We are proudly a Ukrainian website. Our country was attacked by Russian Armed Forces on Feb. 24, 2022.
You can support the Ukrainian Army by following the link: https://u24.gov.ua/.
Even the smallest donation is hugely appreciated!
Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями
Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Waste solidification".
Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.
Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.
Svidersky, V., V. Glukhovsky, I. Glukhovsky, and T. Dashkova. "Liquid Radioactive Solidification Technologies." Nuclear and Radiation Safety, no. 1(81) (March 12, 2019): 68–74. http://dx.doi.org/10.32918/nrs.2019.1(81).12.
This review provides a brief analysis of familiar and tested technologies of liquid radioactive waste solidification. The technologies of bituminization, vitrification and incorporation of radioactive waste into the polymer matrix are considered. The paper presents the efficiency indices of the conventional cementation technology and sets forth the results of calculating the cost of components for cementing liquid radioactive waste of various concentrations. Besides, there are results of calculating the volumetric characteristics of cement stone for water-cement relations used for cementing liquid radioactive waste. The review includes the results based on the development and implementation of solidification technologies for liquid radioactive waste using contact-hardening binders that form a durable waterproof stone at the time of pressing and do not require additional water for curing. Generated compounds for immobilization of liquid radioactive waste from nuclear power plants are tested to identify their strength characteristics, resistance to irradiation and leaching parameters. The paper covers the calculation of the cost of components for the solidification of liquid radioactive waste of various concentrations. The developed technology of liquid radioactive waste solidification allows obtaining compounds with strength up to 40 MPa. The volume of the final product is increased by 1.8 times, and the leaching rate is in the range of 1.10×10–4…9.5×10–5 kg/m2 per day.
2
Luhar, Ismail, Salmabanu Luhar, Mohd Mustafa Al Bakri Abdullah, Andrei Victor Sandu, Petrica Vizureanu, Rafiza Abdul Razak, Dumitru Doru Burduhos-Nergis, and Thanongsak Imjai. "Solidification/Stabilization Technology for Radioactive Wastes Using Cement: An Appraisal." Materials 16, no. 3 (January 19, 2023): 954. http://dx.doi.org/10.3390/ma16030954.
Across the world, any activity associated with the nuclear fuel cycle such as nuclear facility operation and decommissioning that produces radioactive materials generates ultramodern civilian radioactive waste, which is quite hazardous to human health and the ecosystem. Therefore, the development of effectual and commanding management is the need of the hour to make certain the sustainability of the nuclear industries. During the management process of waste, its immobilization is one of the key activities conducted with a view to producing a durable waste form which can perform with sustainability for longer time frames. The cementation of radioactive waste is a widespread move towards its encapsulation, solidification, and finally disposal. Conventionally, Portland cement (PC) is expansively employed as an encapsulant material for storage, transportation and, more significantly, as a radiation safeguard to vigorous several radioactive waste streams. Cement solidification/stabilization (S/S) is the most widely employed treatment technique for radioactive wastes due to its superb structural strength and shielding effects. On the other hand, the eye-catching pros of cement such as the higher mechanical strength of the resulting solidified waste form, trouble-free operation and cost-effectiveness have attracted researchers to employ it most commonly for the immobilization of radionuclides. In the interest to boost the solidified waste performances, such as their mechanical properties, durability, and reduction in the leaching of radionuclides, vast attempts have been made in the past to enhance the cementation technology. Additionally, special types of cement were developed based on Portland cement to solidify these perilous radioactive wastes. The present paper reviews not only the solidification/stabilization technology of radioactive wastes using cement but also addresses the challenges that stand in the path of the design of durable cementitious waste forms for these problematical functioning wastes. In addition, the manuscript presents a review of modern cement technologies for the S/S of radioactive waste, taking into consideration the engineering attributes and chemistry of pure cement, cement incorporated with SCM, calcium sulpho–aluminate-based cement, magnesium-based cement, along with their applications in the S/S of hazardous radioactive wastes.
3
Bahadir, Müfit. "Waste solidification and related problems." Toxicological & Environmental Chemistry 20-21, no. 1 (April 1989): 405–9. http://dx.doi.org/10.1080/02772248909357404.
Pinto, C. A., L. T. Hamassaki, F. R. Valenzuela-Diaz, J. Dweck, and P. M. Büchler. "Tannery waste solidification and stabilization." Journal of Thermal Analysis and Calorimetry 77, no. 3 (2004): 777–87. http://dx.doi.org/10.1023/b:jtan.0000041657.06335.54.
Vacenovska, Bozena, Rostislav Drochytka, and Tomas Bina. "The Verification of Usage Possibilities of the Hazardous Waste Solidification Product in the Construction of Road Embankment." Advanced Materials Research 864-867 (December 2013): 1947–53. http://dx.doi.org/10.4028/www.scientific.net/amr.864-867.1947.
This paper presents a fraction of the ongoing research at the Faculty of Civil Engineering Brno University of Technology which is devoted to the verification of the possibility to use solidification products prepared from selected types of hazardous waste in building industry. Presented paper deals with the verification of possibility of its use as a material used in the construction of road embankment. Two types of hazardous waste were chosen - the first of these is an inorganic waste sludge from the wire drawing process (indicated as A) and the second is waste pressed sludge from the neutralization station from tooling (indicated as B).Solidification formulas for these wastes were proposed, then sample specimens were prepared and laboratory tested in accordance to their future use were provided.
7
Shon, Jong-Sik, Hyun-Kyu Lee, Gi-Yong Kim, Tack-Jin Kim, and Byung-Gil Ahn. "Evaluation of Disposal Stability for Cement Solidification of Lime Waste." Materials 15, no. 3 (January 24, 2022): 872. http://dx.doi.org/10.3390/ma15030872.
The Korea Atomic Energy Research Institute (KAERI) obtains UO2 powder using the ammonium uranyl carbonate (AUC) wet process. Hydrated lime (Ca(OH)2) is used to neutralize liquid wastes produced from the AUC process, and the resulting byproduct is known as lime waste. The purpose of this study is to determine optimum operating conditions for cementation of radioactive lime waste produced from the AUC process, and to evaluate the structural stability and leaching stability of cement waste form. The waste acceptance criteria (WAC) of a waste disposal facility in Korea were used to evaluate the cement waste form samples. The maximum lime waste content guaranteeing the shape stability of cement waste form was found to be 80 wt.% or less. Considering the economic feasibility and error of the cementation process, the optimum operating conditions were achieved at a lime waste content of 75 wt.% and a water-to-cement (w/c) ratio of 2.0. The compressive strength of cement waste form samples prepared under optimal operating conditions was 61.4, 76.3, and 61.0 kgf/cm2 after the thermal cycling test, water immersion test, and irradiation, respectively, satisfying the compressive strength of 35.2 kgf/cm2 specified in WAC. A leaching test was performed on the samples, and the leachability indexes (LX) of Cs, Sr, and Co nuclides were 7.63, 8.02, and 10.89, respectively, which are all higher than the acceptance criterion of 6. The results showed that the cement waste forms prepared under optimal operating conditions satisfied the WAC in terms of structural stability and leaching stability. As such, the proposed cement solidification method for lime waste disposal can be effective in solidifying lime waste powder produced during the neutralization of liquid wastes in the AUC process.
8
Jeon, Ji-Hun, Jong-Hwan Lee, Woo-Chun Lee, Sang-Woo Lee, and Soon-Oh Kim. "Solidification of Radioactive Wastes Using Recycled Cement Originating from Decommissioned Nuclear-Energy Facilities." Applied Sciences 14, no. 5 (February 22, 2024): 1781. http://dx.doi.org/10.3390/app14051781.
Hundreds of thousands of tons of waste are generated from decommissioned nuclear- power facilities, and it has become a critical global issue to secure technology for reducing and recycling this waste. Concrete waste (CW) is estimated to comprise 60–80% of the total waste, and concrete-waste powder (CWP) includes enough inorganic substances used as effective materials for waste treatment. Accordingly, it can be used to produce recycled cement (RC). This study aimed to evaluate the performance of a solidification agent manufactured using recycled cement (SRC) for the safe packing of radioactive wastes, such as coarse aggregates of CW, waste soil, and metal wastes originating from decommissioned nuclear facilities. The experimental results indicated that the most relevant incineration temperature of CWP for RC was 700 °C. The optimum water-to-binder ratio was determined to be 0.4, and the most relevant substitution ratio of ground granulated blast furnace slag for CWP was determined to be 15%. In addition, calcium silicate hydrate is the most effective hydration product for improving the compressive strength of SRC. The maximum packing capacities of the SRC for coarse aggregates, waste soil, and metal waste, which were simulated as radioactive wastes, were determined to be 30, 5, and 7 wt%, respectively. The results of leaching tests using SRC containing radioactive wastes contaminated with Co, Cs, and Sr indicated that their leachability indices met the acceptance level for disposal. Consequently, the RC composed of CWP can be used as a solidifying agent to safely dispose of radioactive wastes, such as coarse aggregates, waste soil, and metal waste.
9
Osmanlioglu, Ahmet Erdal. "Utilization of coal fly ash in solidification of liquid radioactive waste from research reactor." Waste Management & Research: The Journal for a Sustainable Circular Economy 32, no. 5 (March 17, 2014): 366–70. http://dx.doi.org/10.1177/0734242x14523664.
In this study, the potential utilization of fly ash was investigated as an additive in solidification process of radioactive waste sludge from research reactor. Coal formations include various percentages of natural radioactive elements; therefore, coal fly ash includes various levels of radioactivity. For this reason, fly ashes have to be evaluated for potential environmental implications in case of further usage in any construction material. But for use in solidification of radioactive sludge, the radiological effects of fly ash are in the range of radioactive waste management limits. The results show that fly ash has a strong fixing capacity for radioactive isotopes. Specimens with addition of 5–15% fly ash to concrete was observed to be sufficient to achieve the target compressive strength of 20 MPa required for near-surface disposal. An optimum mixture comprising 15% fly ash, 35% cement, and 50% radioactive waste sludge could provide the solidification required for long-term storage and disposal. The codisposal of radioactive fly ash with radioactive sludge by solidification decreases the usage of cement in solidification process. By this method, radioactive fly ash can become a valuable additive instead of industrial waste. This study supports the utilization of fly ash in industry and the solidification of radioactive waste in the nuclear industry.
10
Polek, Daria. "Solidification of hazardous waste as a part of the raw material recovery process." E3S Web of Conferences 18 (2017): 01026. http://dx.doi.org/10.1051/e3sconf/20171801026.
Paper presents the process capabilities for solidification hazardous waste. In the first part of the article the authors present general technologies and methods in a comparative model. The following section describes the results of market research for the most advanced and innovative solidification technologies. Comparative analysis of the material has shown and described the three most promising, leading-edge technologies of waste solidification avalible on the Polish market.
Lin, Sheng-Lung. "Effectiveness of sulfur for solidification/stabilization of metal contaminated wastes." Diss., Georgia Institute of Technology, 1995. http://hdl.handle.net/1853/19475.
Asavapisit, Suwimol. "Solidification system for metal containing hazardous wastes." Thesis, Imperial College London, 1998. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.287950.
DELLAMANO, JOSE C. "Uso de microssilica como aditivo na imobilizacao de rejeitos radioativos em cimento." reponame:Repositório Institucional do IPEN, 1995. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10413.
Made available in DSpace on 2014-10-09T12:38:25Z (GMT). No. of bitstreams: 0 Made available in DSpace on 2014-10-09T14:04:47Z (GMT). No. of bitstreams: 1
05833.pdf: 3627328 bytes, checksum: 76369e5662f766257847711bedba7fae (MD5) Dissertacao (Mestrado) IPEN/D Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
4
Montgomery, Diana Margaret. "Organophilic clays in stabilisation and solidification of hazardous wastes." Thesis, Imperial College London, 1989. http://hdl.handle.net/10044/1/47574.
Solidification technology can be an effective process for treating a variety of difficult to manage waste materials containing heavy metals prior to reuse or disposal. There are numerous commercial solidification techniques spanning a spectrum of technical complexity and cost. The most common methods include those based on cement or cement/pozzolanic materials. These materials, which are used in many solidification processes, make the technology appear simple and inexpensive. However, there are significant challenges to the successful application of this technique. The morphology and chemistry of the solidified waste forms are complex, specially when the waste streams used contain components other than the metals that are likely to be effectively immobilised. Also, the selection of the binder, depends upon an understanding of the chemistry of both the contaminants and the binder itself, to ensure efficient and reliable results. Nevertheless,a number of complex interactions are known to cause significant retardation on normal hydraulic reactions of cement-based materials, causing numerous and controversial problems. In recent years there has been renewed interest in elucidating the binding mechanisms responsible for the fixation of waste species. Carbonation, which is known to affect a wide range of cementitious materials, is a phenomenon observed by many scientists and has received very little attention. The aim of this work has been to investigate the effects of natural and accelerated carbonation on the development of mechanical and microstructural properties of solidified products as well as on the binding of metallic waste components. Particular emphasis was paid to examine the influence of different binders on the properties of carbonated solidified waste forms. The kinetics of the carbonation reaction was thoroughly examined, particularly when mix parameters such as binder/waste type and water content were varied. An examination of the resulting products showed that carbonated solidified waste materials had improved mechanical properties and increased metal binding capacity, when compared to specimens cured in nitrogen or normal atmospheric conditions. Microstructural analysis showed that large amounts of calcite where characteristics of carbonated samples. The increased formation of calcite as a result of carbonation appeared to be directly linked with the development of strength and enhanced metals fixation. NMR and FTIR spectroscopy indicated that carbonation has a significant influence on the hydration of waste forms by increasing the degree of polymerisation of the silicate hydration phases, with a consequent acceleration of the hydration of the cement paste. Examination by SEM analysis confirmed an acceleration of C3S hydration, typified by a de-calcified hydration rims and a matrix of dense calcite intergrowth infilling porosity. Some metals appeared to be incorporated in the silica-rich rims and others in the calcite rich matrix, suggesting precipitation of metal as both carbonates, silicates and complex double-salts. An examination of the kinetic of the carbonation reaction revealed that the reactivity of the different cements was different in the presence of carbon dioxide, and that when metal wastes were added the susceptibility of the paste to react with carbon dioxide increased. In general the results of this work indicate the potential of carbon dioxide for incorporation into the treatment of wastes during solidification. However, further work is necessary to establish the long-term performance of these carbonated waste forms as well as the behaviour of carbon dioxide upon different waste streams.
6
Maffettone, Roberta. "Stabilization/solidification processes for the treatment of contaminated soil and waste." Doctoral thesis, Universita degli studi di Salerno, 2015. http://hdl.handle.net/10556/1753.
2013-2014 Recovering industrial waste and contaminated soil is one of the main objectives in environmental management. Nowadays in Italy, landfilling is responsible for up to 40% of total soil contamination and up to 50% of the used remediation techniques involves excavation and disposal. On the other hand, the European Legislation has set key drivers to improve waste management, as setting recycling targets and limiting the use of landfilling with its rising cost. In this scenario, new technologies to reduce the toxicity of contaminated soil and hazardous waste before their disposal or to reuse them as aggregates are of great interest.
Stabilisation/solidification (S/S) is a treatment for wastes and soils which mainly uses cementitious or pozzolanic binders to produce a solid monolith that incorporates the contaminants. This process is particularly effective on heavy-metals contaminated soils. Other additives/fillers can also be used during a pre-treatment phase to amend adverse chemical and physical characteristics, e.g. high moisture content. Alternative methods to treat contaminated waste and soil exploited the application of accelerated carbonation to cement-based S/S. This process can improve the characteristics of the stabilized products in terms of leaching, strengths or pH.
Accelerated carbonation (ACT) is an enhanced form of natural carbonation that has been developed during the last years at industrial scale for the treatment of contaminated soil and industrial wastes. Accelerated carbonation induces a rapid reaction exposing the mineral or the reactive waste to a controlled atmosphere containing CO2 and promotes rapid hardening of the product. The resultant precipitation of calcium carbonate reduces the porosity of the material, and leads to further changes at the microstructure, aiding the retention of contaminants and improving the mechanical properties. The pH is also lowered with the result of reduced solubility of many heavy metals.
Waste can be formed into aggregate by agglomeration. If the two processes are combined, it is feasible to produce hardened aggregate. The final product can be reused as aggregate in engineering fill or in concrete production.
The aim of the research project conducted during the Ph.D. programme is the development of an innovative approach for the enhancing of stabilization/solidification treatment of contaminated soils and wastes. The research aimed at the identification of innovative formulation using cement and thermal wastes for heavy-metals contaminated soil treatment and at the investigation of the effect of the accelerated carbonation applied to cement-based stabilization/solidification.
Tests of cement-based stabilization/solidification using Portland cement and the effect of accelerated carbonation on metals mobility were investigated on artificial heavy-metals contaminated soil at the Sanitary Environmental Engineering Division (SEED) at the University of Salerno. The process was assessed with further investigations on soil washing residues blended with thermal ashes and cement for the production of lightweight recycled aggregate. This part was conducted within the LLP Erasmus Placement Programme at the Centre for Contaminated Land Remediation (CCLR) of the University of Greenwich (UK). The process investigated entailed the mixing of soil washing residues with paper incineration ashes, reactive to carbon dioxide, or sewage sludge ashes followed by accelerated
carbonation to produce the aggregate. Portland cement was used as the binder, which also has an ability to combine with CO2.
The effect of accelerated carbonation on the cemented contaminated soil was evaluated by mineralogical and structural properties. Chemical stability was measured by leaching of heavy metals from the raw materials and the final products. The aggregates produced showed comparable strength to commercially lightweight aggregates. Accelerated carbonation increased the strength and the density of the aggregate compared to the hydrated one. Heavy metals leaching were substantially unaffected by carbonation, apart for copper and barium. Further investigation tested the aggregates for using in lightweight concrete block and for green roofing. The use of a synthetic CO2 flue gas lead to a capture of the carbon dioxide leading to a “low carbon” product. The study showed the applicability of the process for manufacturing lightweight aggregates from soil washing residues and ashes by enhanced cement based S/S as a good alternative for a wide range of civil engineering applications. The effect of accelerated carbonation has to be further explained. Future investigations are needed to enhance the process based on the variability of the wastes. Other waste and alternative carbon dioxide reactive fillers can be considered to be treated by the process. [edited by author] XIII n.s.
7
Moore, Tiffany Len. "Treatment of inorganic hazardous waste constituents found in electric arc furnace dust by solidification/stabilization." Thesis, Virginia Tech, 1991. http://hdl.handle.net/10919/41698.
In this study, solidification and stabilization processes were evaluated for use as a treatment method for electric arc furnace dust. Specific objectives were (1) to develop a solidified material capable of meeting EPA requirements for heavy metal leaching, and (2) to develop a solidified material that could be used for construction.
Results from the studies of the untreated electric arc furnace dust showed that the solubility of cadmium is controlled by the hydroxide species. Lead solubility is more complex because its solubility is controlled by a species other than hydroxide and therefore it is more difficult to predict. Studies also indicated that approximately 1.9% of the composition of the electric arc Furnace dust is made up of lead.
This study demonstrated that solidification and. stabilization is a viable treatment process for electric arc. furnace dust. Success in treating the electric arc furnace dust by this method, however, depends upon such factors as the compressive strength of the solidified waste, the amount of electric arc furnace dust incorporated in the concrete, and the ability of the solidified waste to remain intact during the Toxicity Characteristic Leaching Procedure (TCLP). Based on these factors, approximately 165 lb dust/cu yd concrete was determined to be the upper limit on the amount of electric arc furnace dust that can be incorporated in such a system. Efforts to improve the quality of the concrete by the addition of a chelating agent was moderately successful; however, the addition of salts to speed the concrete set times was not successful.
A model was developed which predicts the required compressive strength of the solidified dust based upon the amount of electric arc furnace dust that is incorporated in the concrete. The model effectively predicts, without performing the TCLP test, whether the solidified material will meet limits for heavy metal required by the EPA. Master of Science
8
Lampris, Christos. "Solidification/stabilisation of air pollution control residues from municipal solid waste incineration." Thesis, Imperial College London, 2013. http://hdl.handle.net/10044/1/18973.
Air pollution control (APC) residues are by-products of the flue gas cleaning process in energy-from-waste (EfW) plants treating municipal solid waste. They are classified as a hazardous waste in the EU Waste Catalogue and are a priority hazardous waste stream in the UK due to high alkalinity, concentrations of volatile heavy metals and soluble salts. Plans currently exist to increase the number of EfW plants in the UK, with the potential to increase future arisings of APC residues. Stabilisation/solidification (S/S) is an inexpensive treatment technology, involving mixing of the waste with cementitious binders. The main objective of this research is to assess the effectiveness of CEM I and ground granulated blast furnace slag (GGBS) as S/S binders for the treatment of APC residues. The ultimate goal is to expand existing knowledge on S/S systems and assist development of more sustainable treatment methods for APC residues. S/S APC residue specimens were prepared varying the waste-to-binder and water-to-solids ratios and subsequently tested for physical properties and contaminant leaching according to international standards. Geochemical modelling was used to assess contaminant release-controlling processes and contribute to more efficient mix and treatment design. Results from this study indicate that mechanical properties of 50 wt.% CEM I and GGBS mixes exceed UK landfill disposal criteria (1.0 MPa), achieving unconfined compressive strength (UCS) values of up to 21 MPa. CEM I mixes with 10 and 20 wt.% binder addition also met the criterion of 1.0 MPa, achieving UCS values of up to 10 MPa. In contrast, 10 and 20 wt.% GGBS mixes exhibited inferior mechanical properties (UCS < 1.0 MPa). S/S is hampered predominantly by high concentrations of chloride in APC residues. All monolithic S/S samples exceeded relevant UK waste acceptance criteria (monWAC) for chloride (20,000 mg/m2) within the first two days of the 64-day monolithic leaching test. Altough partial immobilisation occurs through the formation of chloro-complexes, S/S of APC residues would require binder additions greater than 50 wt.% to meet UK requirements for landfill disposal. Leaching of Pb also becomes problematic for mixes with 10 and 20 wt.% binder addition, exceeding UK monWAC (20 mg/m2). Nevetheless, the amphoteric nature of heavy metals and the high solubility of chloride salts could favour extraction of potentially valuable elements through washing procedures. Modelling results indicate that a simple washing step may be able to extract 650 mg of Pb and 120 mg of Zn per kg of APC residues treated, while removing approximately 90% of available chloride.
9
Lu, Chen-Hong. "Evaluation of oil and freeze-thaw effects on cement hydration for waste solidification." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1997. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape11/PQDD_0003/MQ44210.pdf.
Hossein, Mohsen. "Role of ettringite formation in the stabilization/solidification of sulphide-bearing mine waste." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 2000. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape4/PQDD_0030/NQ64573.pdf.
U.S. Nuclear Regulatory Commission. Division of Fuel Cycle Safety and Safeguards. and Center for Nuclear Waste Regulatory Analyses (Southwest Research Institute), eds. Survey of waste solidification process technologies. Washington, DC: Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 2001.
Cullinane, M. John. Handbook for stabilization/solidification of hazardous waste. Cincinnati, Ohio: Hazardous Waste Engineering Research Laboratory, Office of Research and Development, U.S. Environmental Protection Agency, 1986.
Cullinane, M. John. Handbook for stabilization/solidification of hazardous waste. Cincinnati, Ohio: Hazardous Waste Engineering Research Laboratory, Office of Research and Development, U.S. Environmental Protection Agency, 1986.
Cullinane, M. John. Handbook for stabilization/solidification of hazardous waste. Cincinnati, Ohio: Hazardous Waste Engineering Research Laboratory, Office of Research and Development, U.S. Environmental Protection Agency, 1986.
Donald, Ian W. Waste immobilization in glass and ceramic based hosts: Radioactive, toxic, and hazardous wastes. Chichester, West Sussex, U.K: Wiley, 2010.
Donald, Ian W. Waste immobilization in glass and ceramic based hosts: Radioactive, toxic, and hazardous wastes. Chichester, West Sussex, U.K: Wiley, 2010.
Dutré, Veronika, and Carlo Vandecasteele. "Solidification/Stabilisation of Hazardous Waste Containing Arsenic." In Chemistry for the Protection of the Environment 3, 199–203. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4757-9664-3_24.
Gliniak, Maciej, Anna Lis, Anna Łoś, Dariusz Mikołajek, and Ziemowit Kapłański. "Hazardous Waste Solidification from Chemical Technological Process." In Springer Proceedings in Energy, 727–34. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-13888-2_70.
Sri Bala Kameswari, K., Pendem Rohit Babu, B. Lekshmi, and Chitra Kalyanaraman. "Solidification and Stabilization of Tannery Sludge." In Recycling of Solid Waste for Biofuels and Bio-chemicals, 381–98. Singapore: Springer Singapore, 2016. http://dx.doi.org/10.1007/978-981-10-0150-5_14.
Cozzi, A. D., and C. A. Langton. "Waste form Development for the Solidification of PDCF/MOX Liquid Waste Streams." In Ceramic Transactions Series, 233–41. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118408438.ch23.
Cau-dit-Coumes, C. "Alternative Binders to Ordinary Portland Cement for Radwaste Solidification and Stabilization." In Cement-Based Materials for Nuclear Waste Storage, 171–91. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-3445-0_16.
Wang, Guiwei, Hui Xu, Xiaoqing Ding, Yanxu Gao, Ping Chen, and Xiufang Hu. "Microbial Induced Solidification of Municipal Solid Waste Incineration Fly Ash." In Proceedings of the 8th International Congress on Environmental Geotechnics Volume 3, 363–68. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-13-2227-3_45.
Yanagisawa, Kazumichi, Mamoru Nishioka, and Nakamichi Yamasaki. "Hydrothermal Treatment of Radioactive Waste: Solidification of High-Level Radioactive Waste by Hydrothermal Hot-Pressing." In Transactions of the Materials Research Society of Japan, 407–32. Dordrecht: Springer Netherlands, 1990. http://dx.doi.org/10.1007/978-94-009-0789-8_31.
Schifano, V., and F. Lilley. "Solidification/Stabilization Remediation of Acid Organic Waste for Impoundment Units Closure." In Environmental Science and Engineering, 691–99. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-13-2221-1_77.
Bao, Yun, and Michael W. Grutzeck. "Solidification of Sodium Bearing Waste Using Hydroceramic and Portland Cement Binders." In Ceramic Transactions Series, 243–52. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118408438.ch24.
Santos, D. I., P. C. Santos Ventura, and M. A. Aegerter. "Porous Glass Matrix for Nuclear Waste Storage Part II: Solidification, Characterization and Leaching." In Glass … Current Issues, 698. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5107-5_72.
Тези доповідей конференцій з теми "Waste solidification":
1
Stegemann, J. A., and Q. Zhou. "Development of process envelopes for cement-based stabilisation/solidification of metal treatment filtercakes." In WASTE MANAGEMENT 2008. Southampton, UK: WIT Press, 2008. http://dx.doi.org/10.2495/wm080031.
Wang, Yaguang, Jinsong Zhang, Yunming Chen, Bing Li, and Qi Cao. "The Study on High Efficiency Solidification Technology of Radioactive Liquid Waste Containing Boron." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67665.
The technology of radioactive liquid wastes containing boron is a hot spot of radioactive waste disposal. The radioactive borate waste is solidified by conventional cement solidification in our country. In order to dispose the radioactive boron-containing waste more securely and efficiently, this work focuses on the development of high-efficiency cement solidification. In this work, the borate in radioactive liquid wastes containing boron is changed into polyborate and solidified by high efficiency formula to increase the waste containing rate. The high efficiency cement solidification formula was gotten in lab, its indicators are as follows: The containment of boron is 49.5%;The fluidity is 375mm;The compressive strength is 22MPa;The resistance of leachability (Sr, Cs,Co) is better than the requirement of national standard.
3
Lee, Si Y. "Heat Transfer Analysis for Nuclear Waste Solidification Container." In ASME 2009 International Mechanical Engineering Congress and Exposition. ASMEDC, 2009. http://dx.doi.org/10.1115/imece2009-10241.
The Nuclear Nonproliferation Programs Design Authority is in the design stage of the Waste Solidification Building (WSB) for the treatment and solidification of the radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility (PDCF) and Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The waste streams will be mixed with a cementitious dry mix in a 55-gallon waste container. Savannah River National Laboratory (SRNL) has been performing the testing and evaluations to support technical decisions for the WSB. Engineering Modeling & Simulation Group was requested to evaluate the thermal performance of the 55-gallon drum containing hydration heat source associated with the current baseline cement waste form. A transient axi-symmetric heat transfer model for the drum partially filled with waste form cement has been developed and heat transfer calculations performed for the baseline design configurations. For this case, 65 percent of the drum volume was assumed to be filled with the waste form, which has transient hydration heat source, as one of the baseline conditions. A series of modeling calculations has been performed using a computational heat transfer approach. The baseline modeling results show that the time to reach the maximum temperature of the 65 percent filled drum is about 32 hours when a 43°C initial cement temperature is assumed to be cooled by natural convection with 27°C external air. In addition, the results computed by the present model were compared with analytical solutions. The modeling results will be benchmarked against the prototypic test results. The verified model will be used for the evaluation of the thermal performance for the WSB drum. Detailed results and the cases considered in the calculations will be discussed here.
4
Porter, Jim. "Experience in Operating Mobile Solidification Plant for BNFL Environmental Services." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4578.
UK power stations have generated wet radioactive wastes, principally from operation of treatment plants for cooling pond water and liquid effluents. These include ion exchange resins, filter backwash sludges, flocs, pond sludges, filter aids, and miscellaneous oily sludges. To treat these wastes, it was concluded that mobile plants offered significant benefits compared with the alternative of constructing fixed installations. NSG Environmental Ltd designed and built a Mobile LLW Solidification Plant, which we have operated on behalf of BNFL Environmental Services and its predecessors for over twelve years. Since commencing active operations in 1991 the plant has successfully performed 28 campaigns on 13 nuclearlicensed sites. A total of nearly 3,000 drums of active waste have been processed during those campaigns. There have been no failures to solidify wastes, no excessive doses to operators and no transport incidents.
5
Sun, Qina, Junfeng Li, Jianlong Wang, Shixi Ouyang, Qiang Li, and Minghui Wu. "Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive Borate Liquid Waste." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30154.
To investigate the solidification efficiency of sulfoaluminate cement (SAC) and to provide more information for formula optimization, SAC blending zeolite, accelerator and Dura fiber was used as matrix materials for solidification of simulated radioactive borate liquid waste. The simulated radioactive borate liquid waste was prepared with boric acid and sodium hydroxide using drinking water. The performances of solidified waste forms were evaluated mainly basing on matrix compressive strength and leachability. The 28d compressive strength of the solidified waste forms were tested according to Chinese National Standard GB 14569.1-1993, and experiments on water/freezing/irradiation/impact resistance were also carried out. Nuclides Sr, Cs and Co were substituted by their non-radioactive isotopes respectively in leachability test, and the testing procedures were consistent with Chinese National Standard GB 7023-1986. Experimental results showed that it was feasible to solidify borated liquid wastes with SAC. The 28d compressive strength was 13.9MPa, nearly twice of the standard in GB 14569.1-1993. Strength losses in water/freezing/irradiation/impact resistance tests met the demands of GB 14569.1-1993 well. In the leaching test, the 42d leaching rates were 3.39×10−5 cm/d, 4.45×10−5 cm/d and 4.07×10−7 cm/d for Sr2+, Cs+ and Co2+ respectively, much lower than GB 14569.1-1993 limits. Results of leaching test also showed that the leaching mechanism of Co2+ was different from that of Sr2+ and Cs+.
6
Hassan Bek, Muna, and Laila Ben Giuma. "Solidification/Stabilisation of Drilling Waste Using Portland Cement and GBFS." In 14th Mediterranean Congress of Chemical Engineering (MeCCE14). Grupo Pacífico, 2020. http://dx.doi.org/10.48158/mecce-14.dg.09.04.
Katagiri, Gen-ichi, Morio Fujisawa, Kazuya Sano, and Norikazu Higashiura. "Study of LPOP Residue on Resin Mineralization and Solidification." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40112.
Fuji Electric had developed the low pressure oxygen plasma technology for mild decomposition and mineralization of an organic material such as ion exchange resin. This method is suitable for radioactive spent resin volume/weight reduction and stabilization for final disposal. On this process, the ion-exchange resins are vaporized and decomposed into gas-phase with pyrolysis, and then, they are decomposed and oxidized with low-pressure plasma activity based on oxygen. And this process is achieved under moderate condition for radio active waste. • incinerate temperature: 400–700 deg C; • low-pressure (low-temperature) plasma condition: 10–50 Pa. From the result of this process, named of LPOP(low pressure oxidation process) by the inductively coupled plasma, we have confirmed that the process is applicable for organic fireproof waste including ion-exchange resin, and found that the used resin treatment performance is the same as cold test (using imitate spent resin) [1] [2] [3]. In this paper, the outline of the LPOP technology, and two research results on the possibility of solidification with cement of LPOP residue for geological disposes are reported. (1)Study of the residue chemical form after LPOP process (2)Study of the solidification character with cement.
8
Wu, Minghui, Qiang Li, and Shixi Ouyang. "The Application of Uniform Design Table in Cement Solidification of Nuclear Waste Resin." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30164.
As a lower cost raw material, few demand for equipments, convenient solidification process, cement solidification for radioactive waste is widely used for several decades. Formulations of solidification are complex and diverse, involving various types of substrate and additives. Traditional approach for formulation design is single-factor test whose representation is inadequate and workload is huge. Uniform design based on the theory of Quasi-Monte-Carlo takes advantage of limited and representative tests instead of the system. In the multi-factor formulation design, it can be very quick and convenient to find the formulations required by uniform design table and direct-vision method. This article introduced the application of uniform design table for formulation in cement solidification of nuclear waste resin.
9
Abramenkova, G., A. Abramenkovs, and M. Klavins. "Optimization of Radioactive Waste Cementation for Decommissioning of Salaspils Research Reactor." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59066.
This paper deals with information on the radioactive waste cementation technology for decommissioning of Salaspils Research Reactor (SRR). Dismantled and segmented radioactive materials were cemented in concrete containers using tritiated water-cement mixture. The viscosity of water-cement mortar, mechanical tests of solidified mortar’s samples, change of temperature of the samples during solidification time and long time leakage of 137Cs, 14C, 60Co and 3T radionuclides was studied for different water-cement compositions with additives. The pH and electro conductivity of the solutions during leakage tests were controlled. It was shown, that water/cement ratio significantly influences on water-cement mortar’s viscosity and solidified samples mechanical stability. The role of additives — fly ash and Penetron admix in reduction of solidification temperature is discussed. It was found, that addition of fly ash to the cement-water mortar can reduce the solidification temperature from 81°C up to 62°C. The optimal interval of water ratio in cement mortar is discussed. Radionuclides leakage tests show that the release curves has a complicate structure. The possible radionuclides release mechanisms are discussed. Experimental results indicated that additives can significantly influence on the radionuclides release processes from cemented samples. The optimization of cementation of radioactive wastes in concrete containers was performed using mechanical stability, solidification temperature, radionuclide releases and viscosity of mortar.
10
Zhang, Chunlei, Wei Jin, and Zhongmin Zhang. "Notice of Retraction: Solidification Treatment of Dredged Waste for Planting Use." In 2011 5th International Conference on Bioinformatics and Biomedical Engineering. IEEE, 2011. http://dx.doi.org/10.1109/icbbe.2011.5781469.
Langton, C. A. PUREX Organic Waste Solidification. Office of Scientific and Technical Information (OSTI), December 2002. http://dx.doi.org/10.2172/805854.
Langton, C. A. Aqueous Zinc Bromide Waste Solidification. Office of Scientific and Technical Information (OSTI), July 2002. http://dx.doi.org/10.2172/799460.
Del Cul, G., W. Bostick, R. Adamski, W. Slover, P. Osborne, R. Fellows, and T. White. Solidification of waste sludges using microwave heating. Office of Scientific and Technical Information (OSTI), May 1994. http://dx.doi.org/10.2172/10147043.
Dixon, D., R. Erle, and V. Eschen. Microwave solidification development for Rocky Flats waste. Office of Scientific and Technical Information (OSTI), April 1994. http://dx.doi.org/10.2172/120869.
Hansen, E., T. Timothy Jones, T. Tommy Edwards, and A. Alex Cozzi. WASTE SOLIDIFICATION BUILDING BENCH SCALE HIGH ACTIVITY WASTE SIMULANT VARIABILITY STUDY FY2008. Office of Scientific and Technical Information (OSTI), March 2009. http://dx.doi.org/10.2172/952437.
LAWRENCE, OJI. Solidification of SRNL High Activity Drain Waste Feasibility Study. Office of Scientific and Technical Information (OSTI), October 2004. http://dx.doi.org/10.2172/838798.
Taylor, Paul. SOLIDIFICATION OF REDC ORGANICS FOR DISPOSAL AS SOLID WASTE. Office of Scientific and Technical Information (OSTI), November 2023. http://dx.doi.org/10.2172/2205428.
Clark, Sandra, Talya Greathouse, and Jeffrey Means. Review of Literature on Waste Solidification/Stabilization with Emphasis on Metal-Bearing Wastes. Fort Belvoir, VA: Defense Technical Information Center, August 1989. http://dx.doi.org/10.21236/ada213133.
McConnell, J. W. Jr. Portland cement: A solidification agent for low-level radioactive waste. Office of Scientific and Technical Information (OSTI), October 1991. http://dx.doi.org/10.2172/183882.
Singh, Dileep, and Cinta Lorenzo-Martin. Stabilization and Solidification of Nitric Acid Effluent Waste at Y-12. Office of Scientific and Technical Information (OSTI), December 2016. http://dx.doi.org/10.2172/1346558.
