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Relevant bibliographies by topics / Nuclear waste

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Academic literature on the topic 'Nuclear waste'

Author: Grafiati

Published: 4 June 2021

Last updated: 22 June 2024

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Journal articles on the topic "Nuclear waste"

1

Rosa, E. A., S. P. Tuler, B. Fischhoff, T. Webler, S. M. Friedman, R. E. Sclove, K. Shrader-Frechette, et al. "Nuclear Waste: Knowledge Waste?" Science 329, no. 5993 (August 12, 2010): 762–63. http://dx.doi.org/10.1126/science.1193205.

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Anderson, Kent. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 708. http://dx.doi.org/10.1126/science.233.4765.708.a.

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Vernier, P. Thomas. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.c.

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Weinberg, Alvin M. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.b.

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Palmer, Ronald A. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.d.

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Wilson, Paul. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707–8. http://dx.doi.org/10.1126/science.233.4765.707.e.

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Utter, Donald F. "Nuclear Waste." Science 233, no. 4765 (August 15, 1986): 707. http://dx.doi.org/10.1126/science.233.4765.707.a.

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Janata, Jiri, and Roy E. Gephart. "Nuclear Waste." Electrochemical Society Interface 4, no. 4 (December 1, 1995): 46–50. http://dx.doi.org/10.1149/2.f08954if.

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JOHNSON, JEFF. "NUCLEAR WASTE." Chemical & Engineering News Archive 82, no. 29 (July 19, 2004): 5. http://dx.doi.org/10.1021/cen-v082n029.p005.

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Driscoll, Harry. "Nuclear waste." New Scientist 197, no. 2642 (February 2008): 24–25. http://dx.doi.org/10.1016/s0262-4079(08)60340-1.

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Dissertations / Theses on the topic "Nuclear waste"

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Hoffman, Edward Albert. "Neutron transmutation of nuclear waste." Diss., Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/16700.

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Curtis, Deborah Claire. "Advancements in nuclear waste assay." Thesis, University of Birmingham, 2008. http://etheses.bham.ac.uk//id/eprint/153/.

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The research described in this thesis is directed at advancing the state of the practice of the non-destructive gamma-ray assay of nuclear waste containers. A number of potentially accuracy-limiting issues were identified and addressed, resulting in new developments which were implemented on an instrument prior to entering it into service. A set of Pu reference sources used for experimental data have been studied to determine the internal composition (density and fill height) of the sources to assist with validation of a point kernel model. This model has been used to observe the behaviour of gamma-rays in lumps of fissile material from plutonium over the mass range 0.001g to 350g, for a number of densities corresponding to Pu, PuO\(_2\) and PuF\(_3\). Established lump corrections have been analysed and have been found to produce large over- and under-corrected results for the range of masses. Due to the inadequacies of current techniques, a new Pu self-absorption correction method has been developed using the data from numerical simulations, allowing nature to reveal the correlations rather than traditional approaches based upon approximate models. For a 25g 1cm-high Pu flat-plate of density 15g.cm\(^{-3}\), the developed Pu correction produces a result of (24.9 ± 8.8)g compared to (19.5 ± 0.9)g for the Fleissner 2-line method, and (14.7 ± 0.4)g for the Infinite Energy Extrapolation method. The developed Pu correction method has been extended to the application of uranium lumps in waste matrices, provided the enrichment of the sample is known or may be determined via sophisticated isotopic analysis methods such as MGAU or FRAM. The U self-absorption correction method has been found to produce results within 30% of the true mass of the sample for the lumps studied. An analysis of ‘real drum’ effects has been performed, including the revisiting of the Total Measurement Uncertainty (incorporating the uncertainty components of the new Pu and U self-absorption corrections) and results from known sources placed in artificial inhomogeneous waste matrices assayed inside a Canberra Auto Q2 system.

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Kazi-tani, Zakaria, and Alvarez André Ramirez. "Optimizing the Nuclear Waste Fund's Profit." Thesis, Stockholms universitet, Företagsekonomiska institutionen, 2018. http://urn.kb.se/resolve?urn=urn:nbn:se:su:diva-163865.

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The Nuclear Waste Fund constitutes a financial system that finances future costs of the management of spent nuclear fuel as well as decommissioning of nuclear power plants. The fund invests its capital under strict rules which are stipulated in the investment policy established by the board. The policy stipulates that the fund can only invest according to certain allocation limits, and restricts it to invest solely in nominal and inflation-linked bonds issued by the Swedish state as well as treasury securities. A norm portfolio is built to compare the performance of the NWF’s investments. On average, the NWF has outperformed the norm portfolio on recent years, but it may not always have been optimal. Recent studies suggest that allocation limits should be revised over time as the return and risk parameters may change over time. This study focused on simulating three different portfolios where the allocation limits and investment options were extended to see if these extensions would outperform the norm portfolio while maintaining a set risk limit. Portfolio A consisted of OMRX REAL and OMRX TBOND indexes, Portfolio B consisted of OMRX REAL, OMRX TBOND and S&P Sweden 1+ Year Investment Grade Corporate Bond Indexes, and Portfolio C consisted of OMXR REAL, OMRX TBOND and OMXSPI indexes. The return of each portfolio for different weight distributions of the assets were simulated in MATLAB, and polynomial regression models were built in order to optimize the return as a function of the assets’ weights using a Lagrange Multiplier approach for each portfolio. The results depicted that the maximal returns of Portfolios A, B and C were 4.00%, 4.13% and 7.93% respectively, outperforming the norm portfolio’s average return of 3.69% over the time period 2009-2016.

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Cabeche, Dion Tunick. "Water borne transport of high level nuclear waste in very deep borehole disposal of high level nuclear waste." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76933.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.
Cataloged from PDF version of thesis.
Includes bibliographical references (p. 52).
The purpose of this report is to examine the feasibility of the very deep borehole experiment and to determine if it is a reasonable method of storing high level nuclear waste for an extended period of time. The objective of this thesis is to determine the escape mechanisms of radionuclides and to determine if naturally occurring salinity gradients could counteract this phenomenon. Because of the large dependence on the water density, the relationship between water density and the salinity was measured and agreed with the literature values with a less than 1% difference. The resultant relationship between the density and salinity is a linear relationship with the molality, and dependent upon the number of ions of the dissolved salt (e.g. CaCl₂ contains 3 and NaCl has 2). From the data, it was calculated that within a borehole with a host rock porosity of 10-⁵ Darcy, it would take approximately 10⁵ years for the radionuclides to escape. As the rock porosity decreases, the escape time scale increases, and the escape fraction decreases exponentially. Due to the conservative nature of the calculations, the actual escape timescale would be closer to 106 years and dominated by 1-129 in a reducing atmosphere. The expected borehole salinity values can offset the buoyancy effect due to a 50°C temperature increase.
by Dion Tunick Cabeche.
S.B.

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Short, Rick. "Incorporation of molybdenum in nuclear waste glasses." Thesis, University of Sheffield, 2004. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.444469.

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Pelendritis, Michalis. "Nuclear fuel waste extraction : third phase revisited." Thesis, University of Manchester, 2017. https://www.research.manchester.ac.uk/portal/en/theses/nuclear-fuel-waste-extraction-third-phase-revisited(55e7be69-dd39-49ec-97bc-fb7b7828c70e).html.

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The problem of third phase formation plays a key role in the plutonium and uranium extraction process (PUREX). This process is responsible for the recycling of used nuclear fuel in order to save fuel usage and more importantly to reduce the amount of waste created (and afterwards disposed or stored) after the end of a nuclear fuel cycle. Understanding the role and behaviour of its components in the aqueous and organic phase, and more in depth on the process' extractant tributyl phosphate (TBP), will help give a better understanding of what causes the phase separation of the organic phase and the interactions occuring at that interface. The focus of this project is on the mean activity coefficients of aqueous uranyl nitrate (and other salts) under varying concentrations using the Statistical Associating Fluid Theory (SAFT). Also, apart from the thermodynamic aspect of the above, molecular dynamic simulations were performed on tributyl phosphate and its interactions with other third phase components to study the effects on the structure and behaviour of TBP. By studying TBP in dodecane mixtures it was found that TBP forms aggregates and filament structuring throughout the organic diluent at most TBP concentrations. Also nitric acid hinders this formation by contacting the polar group (P=O) of TBP via intermolecular forces; its action is physical (based on intermolecular interactions) as opposed to chemical. It is expected that this structuring of TBP in the organic phase has an important effect in the transport of metal nitrates from the aqueous to the organic phase in the PUREX process.

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Lee, S. (Sanyung). "Monumental Museum for Onkalo nuclear waste repository." Master's thesis, University of Oulu, 2018. http://jultika.oulu.fi/Record/nbnfioulu-201805312047.

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Abstract. Contemporary civilization needs diverse resources to maintain its form, such as agriculture, knowledge, engineering, infrastructure, and energy, of course. In terms of the energy, the nuclear power is the thickest column to support our present civilization. However, sometimes the bigger advantage you get means the bigger responsibility you embrace. The powerful source of energy, nuclear power causes the crucial side effect behind which is tons of nuclear wastes, which is highly radioactive. Fortunately, many countries which own nuclear power plants are already working on this issue but still, most countries have no specific back-up plan how to deal with these critical but inevitable burdens. Finland is the fore-runner in this field and the Onkalo nuclear waste repository is one of a kind in this important subject. Still, the Onkalo is in the middle of research and engineering level right now, but it will be face the cultural and architectural questions for the Onkalo soon. As an echo of this subject the Onkalo will face, I propose the public facility to fulfill the additional needs and purposes of the Onkalo. OMM-Onkalo Monumental Museum which I am proposing will be the one of options for these demands. It can be a museum to memorize the place, the facility to maintain the place, the shelter to protect the place, and the hub to connect present to future.

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Künzel, Carsten. "Metakaolin based geopolymers to encapsulate nuclear waste." Thesis, Imperial College London, 2013. http://hdl.handle.net/10044/1/11172.

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This thesis investigates the potential use of geopolymers to encapsulate intermediate level waste (ILW), particularly Magnox swarf contaminated with Al metal and Cs/Sr-loaded clinoptilolite. Both wastes have different interactions with the encapsulation matrix. For Magnox swarf waste containing trace Al metal, the pH of the encapsulating matrix is a key factor that controls corrosion and release of hydrogen. Cs and Sr can leach from contaminated clinoptilolite into the encapsulating geopolymer and therefore the chemical interactions of these ions with the matrix have been investigated. A fundamental understanding of the geopolymer system used for encapsulation was developed. This involved investigating the influence of different precursor on the mechanical properties. It was shown showed that metakaolin based geopolymers are unstable at room temperature when in contact with an atmosphere with a low relative humidity and excessive drying shrinkage occurs. This shrinkage can be reduced by adding inert fillers which have low impact on the mortar viscosity and mechanical strength. Magnox waste and Al-metal have been encapsulated in metakaolin based geopolymers and surface interactions studied using SEM-EDX and XRD. In addition the corrosion rates were determined. Magnox swarf does not react with the geopolymers matrix, while Al-metal rapidly corrodes. However, by using a metakaolin with a low molar Si:Al ratio and controlling the molar Al:Na ratio in geopolymers the corrosion can be significantly reduced and allows encapsulation of this difficult waste stream. Surface reactions of Cs/Sr-contaminated clinoptilolite and geopolymers were also studied. Simulated wastes containing Cs+ and Sr2+ salts were mixed with geopolymers and the influence of the cations on the geopolymer microstructure and leaching were investigated. Mixing Cs/Sr-contaminated clinoptilolite with activation solution causes surface dissolution of clinoptilolite with release of Cs and Sr ions into the matrix. Leaching of Cs contaminated geopolymers showed that Cs+ ions can be immobilised at concentrations up to 10 wt%. Sr2+ reacts with the activating solution and dissolved metakaolin and is build chemically into the structure. The research has resulted in a number of key conclusions related to the stability of metakaolin derived geopolymers and their interactions with the selected wastes.

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Paul, Neepa. "Characterisation of highly active nuclear waste simulants." Thesis, University of Leeds, 2014. http://etheses.whiterose.ac.uk/8586/.

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Nuclear power is a non-carbon emitting energy resource generating 18% of electricity to the UK. As with any type of industrial process the waste management strategy is an important step to define considering the environmental, economic and political factors. However, the nuclear industry faces ongoing challenges to underpin a well-defined waste treatment strategy due to the high heat load and the radioactive nature of the products produced. Reprocessing of spent nuclear fuel produces a highly active liquor (HAL) waste stream. HAL is currently stored in a number of highly active storage tanks (HASTs). Within the HASTs, solid materials are known to have precipitated from the HAL over time. Particle simulants provide a route for understanding the physical behaviour, it is the synthesis of the particle simulants and the characterisation of these solid-liquid systems that are the interest of this study. An understanding of the HAL waste properties is required for its safe transport, storage and eventual disposal of the HASTs are to be safely emptied and decommissioned. Collaboration with the National Nuclear Laboratory (NNL), at Sellafield UK, provided the opportunity to manufacture the HAL simulants, caesium phosphomolybdate (CPM) and zirconium molybdate (ZM), on larger scale. Manipulation of the aspect ratio of ZM particles is also investigated. The initial step of the synthesis produces spherical CPM which leads to the production of cubic ZM, the final step requires the addition of an organic additive, citric acid, where cuboidal zirconium citratomolybdate (ZMCA) is formed. Molecular modelling analysis revealed growth inhibition of the {2 0 0}, {-2 0 0}, {0 2 0} and {0 -2 0} faces, due to greater number of Zr sites for citratomolybdate complex affiliation. Distinct particle properties are established for CPM, ZM and ZMCA and compared to a common oxide particle material titanium dioxide (TiO2). The results of this study highlight the influence of key aspects of the HAL particulates, such as size and shape, on relevant solid-liquid properties such as sedimentation and rheology. The influence of bulk liquid properties such as electrolyte concentration and pH were also investigated. Sedimentation behaviour was characterised by fitting the experimental data to the Richardson-Zaki model, yielding a fitting parameter n (cognate to particle size and shape) and thus demonstrated a settling relationship with particle shape, sphere > cubic > cuboidal. The rheological behaviour explored was categorised into four groups: (i) flow behaviour data was fitted to a simplified Cross model yielding two parameters K (related to viscosity) and n (extent of shear-thinning); (ii) dependency of viscosity on particle volume fraction was characterised using the Krieger-Dougherty model yielding fitting parameter [µ] (particle’s contribution to suspension viscosity) and maximum packing fraction m, this demonstrated the relationship, cuboidal > sphere > cube; (iii) yield stress was characterised using an empirical model derived by Heymann et al (2002) yielding a fitting parameter σ^* (cognate to particle shape and size) and demonstrating a relationship, sphere > cuboidal > cubic; (iv) characterisation of compressive yield stress demonstrated the relationship, cuboidal > cubic > sphere. The results indicate various possible behaviours within the tanks which may impact the storage, remobilisation and pipeline transport of this class of nuclear waste. Ultimately, it is of importance to establish the effect of solid-liquid properties on the behaviour of HAL for current processing, post operational clean out (POCO) and life-time assessment.

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Miller, James. "Modelling melt viscosity for nuclear waste glass." Thesis, University of Sheffield, 2014. http://etheses.whiterose.ac.uk/9110/.

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This work forms part of a Collaborative Awards in Science and Engineering industrial studentship (iCASE), jointly funded by the Engineering and Physical Sciences Research Council and the National Nuclear Laboratory. The aim is to develop improved models for calculating viscosities of vitreous nuclear waste melts, particularly with respect to the variation in temperature and composition. Both in vitro and in situ experimentation on nuclear material is complicated by radioactivity and its associated expenses, so computational modelling is the principal means we use to study these industrially important glasses. The problem is approached with both top-down and bottom-up methods. From a more fundamental perspective, beginning in Section 7 Molecular Dynamics techniques are used to simulate glass melts at atomic resolution. An audit of literature forcefields, using a systematic methodology for particulate systems generation, involved calculation of structural and diffusive properties to reveal the advantages and disadvantages of contemporary sodium-borosilicate models. After developing an improved glass model, from Section 11 different methods of viscosity computation were trialled to determine that most appropriate for the conditions of the nuclear glass melters. In Section 14 the Inoue2 SBN forcefield was combined with the Green-Kubo technique, using simulated runtimes more than double those of previous literature work. The analyses produced qualitative agreement in compositional and temperature trends, as well as order-of-magnitude quantitative agreement between experimental and computational viscosity results for ternary nuclear glass frits. Complimentary top-down approaches were also used, with rotary viscometry experimentation employed in Section 4 to gather temperature-composition-viscometry data for nuclear waste glasses. These data were used with different fitting algorithms in Section 15 to compare the efficacy of theoretical descriptions for glass viscosity, described in Section 3. A combination of fitting techniques assembles in Section 17 an interpolative second-order model for which the maximum discrepancy between prediction and experiment is 17% of the absolute viscosity.

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Books on the topic "Nuclear waste"

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Risoluti, Piero. Nuclear Waste. Berlin, Heidelberg: Springer Berlin Heidelberg, 2004. http://dx.doi.org/10.1007/978-3-662-09012-1.

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Gardiner, Brian. Nuclear waste. New York: Gloucester Press, 1992.

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Nuclear waste. London: Franklin Watts, 2006.

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Nuclear waste. Mankato, Minn: Bridgestone Books, 2003.

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Hansen, Brian. Nuclear Waste. 2455 Teller Road, Thousand Oaks California 91320 United States: CQ Press, 2001. http://dx.doi.org/10.4135/cqresrre20010608.

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Galperin, Anne. Nuclear energy/nuclear waste. New York: Chelsea House Publishers, 1991.

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Galperin, Anne. Nuclear energy, nuclear waste. New York: Chelsea House Publishers, 1992.

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Library of Congress. Major Issues System, ed. Nuclear waste management. [Washington, D.C.]: Library of Congress, Congressional Research Service, Major Issues System, 1985.

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1958-, Streissguth Thomas, ed. Nuclear and toxic waste. San Diego, Calif: Greenhaven Press, 2001.

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League of Women Voters (U.S.). Education Fund, ed. The Nuclear waste primer. New York, NY: Lyons & Burford, 1994.

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Book chapters on the topic "Nuclear waste"

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Rechard, Rob P. "Nuclear Waste." In Encyclopedia of Quality of Life and Well-Being Research, 4391–95. Dordrecht: Springer Netherlands, 2014. http://dx.doi.org/10.1007/978-94-007-0753-5_1971.

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Rechard, Rob P. "Nuclear Waste." In Encyclopedia of Quality of Life and Well-Being Research, 1–8. Cham: Springer International Publishing, 2022. http://dx.doi.org/10.1007/978-3-319-69909-7_1971-2.

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Rechard, Rob P. "Nuclear Waste." In Encyclopedia of Quality of Life and Well-Being Research, 4736–44. Cham: Springer International Publishing, 2023. http://dx.doi.org/10.1007/978-3-031-17299-1_1971.

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Eriksen, Christine, and Stephen Herzog. "Nuclear Waste." In Handbook of the Anthropocene, 1521–25. Cham: Springer International Publishing, 2023. http://dx.doi.org/10.1007/978-3-031-25910-4_247.

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Risoluti, Piero. "The problem." In Nuclear Waste, 1–9. Berlin, Heidelberg: Springer Berlin Heidelberg, 2004. http://dx.doi.org/10.1007/978-3-662-09012-1_1.

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Risoluti, Piero. "A special energy and its enemies." In Nuclear Waste, 10–28. Berlin, Heidelberg: Springer Berlin Heidelberg, 2004. http://dx.doi.org/10.1007/978-3-662-09012-1_2.

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Risoluti, Piero. "Before and after Chernobyl." In Nuclear Waste, 29–75. Berlin, Heidelberg: Springer Berlin Heidelberg, 2004. http://dx.doi.org/10.1007/978-3-662-09012-1_3.

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Risoluti, Piero. "Technical issues." In Nuclear Waste, 76–97. Berlin, Heidelberg: Springer Berlin Heidelberg, 2004. http://dx.doi.org/10.1007/978-3-662-09012-1_4.

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Risoluti, Piero. "Nuclear Waste and Democracy." In Nuclear Waste, 98–129. Berlin, Heidelberg: Springer Berlin Heidelberg, 2004. http://dx.doi.org/10.1007/978-3-662-09012-1_5.

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Nuttall, William J. "Nuclear Waste Management." In Nuclear Renaissance, 89–124. 2nd ed. Boca Raton: CRC Press, 2022. http://dx.doi.org/10.1201/9781003038733-7.

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Conference papers on the topic "Nuclear waste"

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PUSCH, ROLAND, JÖRN KASBOHM, THAO HOANG-MINH, LAN NGUYEN-THANH, and LAURENCE WARR. "DEEP DISPOSAL OF SPENT NUCLEAR FUEL." In WASTE MANAGEMENT 2018. Southampton UK: WIT Press, 2018. http://dx.doi.org/10.2495/wm180371.

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Sjöblom, R. "The long-term effects of nuclear accidents." In WASTE MANAGEMENT 2014. Southampton, UK: WIT Press, 2014. http://dx.doi.org/10.2495/wm140311.

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Khankhasayev, Mikhail Kh, Zhanat B. Kurmanov, and Hans S. Plendl. "NUCLEAR METHODS FOR TRANSMUTATION OF NUCLEAR WASTE." In Proceedings of the International Workshop. WORLD SCIENTIFIC, 1996. http://dx.doi.org/10.1142/9789814530200.

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Maddrell, E. R., and N. B. Milestone. "Current developments and future directions in nuclear waste immobilisation." In WASTE MANAGEMENT 2006. Southampton, UK: WIT Press, 2006. http://dx.doi.org/10.2495/wm060021.

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Maris, Patrick, Rene´ Cornelissen, and Michel Bruggeman. "Radiological Characterization of the Nuclear Waste Streams of the Belgian Nuclear Research Centre SCK•CEN." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7249.

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The radiological characterization of nuclear wastes of a research centre is difficult seen the many different processes that generate waste. Since these wastes may contain radionuclides relevant for the disposal option, the nuclide content and activity have to be known. Considering the fact that some wastes are generated only in minor quantities, complex approaches, involving sampling and successive analysis are not justified. Basic physical models can generally be applied to estimate activity ratios, from which the radionuclide inventory can be determined by non-destructive assay on waste-packages. This article discusses waste streams at the Belgian Nuclear Research Centre SCK•CEN and explains how nuclide inventories and activity are determined. The physical models, used to derive activity ratios, and other simple approaches are discussed.

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Karelin, A. V., and R. V. Shirokov. "Salvaging of nuclear waste by nuclear-optical converters." In International Conference on Lasers, Applications, and Technologies '07, edited by Gennadii Matvienko, Arkadii Ivanov, Petr Nikitin, Eugene Voropay, Mikhail Khodasevich, Vladislav Panchenko, and Vladimir Golubev. SPIE, 2007. http://dx.doi.org/10.1117/12.753140.

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Adams, J. F., S. R. Biggs, M. Fairweather, D. Njobuenwu, and J. Yao. "Theoretical Modelling of Nuclear Waste Flows." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16377.

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A large amount of nuclear waste is stored in tailings ponds as a solid-liquid slurry, and liquid flows containing suspensions of solid particles are encountered in the treatment and disposal of this waste. In processing this waste, it is important to understand the behaviour of particles within the flow in terms of their settling characteristics, their propensity to form solid beds, and the re-suspension characteristics of particles from a bed. A clearer understanding of such behaviour would allow the refinement of current approaches to waste management, potentially leading to reduced uncertainties in radiological impact assessments, smaller waste volumes and lower costs, accelerated clean-up, reduced worker doses, enhanced public confidence and diminished grounds for objection to waste disposal. Mathematical models are of significant value in nuclear waste processing since the extent of characterisation of wastes is in general low. Additionally, waste processing involves a diverse range of flows, within vessels, ponds and pipes. To investigate experimentally all waste form characteristics and potential flows of interest would be prohibitively expensive, whereas the use of mathematical models can help to focus experimental studies through the more efficient use of existing data, the identification of data requirements, and a reduction in the need for process optimisation in full-scale experimental trials. Validated models can also be used to predict waste transport behaviour to enable cost effective process design and continued operation, to provide input to process selection, and to allow the prediction of operational boundaries that account for the different types and compositions of particulate wastes. In this paper two mathematical modelling techniques, namely Reynolds-averaged Navier-Stokes (RANS) and large eddy simulation (LES), have been used to investigate particle-laden flows in a straight square duct and a duct with a bend. The flow solutions provided by these methods have been coupled to a three-dimensional Lagrangian particle tracking routine to predict particle trajectories. Simulation results are shown to be good agreement with experimental data, where available. Based on the LES and RANS-Lagrangian methods, the mean value of the particle displacement in a straight square duct is found to generally decrease with time due to gravity effects, with the rate of deposition increasing with particle size. Using the RANS-Lagrangian method to study flows in a duct bend, there is good agreement between predicted profiles and data, with the method able to simulate particle dispersion, the phenomenon of particle roping and the increase of particle collisions with the bend-wall with particle size. With the LES-Lagrangian method, particle re-suspension from a bed is studied in a straight square duct flow and this process shown to be dominated by secondary flows within the duct, with smaller particles tending to re-suspend in preference to larger ones. Overall, the study demonstrates that modelling techniques can be used to provide insight in to processes that are of relevance to the processing of nuclear waste, and are capable of predicting their transport behaviour. In particular, they are able to provide reliable predictions of particle deposition within flows to form solid beds, the re-suspension of particles from a bed, and the influence of complex flow geometries on particle dispersion. In the latter case, they are also of value to studies of erosion due to particle impact. Such models are therefore of value as engineering tools for use in the prediction of waste behaviour and in cost effective process design.

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8

Kristiansen, Håvard, and Bernt Sigve Aadnøy. "Borehole Disposal of Nuclear Waste." In SPE/IADC International Drilling Conference and Exhibition. SPE, 2021. http://dx.doi.org/10.2118/204117-ms.

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Abstract Approximately 370 000 tons of high-level radioactive waste exists. Some nations have mature projects for disposing of such waste in mined repositories hundreds of meters below ground. Emplacement in boreholes of greater depth could be a cost-efficient and fast alternative, particularly for nations with relatively small amounts of waste. A borehole repository could be developed via an iterative process, which would ultimately end with the completion of a comprehensive safety case and a fully operational disposal facility which would be sealed and decommissioned in a reliable manner. Each design should be adapted to the properties of the waste in question, site-specific geological conditions, and regulatory requirements. This variability causes designs and cost estimates to differ. Overall, borehole disposal of high-level radioactive waste is an opportunity for the drilling industry to expand its service portfolio in a way that is beneficial to the environment and the safety of current and future generations.

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9

Brown, Peter A. "Canada’s New Nuclear Waste Act." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4674.

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The Nuclear Fuel Waste (NEW) Act is a stand-alone piece of legislation with some 30 articles and without regulations. The Act deals essentially with social, financial and socioeconomic considerations of the long-term management of nuclear fuel waste. It complements the health, environment, safety and security requirements under the Nuclear Safety and Control, Act. The NFW Act provides for 1) the nuclear industry to set up a waste management organization to manage the full long-term waste management activities and to establish trust funds to finance long-term waste management responsibilities; and 2) the waste management organization to submit, for government decision, long-term waste management options within three years of coming into force.

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Evans, N., R. Hallam, S. Aldridge, and P. Warwick. "The fate of Tc in a UK intermediate-level nuclear waste repository." In WASTE MANAGEMENT 2008. Southampton, UK: WIT Press, 2008. http://dx.doi.org/10.2495/wm080591.

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Reports on the topic "Nuclear waste"

1

McDaniel, E. (Nuclear waste management). Office of Scientific and Technical Information (OSTI), November 1988. http://dx.doi.org/10.2172/6995981.

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2

Toor, A., and R. Buck. Transmutation of radioactive nuclear waste. Office of Scientific and Technical Information (OSTI), March 2000. http://dx.doi.org/10.2172/15005725.

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3

DOE. Managing Nuclear Waste: Options Considered. Office of Scientific and Technical Information (OSTI), May 2002. http://dx.doi.org/10.2172/808028.

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4

Weber, William J. Radiation Effects in Nuclear Waste Materials. Office of Scientific and Technical Information (OSTI), June 2005. http://dx.doi.org/10.2172/893271.

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Weber, William J., L. Rene Corrales, Nancy J. Ness, Ralph E. Williford, Howard L. Heinisch, Suntharampillai Thevuthasan, Jonathan P. Icenhower, et al. Radiation Effects in Nuclear Waste Materials. Office of Scientific and Technical Information (OSTI), October 2000. http://dx.doi.org/10.2172/985099.

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Weber, William J. Radiation Effects in Nuclear Waste Materials. Office of Scientific and Technical Information (OSTI), September 2005. http://dx.doi.org/10.2172/881101.

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7

Abrahms, C. W., M. D. Patridge, and J. E. Widrig. International nuclear waste management fact book. Office of Scientific and Technical Information (OSTI), November 1995. http://dx.doi.org/10.2172/206523.

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Weber, William J., Lumin Wang, Nancy J. Hess, and B. Peter McGrail. Radiation Effects in Nuclear Waste Materials. Office of Scientific and Technical Information (OSTI), June 2001. http://dx.doi.org/10.2172/833736.

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Weber, William J., Lumin Wang, Jonathan P. Icenhower, Nancy J. Hess, and Suntharampillai Thevuthasan. Radiation Effects in Nuclear Waste Materials. Office of Scientific and Technical Information (OSTI), June 2002. http://dx.doi.org/10.2172/833738.

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10

Weber, William J., Lumin Wang, Nancy J. Hess, Jonathan P. Icenhower, and Suntharampillai Thevuthasan. Radiation Effects in Nuclear Waste Materials. Office of Scientific and Technical Information (OSTI), June 2003. http://dx.doi.org/10.2172/833746.

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