Strength Concrete - HPC/HSC, Ultra High-Performance/Very High-Strength Concrete - UHPC /VHSC, Self-Compacting/Consolidating Concrete - SCC, Light-Weight Concrete - LWC, shotcrete and high-strength mortars. It is shown that these materials can be "tailored" according to a variety of requirements and functions, even if several aspects of their behavior (like spalling in fire and long-term mechanical properties under sustained high temperature) are still open to investigation.
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Kuznetsov, D. G., V. V. Ivanov, I. B. Popov, and B. G. Ershov. "Effect of thermal annealing on the properties of boron-containing basalt systems containing radioactive waste components." Radiochemistry 51, no. 1 (February 2009): 73–76. http://dx.doi.org/10.1134/s1066362209010160.

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Dissertations / Theses on the topic "Radioactive wastes – Thermal properties"

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ORTIZ, ANGEL V. "Desenvolvimento de processo de obtenção de nanopartículas de sílica a partir de resíduo de fonte renovável e incorporação em polímero termoplástico para a fabricação de nanocompósito." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/27498.

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A tecnologia de nanocompósitos é aplicável a uma vasta gama de polímeros termoplásticos e termofixos. A utilização de subprodutos da cana de açúcar tem sido extensivamente estudada como fonte de reforços para os nanocompósitos. O bagaço da cana é largamente utilizado na cogeração de energia e, como resultado da queima deste material, são produzidas milhões de toneladas de cinzas. Para este trabalho, sílica contida nas cinzas do bagaço da cana de açúcar foi extraída por método químico e método térmico. O método térmico se mostrou mais eficiente levando a uma pureza de mais de 93 % em sílica, enquanto o método químico gerou sílica bastante contaminada com cloro e sódio provenientes dos reagentes da extração. As partículas de sílica obtidas foram avaliadas por espalhamento de luz dinâmico (DSL) e apresentaram tamanho médio de 12 μm. Estas partículas foram submetidas à moagem em moinho de bolas e na sequência a tratamento sonoquímico em meio líquido. As partículas de sílica tratadas no processo sonoquímico a 20 kHz, potência de 500 W e 90 minutos tiveram suas dimensões reduzidas a escala nanométrica da ordem de dezenas de nanômetros. A nanossílica obtida foi então incorporada como reforço em polietileno de alta densidade (HDPE). Ensaios mecânicos e termo-mecânicos mostram ganhos de propriedades mecânicas, com exceção da propriedade de resistência ao impacto. O ensaio de deflexão térmica (HDT) mostrou que a incorporação deste reforço no HDPE levou a um pequeno aumento nesta propriedade relação ao HDPE puro. A cristalinidade dos nanocompósitos gerados foi avaliada por meio de calorimetria exploratória diferencial (DSC) e observou-se um decréscimo de cristalinidade do material quando a incorporação de reforço foi de 3%. O material irradiado a 250 kGy com feixe de elétrons mostra ganhos acentuados na principais propriedades do mesmo, principalmente devido ao alto nível de reticulação do HDPE irradiado.
Tese (Doutorado em Tecnologia Nuclear)
IPEN/T
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
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FERREIRA, EDUARDO G. A. "Avaliação da alteração nas propriedades da pasta de cimento em ambiente de repositório." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10208.

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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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FERREIRA, EDUARDO G. A. "Modelagem descritiva do comportamento do cimento Portland em ambiente de repositório para rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2017. http://repositorio.ipen.br:8080/xmlui/handle/123456789/28423.

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Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES)
A deposição de rejeitos radioativos em repositórios geológicos profundos vem sendo estudada nos últimos anos em diversos países. Materiais à base de cimento são utilizados nesses repositórios como material estrutural, matriz de imobilização de rejeitos ou material de preenchimento. Compreender o desempenho desse material é essencial para garantir a segurança da instalação durante o seu tempo de vida útil (de milhares a centenas de milhares de anos, dependendo do tipo de rejeito). Este trabalho objetiva modelar o comportamento em longo prazo do cimento Portland e estudar a influência de diversos fatores na hidratação e na evolução desse material. A modelagem descritiva abordou a hidratação do cimento nas condições ambientais esperadas no repositório e os efeitos desses fatores em propriedades mecânicas, mineralógicas e morfológicas do cimento. Os fatores ambientais considerados relevantes neste trabalho foram: alta temperatura e pressão, penetração de água subterrânea contendo íons quimicamente agressivos ao cimento e a presença do campo de radiação proveniente dos rejeitos. Ensaios acelerados de degradação também foram realizados para corroborar com o modelo descrito. Observou-se uma sinergia entre diversos fatores na degradação do cimento, como a influência da temperatura e da radiação em reações deletérias ao material. O resultado da modelagem apontou três principais possíveis causas de falha nas barreiras artificiais: a) a formação de um caminho preferencial; b) a perda de resistência e coesão do material; e c) o aumento na corrosão das estruturas metálicas. A descrição do modelo apresentada é a base para a modelagem matemática e a análise de segurança dos repositórios estudados no Brasil.
Tese (Doutorado em Tecnologia Nuclear)
IPEN/T
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
CAPES:1231206
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Li, Kang-Wen K. "Remote determination of radioactive molten glass properties." Diss., Georgia Institute of Technology, 1991. http://hdl.handle.net/1853/13055.

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Heath, Paul. "Alternative processing methods for the thermal treatment of radioactive wastes." Thesis, University of Sheffield, 2015. http://etheses.whiterose.ac.uk/9674/.

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The UK has large volumes of radioactive materials which are classified as Intermediate Level Waste (ILW). The baseline treatment for these wastes is encapsulation via cementation, however, this method is not ideally suited for numerous wastes, both in the UK and globally. Alternative thermal processing methods for these materials may be capable of producing wasteforms with improved properties. This thesis presents a series of scoping studies on the thermal treatment of a diverse range of ILWs in order to identify the potential benefits and pits falls of such processes. The wastes selected were Tri-Structural Isotropic (TRISO) Fuel Particles, Prototype Fast Reactor (PFR) raffinate, SIXEP sand/clinoptilolite ion exchange materials and SrTreat® Ion exchange material. The scoping studies performed showed promise for the thermal treatment of all selected waste streams. A summary of the main results for each waste stream are provided below; TRISO Fuel Particles: Immobilisation focused on encapsulation of the particles in highly durable glass matrices. Alumino-borosilicates were determined to be the most effective glass composition for the production of composites, in terms of both their physical and chemical properties. The ability of Hot Isostatic Pressing (HIPing) to improve composites was investigated. Unfortunately, this was shown to result in severe fracturing within the composite. This was hypothesised to occur as a result of excessive pressurisation during the cooling cycle. The HIP process did show some benefits in terms of particle coating properties and with small alterations to the HIP cycle utilised it should also be possible to eliminate the detrimental fracturing features. PFR Raffinate: The vitrification of PFR raffinate was investigated using the G73 glass composition, a glass which has been previously proposed for the immobilisation of other ILWs. This glass was proven to be capable of accommodating a waste loading of up to 20 wt% PFR raffinate. The glass produced was homogeneous with good waste retention, had no noted crystal formation, an aqueous durability comparable to currently employed HLW glasses and the thermal characteristics necessary for industrial scale up. Further study should be performed on the ability of this waste to retain Cs during processing and in aqueous solution. SIXEP Sand/Clinoptilolite Waste: SIXEP sand/clinoptilolite was processed at 95 wt% with a 50 % volume reduction by HIPing. The waste produced was a phase separated glass-ceramic. The wasteform was deemed to be suitable for ILW immobilisation and had an exceptional Cs ii retention in aqueous solutions. However, the presence of an alkali earth sulphate phase increased the Sr release to solution. Attempts to qualify the suitability of this wasteform for disposal, developed methodologies to investigate the properties of phase separated materials. A combination of vertical scanning interferometry (VSI), dissolution experiments and SEM imaging was shown to be capable of elucidating the dissolution behaviour based upon compositional variation. SrTreat®: SrTreat® was processed at 100% waste loading via HIPing. This aim was to investigate the potential for developing ion exchange columns which could subsequently be HIPed, as such, providing a complete waste treatment solution. The HIP process produced a monolithic, mixed phase sodium titanate ceramic. This ceramic was formed by the sintering of individual grain structures and retained the compositional variations seen in the granular waste stream. The wasteform was porous around the grain edges, determined to occur as a result of carbonate formation prior to HIPing. The carbonation of this material is likely to limit the potential to utilise HIPing as a disposal methodology for these wastes. However the aqueous dissolution behaviour of these wastes was still favourable and the process was shown to create a significant reduction in waste volume. The work performed in this thesis has shown that various methods for thermal treatment can be rapidly investigated to determine the potential benefits and pit falls. The application of thermal treatments was shown to be capable of producing significant improvements in wasteform quality by comparison with the cementitious alternatives.
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Shvareva, Tatiana Yurlevna Albrecht-Schmitt Thomas E. "Design and properties of novel uranium-containing layered and framework materials." Auburn, Ala., 2006. http://repo.lib.auburn.edu/2006%20Fall/Dissertations/SHVAREVA_TATIANA_11.pdf.

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Signoret, Christian. "Réseaux polyuréthannes classiques et contenant des motifs furanniques pour le confinement de déchets radioactifs : relations structure-propriétés." Grenoble INPG, 1989. http://www.theses.fr/1989INPG0088.

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Etude des proprietes mecaniques, de la stabilite thermique de la diffusion de l'eau et de sels radioactifs dans des polyurethannes. Les polyetherurethannes souples ont un comportement moyen a la temperature et a la diffusion. Les polyesterurethannes ont un meilleur comportement mais sont hydrolyses rapidement les polyetherurethannes rigides (tv=20 a 40#oc) sont le meilleur compromis; amelioration de la tenue en temperature vers 350-500#oc par addition de derives furanniques
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MOURAO, ROGERIO P. "Amortecedores de impacto em embalagens para transporte de materiais radioativos: uma metodologia para sua avaliacao." reponame:Repositório Institucional do IPEN, 2002. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11068.

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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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REGO, MARIA E. de M. "Gestão dos rejeitos radioativos gerados na produção de 99Mo por fissão nuclear." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10584.

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IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Ling, Jie Albrecht-Schmitt Thomas E. "Hydrothermal syntheses, structures, and properties of new iodate and selenite compounds of transition metals, lanthanides, and actinides." Auburn, Ala, 2007. http://repo.lib.auburn.edu/2007%20Fall%20Dissertations/LING_JIE_49.pdf.

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Books on the topic "Radioactive wastes – Thermal properties"

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McEachern, Rod J. Oxidation behaviour of noble-metal inclusions in used UOb2s nuclear fuel. Pinawa, Man: Research Chemistry Branch, Whiteshell Laboratories, 1997.

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International, Incineration Conference (13th 1994 Houston Texas). 1994 International Incineration Conference: Thermal treatment of radioactive, hazardous chemical, mixed, munitions, and pharmaceutical wastes : proceedings of the 1994 International Incineration Conference, Houston, Texas, U.S.A. Irvine, Calif: available through the University of California, Irvine, Office of Environment, Health & Safety, 1994.

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Incineration, Conference (11th 1992 Albuquerque New Mexico). 1992 Incineration Conference: Thermal treatment of radioactive, hazardous chemical, mixed and medical wastes : proceedings of the 1992 Incineration Conference, Albuquerque, New Mexico, May 11-15, 1992. [Tucson, AZ: Laser Options, 1992.

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Lee, A. S. Buckling analysis of spent fuel basket. Washington, D.C: Division of Industrial and Medical Nuclear Safety, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1995.

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Nazarov, Vyacheslav, Roman Sandu, and Dmitriy Makarenkov. Technique and technology of combined processing of solid waste. ru: INFRA-M Academic Publishing LLC., 2020. http://dx.doi.org/10.12737/996365.

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The educational manual provides information about industrial and domestic waste. The properties of the lithosphere and the soil components. The estimation of soil pollution by industrial and household waste. The peculiarities of classification of wastes and provides criteria for determining risk. Describe the General pattern of the combined methods of processing that use mechanical, physical, thermal and biothermal recycling processes. In detail the construction described granulating equipment, methods of intensification of processes, process flow sheets and engineering calculation methods. Special attention is given to the thermal methods of waste treatment, process lines, constructions of furnaces and reactors. On the basis of the system approach with use of data of environmental monitoring are considered the methodology for selecting the most available technology. Meets the requirements of Federal state educational standards of higher education of the last generation. Intended for independent work of undergraduates majoring in 20.04.01 "Technospheric safety" (master level), 20.03.01 "Technosphere safety" (bachelor level), 18.03.01 "Chemical technology" 18.03.02 "Energy and resource saving processes in chemical technology, petrochemistry and biotechnology". Can be useful for engineers and technicians of chemical industry and related industries.
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T, Rothfuchs, Gesellschaft für Strahlen- und Umweltforschung., and Battelle Memorial Institute. Office of Nuclear Waste Isolation., eds. Brine migration test: Asse Salt Mine, Federal Republic of Germany : final report. München: Gesellschaft für Strahlen- und Umweltforschung, 1988.

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Agency, International Atomic Energy, ed. Application of thermal technologies for processing of radioactive waste. Vienna: IAEA, 2006.

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Chemical Durability and Related Properties of Solidified High-Level Waste Forms (Technical Reports Series (International Atomic Energy Agency)). Intl Atomic Energy Agency, 1986.

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Agency, International Atomic Energy, ed. Chemical durability and related properties of solidified high-level waste forms: Final report of a co-ordinated research programme on the evaluation of solidified high-level waste forms. Vienna: International Atomic Energy Agency, 1985.

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J, Cudahy, and United States. Dept. of Energy. Office of Technology Development, eds. Integrated thermal treatment systems study: U.S. Department of Energy Internal Review Panel report. Washington, DC: U.S. Dept. of Energy, Assistant Secretary for Environmental Management, Office of Technology Development, 1995.

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Book chapters on the topic "Radioactive wastes – Thermal properties"

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Miller, James E., Norman E. Brown, James L. Krumhansl, Daniel E. Trudell, Rayford G. Anthony, and C. V. Philip. "Development and Properties of Cesium Selective Crystalline Silicotitanate (CST) Ion Exchangers for Radioactive Waste Applications." In 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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"Thermal, hydraulic, mechanical, chemical and biological processes." In Containment of High-Level Radioactive and Hazardous Solid Wastes with Clay Barriers, 249–314. CRC Press, 2010. http://dx.doi.org/10.1201/9781482266245-12.

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Biswal, Trinath, and Junaid Ahmad Malik. "Effect of Pollution on Physical and Chemical Properties of Soil." In Advances in Environmental Engineering and Green Technologies, 1–37. IGI Global, 2021. http://dx.doi.org/10.4018/978-1-7998-7062-3.ch001.

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The soil is considered to be one of the most important substances for the existence of the biotic community. The quality of the soil is continually degrading due to the continuous exploitation of human activity. The superiority of a soil is rated on the basis of its chemical and physical characteristics. The contaminants added to the soil mainly because of human activity change the usual function and ecological properties and cause of negative impacts on agricultural productivity and soil health. The property of the soil is potentially affected by urban wastes, industrial wastes, sewage water, mining wastes, oil, radioactive wastes, deforestation, and massive use of fertilizers and pesticides. Heavy metal contamination of the soil is a vital environmental problem because it is the cause of adverse effects on the biological community through the contamination of the food chain. A continuous exposure of municipal solid waste (MSW) in the landfill sites causes leachate formation; this is percolated inside the soil leading to the change in properties.
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Khairuddin, Nozieana, Md Bazlul Mobin Siddique, Mohammad Sobri Merais, Nurul Husna Che Hamzah, and Dayangku Nurshahirah Awang Wahab. "Nano-Cellulosic Fibers from Agricultural Wastes." In Cellulose [Working Title]. IntechOpen, 2021. http://dx.doi.org/10.5772/intechopen.98637.

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In recent years, the potential of agricultural wastes has received increasing attention from academia and industry. The aim has been to identify strategies for the conversion of low-value wastes into new materials and other value-added products. Cellulose is a naturally abundant polymer that is readily available in various agricultural wastes. It is a linear polymer consisting of β-D-glucopyranose units (disaccharides) joined by glycosidic β-1,4 bonds. Nanoparticles can be extracted from cellulose fibers using a top-down mechanically or chemically treatment. Cellulose nanomaterials have generated significant interest due to their intrinsic properties such as large surface-to-volume ratios, high tensile strength, stiffness, and flexibility in addition to good dynamic mechanical, electrical, and thermal properties. The use of nanocellulose for reinforcement in matrices improves thermo-mechanical properties, decreases the sensitivity of polymers to water, and preserves biodegradability. The mixing of nanocellulose with polysaccharides improves mechanical properties. Nano-sized cellulose fibers possess unique physical, chemical, and morphological characteristics. Hence, nano-sized cellulose fibers are considered versatile materials for addition to polymers, and application in high gas barriers and packaging materials. Other uses include electronic devices, foods, medicine, cosmetics, and health care. This chapter focuses on the cellulose nanofibers attained from banana, pineapple and corn-based agricultural wastes.
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Ghiloufi, Imed. "Modeling and Simulation of Chemical System Vaporization at High Temperature: Application to the Vitrification of Fly Ashes and Radioactive Wastes by Thermal Plasma." In Heat and Mass Transfer - Modeling and Simulation. InTech, 2011. http://dx.doi.org/10.5772/22562.

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Rubin, James B., and Craig M. V. Taylor. "Enhancing the Properties of Portland Cements Using Supercritical Carbon Dioxide." In Green Chemistry Using Liquid and Supercritical Carbon Dioxide. Oxford University Press, 2004. http://dx.doi.org/10.1093/oso/9780195154832.003.0021.

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Supercritical CO2 (sc CO2) is being used to accelerate the natural aging reactions (i.e., carbonation) of Portland cement. This treatment method alters the bulk properties of cement, producing profound changes in both structure and chemical composition. As a result of these changes, the mechanical and transport properties of these cements are also dramatically affected, and they display reduced porosity, permeability and pH, as well as increased density and compressive strength. Two areas of application for the sc CO2 treatment of portland cement have been undergoing investigation. Because the calcium carbonate (CaCO3) formed during the accelerated carbonation reaction is found to have excellent cementing properties, it is possible to replace a large fraction of the relatively expensive Portland cement with industrial waste products, such as fly ash and kiln dusts, which have inherently inferior cementing properties. These modified Portland cements, incorporating significant volume fractions of industrial wastes, can be used as low-cost building materials. The second area of application deals with the enhancement of Portland cements used to encapsulate waste products. Portland cement is used as an immobilization matrix for low- and intermediate-level radioactive waste by both the U.S. federal government (Huang et al., 1994) and civilian nuclear power companies in the United States (Wilk, 1997) and abroad (Wilding, 1992). Transportation issues relating to water content, radiolysis, and radionuclide content often preclude the ultimate disposal of these cemented wasteforms (U.S. DOE, 1996). However, the structural and chemical changes produced by accelerated carbonation have been shown to address these problems satisfactorily (Hartmann et al., 1999).
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Bunker, Bruce C., and William H. Casey. "Glass Dissolution and Leaching." In The Aqueous Chemistry of Oxides. Oxford University Press, 2016. http://dx.doi.org/10.1093/oso/9780199384259.003.0023.

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Oxide glasses represent some of the most important and prevalent materials that we encounter in our daily lives. The glass industry in the United States produces more than 75,000 glass products, with annual production estimated to be around 20,000,000 t. Roughly 50% of this production is for glass containers for food, beverages, and other liquids. Everyone relies on transparent glass windows for their homes, cars, and even their cell phones. Fiberglass provides insulation for our homes and businesses. We rely on glass for many optical systems, ranging from eyeglasses to microscope lenses to optical fiber communications. Glass is also an optically pleasing material found in many works of art, including stained glass windows. Glass even plays a role in energy transport and storage, being an important electrical insulator used in devices ranging from transformers to batteries. Glass compositions need to be optimized for specific applications, with important parameters being melting properties, thermal conductivity, thermal expansion, strength, dielectric properties, and, of course, optical properties. In most of these applications, glass objects encounter water, either to perform their basic functions or as a result of long-term environmental exposure. This means the chemical properties of many glasses also need to be optimized. Fortunately, borosilicate glasses, which represent the most widely used technological glass compositions, tend to exhibit a high level of resistance to aqueous attack. Understanding the kinetics and mechanisms of glass dissolution is critically important to the nuclear power and defense industries, which involves how to dispose of nuclear wastes safely. These wastes can be exceedingly complex, and contain almost every element found in the Periodic Table. The challenge is to incorporate these wastes into solids that encapsulate radionuclides safely for millions of years. Glass is an attractive option as a waste form because glass melts can accommodate almost all the constituents found in nuclear wastes. However, the deployment of glass waste forms requires the ability to predict the stability of the waste out to exceedingly long times based on science-based glass-dissolution models.
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Bunker, Bruce C., and William H. Casey. "The Ion Exchange Behavior of Oxides." In The Aqueous Chemistry of Oxides. Oxford University Press, 2016. http://dx.doi.org/10.1093/oso/9780199384259.003.0017.

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Oxides comprise the most common ion-exchange materials on our planet, with the clay minerals alone, formed by the weathering of rock, having a total mass of around 1025 g. This mass represents almost one-third of the total mass of Earth’s crust and is more than six times the mass of Earth’s oceans. These fine-grained ion exchange materials play a major role in mediating the concentrations of ionic species found in freshwater, groundwater, and our oceans (see Chapter 18). Oxide ion exchangers are also of critical importance in removing contaminants from the environment. Nowhere is this role more apparent than in the removal and sequestration of radioactive elements such as 137Cs, 90Sr, and 99Tc, which are serious hazards present in nuclear wastes. Oxide ion exchangers exhibit several properties that make them materials of choice for treating nuclear wastes, including high selectivity, enhanced stability to radiation damage relative to organic exchangers, and the potential as materials to be condensed further into solid waste after they are loaded with radioactive species. Oxide exchangers are extremely useful for extracting valuable cations from complex fluids, such as the lithium used in our highest energy density batteries. Ion exchange also represents a pathway for creating unique nanomaterials, with applications including battery separators, catalysts, optical materials, magnets, and materials for drug delivery. Oxides materials can exhibit exceptional properties as both cation and anion exchangers for a wide range of separation and water treatment technologies. Although the total ion-exchange capacity of an oxide is important for some applications, such as the deionization of water, separations require the use of oxides and hydroxides having the highest degree of ion-exchange selectivity. For selectivity, oxides must be designed with specific sites that exhibit a much higher affinity for one ion than any other, which requires much more sophistication than just generating a net charge. Here, we describe the key factors that control both the capacity and selectivity of inorganic ion exchangers, including (1) the role of acid–base reactions in controlling surface charge and ion-exchange capacity, (2) the role of local charge distributions in determining ion-exchange selectivity, and (3) the effect of shape and selective solvation on enhancing that selectivity.
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"Bio-Mediated Synthesis of Nanomaterials for Packaging Applications." In Materials Research Foundations, 96–117. Materials Research Forum LLC, 2021. http://dx.doi.org/10.21741/9781644901571-4.

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Change in lifestyle of humans in this present generation with huge dependence on packaging materials has encouraged several studies on development of new variety of packaging materials. Emphasis on replacement of existing non-biodegradable packaging materials with biodegradable materials paved the way for the use of biopolymers. Lack of properties, such as thermal stability and mechanical strength in biopolymers led to the development of biopolymer nanocomposites by adding metal/metal oxide nanoparticles as fillers into the biopolymers. Metal/metal oxide nanoparticles improve mechanical/tensile strength, thermal stability as well as antimicrobial properties of the binding and receiving polymer matrix. Bio-mediated synthesis of metal/metal oxide nanoparticles result in the development of novel packaging materials at a low cost and without releasing hazardous wastes into the environments. Novel packaging materials with metal/metal oxide nanoparticles as additives are capable of increasing the shelf life of food, in certain cases they act as indicators of quality food inside the package. Summarily, this present chapter focuses on bio-mediated synthesis of various metal/metal oxide nanoparticles and their applications in food packaging.
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Sharma, Pradeep. "Opportunity of Non-Wood Forest Products in Biocomposites." In Biocomposites [Working Title]. IntechOpen, 2021. http://dx.doi.org/10.5772/intechopen.97825.

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In recent years industries are attempting to decrease their dependency on petroleum-based fuels and products due to increased environmental issues. The tremendous increase in production and use of plastics in every sector of life has led to huge plastic waste disposal problems and also an environmental threat. In order to prevail over the present scenario, the viable and cost-effective approaches are to prepare eco-friendly bio-composites based on non-wood forest products (NWFP), a part of forest wealth of the globe, especially natural fibres, agricultural wastes and extractives. Natural fibres and extractives have many advantages viz. low density, low cost, considerable toughness properties, nontoxicity, sustainability and biodegradability. NWFP based composites may be utilized to produce non-structural parts for diverse applications in various industries as high-performance materials with interesting properties for specific applications viz. furniture, thermal, acoustic insulations and automotive industries etc. In the present chapter, opportunities of extractives, cellulosic and lignocellulosic fibres from non-wood forest products in Bio-composites will be discussed.
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Conference papers on the topic "Radioactive wastes – Thermal properties"

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Pacovsky, Jaroslav, Radek Travnicek, and Radek Vasicek. "Some Results From Geotechnical Research on Bentonite." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1240.

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Abstract A solution of safe isolation of radioactive waste represents a multidisciplinary problem. The waste isolation is to be provided by a multi-barrier system of an underground repository based on a system of several barriers. The system will consist of a container with high level radioactive wastes itself, an engineering barrier — currently intended to be based on ‘bentonites’ — and natural barrier formed with a suitable rock environment. Each of those barriers alone should prevent spreading of hazardous radionuclides from the container to the biosphere. In its main part, this paper deals with laboratory research of some most important geotechnical requirements for the engineering barrier, assumedly based on bentonites materials. The group of tested properties contains: • Hydrophysical properties - permeability, swelling ability, Atterberg’s consistency limits • Physico-technical properties - thermal properties • Rheology Creation of mathematical and physical models forms an independent part of the complex research project for materials of the geotechnical part of the engineering barrier. In the conclusion a short consideration on a prepared physical model of container has been made.
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Kim, In-Tae, Hwan-Seo Park, Yong-Zun Cho, Kwang-Wook Kim, Seong-Won Park, and Eung-Ho Kim. "Characteristics of Solidified Products Containing Radioactive Molten Salt Waste." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7303.

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For a treatment of molten salt wastes generated from a pyroprocessing of oxide spent fuel, we had suggested a stable chemical route, named GRSS (Gel-Route Stabilization & Solidification), and a subsequent consolidation method. By using this method, a series of monolithic wasteforms with different conditions were fabricated, and then their physicochemical properties were investigated. A simulated salt containing 90wt% LiCl, 6.8wt% CsCl, and 3.2wt% SrCl2 was treated with a gel-forming material system, Si/Al/P = 0.4/0.4/0.2 and 0.35/0.35/0.3, and the gel-products were treated at 1100C° after mixing with borosilicate glass powder, where the salt loadings were about 16∼20wt%. The solidified products had a density of 2.3∼2.35g/cm3, a micro-hardness of 4.69∼4.72GPa, a glass transition temperature of 528∼537C°, and a thermal expansion coefficient of 1.65×10−7∼3.38×10−5/C°. Leaching results by the PCT-A method revealed leached rates, 10−3∼10−2g/m2day and 10−4∼10−3g/m2day for Cs and Sr, respectively. From the long-term ISO leaching test, the 900day-leached fraction of Cs and Sr predicted by a semi-empirical model were 0.89% and 0.39%. The leaching behaviors indicated that Cs would be immobilized into a Si-rich phase while Sr would be in a P-rich phase. The experimental results revealed that the GRSS method could be an alternative method for a solidification of radioactive molten salt wastes.
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Kobayashi, Hidekazu, Ippei Amamoto, Takuma Yokozawa, Teruo Yamashita, Takayuki Nagai, Naoto Kitamura, Hiromichi Takebe, Naoki Mitamura, and Tatsuya Tsuzuki. "Applicability of Iron Phosphate Glass Medium for Loading NaCl Originated From Seawater Used for Cooling the Stricken Power Reactors." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96108.

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As the part of investigation for immobilization of the sludge as one of the radioactive wastes arising from the treatment of contaminated water at Fukushima Dai-ichi nuclear power plant, applicability of vitrification method has been evaluated as a candidate technique. The aim of this study is to evaluate the influence of NaCl as one of the main constituents of sludge, on glass formation and glass properties. Two kinds of iron phosphate glass (IPG) media in the xFe2O3-(100-x)P2O5, with x = 30 and 35 (mol%) were chosen and the glass formation, structure and properties including density, coefficient of thermal expansion, glass transition temperature, onset crystallization temperature and chemical durability of NaCl-loaded IPG were studied. The results are summarized as follows. Sodium chloride, NaCl could be loaded into IPG medium as Na2O and Cl contents and their loading ratio could be up to 19 and 15 mol%, respectively. Majority of Cl content of raw material NaCl was thought to be volatilized during glass melting. Loading NaCl into IPG induces to depolymerize glass network of phosphate chains, leads to decrease both glass transition and onset crystallization temperatures, and to increase coefficient of thermal expansion. NaCl-loaded IPG indicated good chemical durability in case of using 35Fe2O3-65P2O5 medium.
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Varlakov, Andrey P., Sergey V. Karlin, Alexandr S. Barinov, Elena V. Zaharova, and Viatcheslav M. Ermolaev. "Study of the Radioactive Silt Sediment Cementation Techniques." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16138.

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Radioactive silt deposits (RSD) of the spent fuel rod cooling pools were used as an object of these studies. In this paper the following techniques were considered for the silt processing: the cementation of silt without a prior treatment, cementation of the dried silt product, cementation of the calcined silt product, and the impregnation of the calcined silt with high penetrating cement grouts. This paper reports the results of the following studies: the chemical and isotope silt composition, physicochemical silt properties, properties of the cement grouts and solidified compounds, obtained as a result of various silt processing techniques. For every processing technique the following cement compound quality index stated in the Russian standard GOST R 51883-2002 was determined: the mechanical strength, freeze-thaw resistance and leach rate of 137Cs. Effects of variations in the thermal silt treatment mode, in the water/cement ratio, and in the binder material type have been determined. Based upon the results of the studies a comparative assessment of the silt cementation techniques has been performed.
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Kozlowska, Anna-Maria, Steve R. Langford, Manjit S. Kahlon, and Haydn G. Williams. "Enhanced Bioremediation as a Cost Effective Approach Following Thermally Enhanced Soil Vapour Extraction for Sites Requiring Remediation of Chlorinated Solvents." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16296.

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Thermally enhanced bioremediation can be a more cost-effective alternative to full scale in-situ thermal treatment especially for sites contaminated with chlorinated solvents, where reductive dechlorination is or might be a dominant biological step. The effect of Thermally Enhanced Soil Vapour Extraction (TESVE) on indigenous microbial communities and the potential for subsequent biological polishing of chlorinated solvents was investigated in field trials at the Western Storage Area (WSA) – RSRL (formerly United Kingdom Atomic Energy Authority - UKAEA) Oxfordshire, UK. The WSA site had been contaminated with various chemicals including mineral oil, chloroform, trichloroethane (TCA), carbon tetrachloride and tetrachloroethene (PCE). The contamination had affected the unsaturated zone, groundwater in the chalk aquifer and was a continuing source of groundwater contamination below the WSA. During TESVE the target treatment zone was heated to above the boiling point of water increasing the degree of volatilization of contaminants of concern (CoC), which were mobilised and extracted in the vapour phase. A significant reduction of concentrations of chlorinated solvent in the unsaturated zone was achieved by the full-scale application of TESVE – In Situ Thermal Desorption (ISTD) technology. The rock mass temperature within target treatment zone remained in the range of 35°–44° C, 6 months after cessation of heating. The concentration of chlorinated ethenes and other CoC were found to be significantly lower adjacent to the thermal treatment area and 1 to 2 orders of magnitude lower within the thermal treatment zone. Samples were collected within and outside the thermal treatment zone using BioTraps® (passive, in-situ microbial samplers) from which the numbers of specific bacteria were measured using quantitative polymerase chain reaction (qPCR) methods of analysis. High populations of reductive dechlorinators such as Dechalococcoides spp. and Dehalobacter spp., were found within the zone that was subjected to thermal remediation and moderate levels of Dehalobacter sp were found outside the treatment area. These results confirm dehalogenating bacteria are present within the site and suggest populations have bounced back following thermal treatment. The thermally treated zone showed a greater number of active indigenous bacteria — indicating that the conditions following TESVE treatment selectively promote the growth of desirable bacteria. This might result from elimination of micro-organisms competing for hydrogen as an electron donor, increased biovailability of CoC or a reduction in its inhibiting properties. This paper aims to show the potential for biologically mediated contaminant reduction in assisting thermal remediation projects. During and post active thermal remediation this approach can help reduce total treatment costs by providing an inexpensive final polishing step or by being a complementary process within the perimeter of heated zone and inside hotspots during the cool-down phase.
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Benay, G., G. Modolo, and R. Odoj. "Synthesis of Yttria-Stabilised Zirconia Matrices for Immobilisation of Actinides by Internal Gelation Method." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7360.

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In the scope of the co-conversion of actinides solutions obtained from partitioning spent nuclear fuel, the internal gelation of ceria-doped yttria-stabilized zirconia was investigated. This dust-free method to fabricate kernels, which can be used as fuel or pressed into pellets, is technically easy to implement and compatible with remote handling. The effects of the quantity of reactants used on the properties of the material were studied. Gels, kernels and pellets were analyzed by thermal analysis, electron microscopy and X-ray diffraction. It was found that the initial broth composition played an important role in the structure of kernels and the formation of cracks during thermal treatment. Pellets obtained with a repressing method were found to present densities up to 86% TD.
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Andersson, Johan, Kristina Skagius, Anders Winberg, Anders Stro¨m, and Tobias Lindborg. "Site Descriptive Modeling as a Part of Site Characterization in Sweden: Concluding the Surface Based Investigations." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7062.

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The Swedish Nuclear Fuel and Waste Management Co., SKB, is currently finalizing its surface based site investigations for the final repository for spent nuclear fuel in the municipalities of O¨sthammar (the Forsmark area) and Oskarshamn (the Simpevar/Laxemar area). The investigation data are assessed into a Site Descriptive Model, constituting a synthesis of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and a surface system description. Site data constitute a wide range of different measurement results. These data both need to be checked for consistency and to be interpreted into a format more amenable for three-dimensional modeling. The three-dimensional modeling (i.e. estimating the distribution of parameter values in space) is made in a sequence where the geometrical framework is taken from the geological models and in turn used by the rock mechanics, thermal and hydrogeological modeling. These disciplines in turn are partly interrelated, and also provide feedback to the geological modeling, especially if the geological description appears unreasonable when assessed together with the other data. Procedures for assessing the uncertainties and the confidence in the modeling have been developed during the course of the site modeling. These assessments also provide key input to the completion of the site investigation program.
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Wileveau, Yannick, Kun Su, and Mehdi Ghoreychi. "A Heating Experiment in the Argillites in the Meuse/Haute-Marne Underground Research Laboratory." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7276.

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A heating experiment named TER is being conducted with the objectives to identify the thermal properties, as well as to enhance the knowledge on THM processes in the Callovo-Oxfordian clay at the Meuse/Haute Marne Underground Research Laboratory (France). The in situ experiment has being switched on from early 2006. The heater, 3 m length, is designed to inject the power in the undisturbed zone at 6 m from the gallery wall. A heater packer is inflated in a metallic tubing. During the experiment, numerous sensors are emplaced in the surrounding rock and are experienced to monitor the evolution in temperature, pore-water pressure and deformation. The models and numerical codes applied should be validated by comparing the modeling results with the measurements. In parallel, some lab testing have been achieved in order to compare the results given with two different scales (cm up to meter scale). In this paper, we present a general description of the TER experiment with installation of the heater equipment and the surrounding instrumentation. Details of the in situ measurements of temperature, pore-pressure and strain evolutions are given for the several heating and cooling phases. The thermal conductivity and some predominant parameters in THM processes (as linear thermal expansion coefficient and permeability) will be discussed.
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Zhou, Wenzhong, and Rong Liu. "Enhanced Thermal Conductivity UO2-BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30647.

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An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. Two fabrication methods to produce high thermal conductivity UO2-BeO oxide nuclear fuels were summarized. These two processing routes generated pellets with two different microstructures. The characteristics and microstructures of the fuel are determined for use in FEM thermal models, and the relevant thermal properties for UO2-BeO fuels by two different fabrication methods were determined. The results showed significant increase in the fuel thermal conductivities. The reactor performance analysis showed that the decrease in centerline temperature was 250–350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors’ performance and safety, and high-level radioactive waste generation.
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Fehrmann, Henning. "Westinghouse Modular Grinding Process: Improvement for Follow on Processes." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96132.

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In nuclear power plants (NPP) ion exchange (IX) resins are used in several systems for water treatment. The resins can be in bead or powdered form. For waste treatment of spent IX resins, two methods are basically used: • Direct immobilization (e.g. with cement, bitumen, polymer or High Integrity Container (HIC)) • Thermal treatment (e.g. drying, oxidation or pyrolysis) Bead resins have some properties (e.g. particle size and density) that can have negative impacts on following waste treatment processes. Negative impacts could be: • Floatation of bead resins in cementation process • Sedimentation in pipeline during transportation • Poor compaction properties for Hot Resin Supercompaction (HRSC) Reducing the particle size of the bead resins can have beneficial effects enhancing further treatment processes and overcoming prior mentioned effects. Westinghouse Electric Company has developed a modular grinding process to crush/grind the bead resins. This modular process is designed for flexible use and enables a selective adjustment of particle size to tailor the grinding system to the customer needs. The system can be equipped with a crusher integrated in the process tank and if necessary a colloid mill. The crusher reduces the bead resins particle size and converts the bead resins to a pump able suspension with lower sedimentation properties. With the colloid mill the resins can be ground to a powder. Compared to existing grinding systems this equipment is designed to minimize radiation exposure of the worker during operation and maintenance. Using the crushed and/or ground bead resins has several beneficial effects like facilitating cementation process and recipe development, enhancing oxidation of resins, improving the Hot Resin Supercompaction volume reduction performance.
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