Chemical Decomposition of High-level Nuclear Waste Storage/disposal Glasses Under Irradiation. 1998 Annual Progress Report

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ISBN 13 :
Total Pages : 3 pages
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Book Synopsis Chemical Decomposition of High-level Nuclear Waste Storage/disposal Glasses Under Irradiation. 1998 Annual Progress Report by :

Download or read book Chemical Decomposition of High-level Nuclear Waste Storage/disposal Glasses Under Irradiation. 1998 Annual Progress Report written by and published by . This book was released on 1998 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this project is to employ the technique of electron spin resonance (ESR), in conjunction with other experimental methods, to study radiation-induced decomposition of vitreous compositions proposed for immobilization/disposal of high-level nuclear wastes (HLW) or excess weapons plutonium. ESR is capable of identifying, even at the parts-per-million level, displaced atoms, ruptured bonds, and free radicals created by radiation in such glassy forms. For example, one of the scientific goals is to determine whether ESR-detectable superoxide (O2−) and ozonide (O3−) ions are precursors of radiation-induced oxygen gas bubbles reported by other investigators. The fundamental understandings obtained in this study will enable reliable predictions of the long-term effects of and decays of the immobilized radionuclides on HLW glasses. This report represents the results of an 18-month effort performed under a 3-year research award. Four categories of materials were studied: (1) several actual and proposed HLW glass compositions fabricated at Savannah River Technology Center (SRTC), samples of which had been irradiated to a dose of 30 MGy (1 Gy = 100 rad) to simulate decay effects, (2) several high-iron phosphate glasses fabricated at the University of Missouri-Rolla (UMR), (3) one other model HLW glass and several simulated natural glasses which had been implanted with 160-keV He ions to simulate-decay damage, and (4) an actual geological glass damaged by decays of trace amounts of contained 238U and 232Th over a period of 65 Myears. Among the category-1 materials were two samples of Defense Waste Processing Facility (DWPF) borosilicate glasses modeling compositions currently being used to vitrify HLW at SRTC. The ESR spectra recorded for the unirradiated DWPF-glass simulants were attributable to Fe 3 ions. The 30-MGy irradiation was found to change the Fe{sup 3+} concentration of these glasses by a statistically insignificant factor (0.987 \261 0.050) and not to create measurable numbers of other defects.

Radiation Effects on Transport and Bubble Formation in Silicate Glasses. 1998 Annual Progress Report

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Total Pages : 3 pages
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Book Synopsis Radiation Effects on Transport and Bubble Formation in Silicate Glasses. 1998 Annual Progress Report by :

Download or read book Radiation Effects on Transport and Bubble Formation in Silicate Glasses. 1998 Annual Progress Report written by and published by . This book was released on 1998 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt: To study the fundamental chemistry of radiation damage in silicate/borosilicate glasses and simulated high-level nuclear waste (HLW) forms. Special emphasis is on delineating molecular processes crucial for understanding the aggregation of defects and formation of oxygen bubbles. The knowledge obtained will provide the needed scientific basis for extrapolating long-term behavior of stored radiative waste glass forms. This report summarizes the first 6 months of a 3-year project. The following issues have been addressed: (i) the production of radiolytic oxygen, (ii) the chemistry of hydrogenous species, and (iii) the effect of glass composition and microstructure on the formation and accumulation of metastable point defects.

The Influence of Radiation and Multivalent Cation Additions on Phase Separation and Crystallization of Glass. 1998 Annual Progress Report

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Total Pages : 3 pages
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Book Synopsis The Influence of Radiation and Multivalent Cation Additions on Phase Separation and Crystallization of Glass. 1998 Annual Progress Report by :

Download or read book The Influence of Radiation and Multivalent Cation Additions on Phase Separation and Crystallization of Glass. 1998 Annual Progress Report written by and published by . This book was released on 1998 with total page 3 pages. Available in PDF, EPUB and Kindle. Book excerpt: The major objectives of this proposed investigation are as follows: (1) To investigate the influence of multivalent cations on the thermodynamics and kinetics of phase separationand crystallization in simple model glasses. (2) To study the influence of a and b particle, heavy ion bombardment and g irradiation on phase separation and crystallization in simple model glasses. (3) To examine the structural changes produced by radiation just prior to the onset of phase separation and/or crystallization. (4) To develop models to explain the observed effects of multivalent cations and radiation on phase separation and crystallization. (5) To utilize the results of these experimental and modeling studies to provide guidelines for the allowed range of composition choices and processing conditions in order to avoid the formation of unwanted phases in nuclear waste disposal glasses. At the fundamental level, the effects of radiation, of transition metal ion additions, and of melting history in the case of multi-valent cations, on phase separation and crystallization behavior will be evaluated for simple glasses whose baseline behavior is characterized and understood. At the practical level, the program will determine the magnitude of the risk associated with the effects of radiation in inducing phase separation and crystallization. It will also provide approaches to ameliorating such effects through controlled complementary dopants and control of melting/processing conditions.

Glass as a Waste Form and Vitrification Technology

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Publisher : National Academies Press
ISBN 13 : 0309056829
Total Pages : 172 pages
Book Rating : 4.3/5 (9 download)

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Book Synopsis Glass as a Waste Form and Vitrification Technology by : National Research Council

Download or read book Glass as a Waste Form and Vitrification Technology written by National Research Council and published by National Academies Press. This book was released on 1997-03-02 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Annual Report on the Characteristics of High-level Waste Glasses

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Annual Report on the Characteristics of High-level Waste Glasses by :

Download or read book Annual Report on the Characteristics of High-level Waste Glasses written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Processes are being developed to immobilize high-level radioactive wastes in glass for increased safety during handling, storage and final disposal. A concurrent program is the characterization of the waste-containing glasses produced by these processes, particularly in relation to their expected long-term behavior as affected by thermal and radiation-induced alteration of the glass. A compilation of characterization data is presented for low-melting (less than 1100°C) borosilicate waste glasses, which may contain 33 wt percent or more waste and which can be melted in situ in their stainless steel storage canisters. The data demonstrate that these low-melting glasses are relatively unaffected by the radiation doses to which they are exposed. The data also show that thermally induced devitrification and phase separation can be minimized by proper selection of glass composition.

An Alternative Host Matrix Based on Iron Phosphate Glasses for the Vitrification of Specialized Nuclear Waste Forms. 1998 Annual Progress Report

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ISBN 13 :
Total Pages : 4 pages
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Book Synopsis An Alternative Host Matrix Based on Iron Phosphate Glasses for the Vitrification of Specialized Nuclear Waste Forms. 1998 Annual Progress Report by :

Download or read book An Alternative Host Matrix Based on Iron Phosphate Glasses for the Vitrification of Specialized Nuclear Waste Forms. 1998 Annual Progress Report written by and published by . This book was released on 1998 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt: Certain high level wastes (HLW) in the US contain components such as phosphates, heavy metals, and halides which make them poorly suited for disposal in borosilicate glasses. Iron phosphate glasses appear to be a technically feasible alternative to borosilicate glasses for vitrifying these HLWs. The iron phosphate glasses mentioned above and their nuclear wasteforms are relatively new, so little is known about their atomic structure, redox equilibria, structure-property relationships, and crystallization products and characteristics. The objective of this research is to gain such information for the binary iron-phosphate glasses as well as iron phosphate wasteforms so that a comprehensive scientific assessment can be made of their usefulness in nuclear waste disposal. This report summarizes the work undertaken and completed in the first 20 months of a three year project. Approximately 250 samples, binary iron phosphate glasses and iron phosphate glasses containing one or two common nuclear waste components such as UO2, Na2O, Bi2O3, Cs2O, SrO, and MoO3, have been prepared. Weight loss has been used to measure the chemical durability and the redox equilibria between Fe(II) and Fe(III) has been investigated using Moessbauer spectroscopy. The atomic structure has been investigated using a variety of techniques including Mossbauer, Raman, X-ray absorption (XAS), and X-ray photoelectron (XPS) spectroscopies and neutron/high energy X-ray scattering. Glass forming and crystallization characteristics have been investigated using differential thermal analysis (DTA). In addition, information necessary for glass manufacturing such as suitable refractories and Joule heating parameters also have been obtained.

Radioactive Waste Processing and Disposal

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ISBN 13 :
Total Pages : 908 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Radioactive Waste Processing and Disposal by : U.S. Nuclear Regulatory Commission

Download or read book Radioactive Waste Processing and Disposal written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 908 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass

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ISBN 13 :
Total Pages : 31 pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass by :

Download or read book Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass written by and published by . This book was released on 1990 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt: Savannah River Site (SRS), currently is storing (approximately)30 million gallons of highly radioactive nuclear wastes. The Defense Waste Processing Facility (DWPF) nearing completion at SRS will incorporate the radionuclides in these wastes into solid borosilicate glass for final disposal in a geologic repository. Because of the variability of the wastes in the tanks, borosilicate glasses of different compositions will be produced by the DWPF during the 20--25 years required to solidify all the wastes at SRS. A chemical durability test, the Product Consistency Test (PCT), has been developed at SRS to measure the consistency of the durability of these glasses. This paper describes the remote and hands-on procedures for performing the PCT on these radioactive glasses. Results will be presented that indicate the good precision of the PCT and indicate some of the chemistry involved in leaching radioactive elements from the glass. 9 refs., 1 fig., 4 tabs.

Defense HLW Glass Degradation Model

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ISBN 13 :
Total Pages : 206 pages
Book Rating : 4.:/5 (316 download)

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Book Synopsis Defense HLW Glass Degradation Model by : D. Strachan

Download or read book Defense HLW Glass Degradation Model written by D. Strachan and published by . This book was released on 2004 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this report is to document the development of a model for calculating the release rate for radionuclides and other key elements from high-level radioactive waste (HLW) glasses under exposure conditions relevant to the performance of the repository. Several glass compositions are planned for the repository, some of which have yet to be identified (i.e., glasses from Hanford and Idaho National Engineering and Environmental Laboratory). The mechanism for glass dissolution is the same for these glasses and the glasses yet to be developed for the disposal of DOE wastes. All of these glasses will be of a quality consistent with the glasses used to develop this report.

Factors Influencing Chemical Durability of Nuclear Waste Glasses

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ISBN 13 :
Total Pages : 8 pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Factors Influencing Chemical Durability of Nuclear Waste Glasses by :

Download or read book Factors Influencing Chemical Durability of Nuclear Waste Glasses written by and published by . This book was released on 1993 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: A short summary is given of our studies on the major factors that affect the chemical durability of nuclear waste glasses. These factors include glass composition, solution composition, SA/V (ratio of glass surface area to the volume of solution), radiation, and colloidal formation. These investigations have enabled us to gain a better understanding of the chemical durability of nuclear waste glasses and to accumulate.a data base for modeling the long-term durability of waste glass, which will be used in the risk assessment of nuclear waste disposal. This knowledge gained also enhances our ability to formulate optimal waste glass compositions.

Nuclear Waste Conditioning

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Publisher : Le Moniteur Editions
ISBN 13 :
Total Pages : 160 pages
Book Rating : 4.3/5 ( download)

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Book Synopsis Nuclear Waste Conditioning by : France. Commissariat à l'énergie atomique (CEA)

Download or read book Nuclear Waste Conditioning written by France. Commissariat à l'énergie atomique (CEA) and published by Le Moniteur Editions. This book was released on 2009 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Annual Report on the Characterization on the High-level Waste Glasses

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (873 download)

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Book Synopsis Annual Report on the Characterization on the High-level Waste Glasses by :

Download or read book Annual Report on the Characterization on the High-level Waste Glasses written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The waste compo itions PW-7c and PW-9 were defined and glass development was completed. Major variations in major oxide concentration would not grossly affect the leach rates of the glass. Impact and strength tests on nonradioactive glass showed that the waste glasses produced slightly less fine particulate than commercial glass. Waste glass had 60% of the strength of the soda-lime glass. A water-quench reduced thermal conductivity about 20%, and a 24-h hold at devitrification temperatures did not produce a significant change. Densities of waste glass at process temperature were 6.6 to 9.3% lower than at room temperature. The effects of glass composition on volatility were measured. Leach tests of highly devitrified samples of 72-68 have shown that leach rates of Cs, Sr and U are increased up to 10X and that Zn leach rates are reduced by nearly 200X. In glass 76-68, where devitrification is much slower, elemental differencesbetween as-formed and thermally-treated samples have not been significant. Average Cs leach rates from the 76-68 glass in an IAEA type long-term test have decreased to 3.3 x 10−8 g/cm2/day. High temperature (250 and 350°C) leach tests showed that glass is comparable to other ceramic materials. In salt brine the glass is rapidly depleted of Cs, Rb and Mo; in water the glass structure is rapidly rearranged to a crystalline structure, and Cs and Rb tend to remain bound in the solid. 76-68 glass (low ZnO) has slow devitrification kinetics compared to 72-68 glass (high ZnO). After equivalent radiation exposures of 300,000 years, the glass buttons still retain their original physical appearance. Stored energy is not a problem for HLW glasses. Density changes are small and do not affect the integrity of the samples. (DLC).

Safe Management of Wastes from Health-care Activities

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Publisher : World Health Organization
ISBN 13 : 9241548568
Total Pages : 327 pages
Book Rating : 4.2/5 (415 download)

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Book Synopsis Safe Management of Wastes from Health-care Activities by : Yves Chartier

Download or read book Safe Management of Wastes from Health-care Activities written by Yves Chartier and published by World Health Organization. This book was released on 2014 with total page 327 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is the second edition of the WHO handbook on the safe, sustainable and affordable management of health-care waste--commonly known as "the Blue Book". The original Blue Book was a comprehensive publication used widely in health-care centers and government agencies to assist in the adoption of national guidance. It also provided support to committed medical directors and managers to make improvements and presented practical information on waste-management techniques for medical staff and waste workers. It has been more than ten years since the first edition of the Blue Book. During the intervening period, the requirements on generators of health-care wastes have evolved and new methods have become available. Consequently, WHO recognized that it was an appropriate time to update the original text. The purpose of the second edition is to expand and update the practical information in the original Blue Book. The new Blue Book is designed to continue to be a source of impartial health-care information and guidance on safe waste-management practices. The editors' intention has been to keep the best of the original publication and supplement it with the latest relevant information. The audience for the Blue Book has expanded. Initially, the publication was intended for those directly involved in the creation and handling of health-care wastes: medical staff, health-care facility directors, ancillary health workers, infection-control officers and waste workers. This is no longer the situation. A wider range of people and organizations now have an active interest in the safe management of health-care wastes: regulators, policy-makers, development organizations, voluntary groups, environmental bodies, environmental health practitioners, advisers, researchers and students. They should also find the new Blue Book of benefit to their activities. Chapters 2 and 3 explain the various types of waste produced from health-care facilities, their typical characteristics and the hazards these wastes pose to patients, staff and the general environment. Chapters 4 and 5 introduce the guiding regulatory principles for developing local or national approaches to tackling health-care waste management and transposing these into practical plans for regions and individual health-care facilities. Specific methods and technologies are described for waste minimization, segregation and treatment of health-care wastes in Chapters 6, 7 and 8. These chapters introduce the basic features of each technology and the operational and environmental characteristics required to be achieved, followed by information on the potential advantages and disadvantages of each system. To reflect concerns about the difficulties of handling health-care wastewaters, Chapter 9 is an expanded chapter with new guidance on the various sources of wastewater and wastewater treatment options for places not connected to central sewerage systems. Further chapters address issues on economics (Chapter 10), occupational safety (Chapter 11), hygiene and infection control (Chapter 12), and staff training and public awareness (Chapter 13). A wider range of information has been incorporated into this edition of the Blue Book, with the addition of two new chapters on health-care waste management in emergencies (Chapter 14) and an overview of the emerging issues of pandemics, drug-resistant pathogens, climate change and technology advances in medical techniques that will have to be accommodated by health-care waste systems in the future (Chapter 15).

Modifications Induced by Irradiation in Glasses

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Publisher : North Holland
ISBN 13 :
Total Pages : 120 pages
Book Rating : 4.F/5 ( download)

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Book Synopsis Modifications Induced by Irradiation in Glasses by : Paolo Mazzoldi

Download or read book Modifications Induced by Irradiation in Glasses written by Paolo Mazzoldi and published by North Holland. This book was released on 1992 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Many aspects of the interaction of radiation with glasses are reviewed in this volume, with contributions from a broad scientific community. Several of the papers focus on the interdisciplinary approach required to connect technological applications to the basic interactions of energetic ions with insulators, reporting on the challenging problems that still remain to be solved. The high quality of these contributions once again demonstrates that the E-MRS is an efficient forum for interaction between research workers and industry. The proceedings represent an ideal bridge between the sixth and the planned seventh International Conference on Radiation Effects in Insulators to be held in Japan in 1993.

Nuclear Waste Glasses - Suitability, Surface Studies, and Stability

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Nuclear Waste Glasses - Suitability, Surface Studies, and Stability by :

Download or read book Nuclear Waste Glasses - Suitability, Surface Studies, and Stability written by and published by . This book was released on 1999 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Every major country involved with long-term management of high-level radioactive waste (HLW) has either selected or is considering glass as the matrix of choice for immobilizing and ultimately, disposing of the potentially hazardous, high-level radioactive material. There are many reasons why glass is preferred. Among the most important considerations are the ability of glass structures to accommodate and immobilize the many different types of radionuclides present in HLW, and to produce a product that not only has excellent technical properties, but also possesses good processing features. Good processability allows the glass to be fabricated with relative ease even under difficult remote-handling conditions necessary for vitrification of highly radioactive material. The single most important property of the waste glass produced is its ability to retain hazardous species within the glass structure and this is reflected by its excellent chemical durability and corrosion resistance to a wide range of environmental conditions.

High-level Nuclear Waste Borosilicate Glass

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ISBN 13 :
Total Pages : 9 pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis High-level Nuclear Waste Borosilicate Glass by :

Download or read book High-level Nuclear Waste Borosilicate Glass written by and published by . This book was released on 1992 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: With the imminent startup, in the United States, of facilities for vitrification of high-level nuclear waste, a document has been prepared that compiles the scientific basis for understanding the alteration of the waste glass products under the range of service conditions to which they may be exposed during storage, transportation, and eventual geologic disposal. A summary of selected parts of the content of this document is provided. Waste glass alterations in a geologic repository may include corrosion of the glass network due to groundwater and/or water vapor contact. Experimental testing results are described and interpreted in terms of the underlying chemical reactions and physical processes involved. The status of mechanistic modeling, which can be used for long-term predictions, is described and the remaining uncertainties associated with long-term simulations are summarized.

Structure and Durability of UK Simulated High Level Nuclear Waste Glasses

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (861 download)

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Book Synopsis Structure and Durability of UK Simulated High Level Nuclear Waste Glasses by : Nathan Cassingham

Download or read book Structure and Durability of UK Simulated High Level Nuclear Waste Glasses written by Nathan Cassingham and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The understanding of dissolution of the British nuclear waste glass, as compared to other nuclear waste glasses, is limited. The few studies that have been performed were generally done in static leach tests with the exception of the single pass flow through test performed by Abratis during his PhD, producing a number of papers (Abraitis, P.K., Univ. Manchester, 1999; Abraitis, P.K. et. al., Applied Geochemistry 15 (2000) 1399; Abraitis, P.K. et. al., Mat. Res. Soc. Sym. Pro. 556 (1999) 401). In order to gain further insight to the British nuclear waste glasses X-ray absorption spectroscopy was used along with dissolution studies of British simulated nuclear waste glasses to determine the role of Zn and to ascertain the mechanisms of corrosion. Both baseline glasses along with a Blend simulated nuclear waste glass were studied to give better comparisons with previous results by other authors. The Blend waste glass is composed of a mixture of Magnox reactor waste and thorium oxide reprocessing (ThORP) waste at a wt% of 25wt% Magnox waste and 75 wt% ThORP. Zn K edge X-ray absorption spectroscopy was applied to determine the Zn coordination environment in model inactive UK high level waste (HLW) glasses. Quantitative analysis of the X-ray absorption fine structure (EXAFS) data provided conclusive evidence for the presence of ZnO4 species participating in network formation, linking, on average, to 2 ± 1 SiO4 units via bridging oxygen atoms. Excellent quantitative agreement was observed between the Zn-O contact distance and coordination number determined from EXAFS and previous Molecular Dynamics simulations of glasses with the same nominal composition. Analysis also provided evidence in support of the network forming role of Zn as predicted from Molecular Dynamics simulation, but it was not possible to confirm the predicted clustering of Zn species at high Zn concentration in simple soda lime silica glasses. The single pass flow through (SPFT) work in this study has shown that the steady state dissolution of a base glass with 25 wt% waste loading (MW+25wt%) and a base glass with 30 wt% waste loading (MW+30wt%) of Blend simulated nuclear waste glasses is similar to that of previous studies. The SPFT flow per surface area (Q/S) results are consistent with previous studies. The dissolution rate dependency on temperature and pH of was also consistent with similar glasses. The NRi with respect to B, Si, Na and Al, of the glasses in this study increased with an increase in solution pH. The average activation energy with respect to Si was consistent for a surface controlled reaction with these glasses as was shown in previous studies on MW+Magnox, a similar glass. One of the current designs for a geological repository of HLW is a co-located repository with intermediate level waste (ILW). At long times, there is the possibility of hyper alkaline solution from the ILW repository interacting with the vitrified HLW glass wasteforms. Dissolution studies were performed to understand the mechanisms by which the UK HLW glasses will corrode under hyper alkaline solutions. The addition of an alkali buffer to high purity H2O resulted in a decrease of the dissolution rate for the MW Blend glasses during the product consistency type tests. The concentration of Si in solution for all of the samples suggests that Ca and Si are co-precipitating as was evident from the decrease in Ca concentrations at short times. It is suggested that the presence of Ca in solution forms a passive reactive interface (PRI) which decreases the rate of formation of a hydrated surface layer decreasing the overall dissolution rate. The results from the geochemical modelling of the product consistency type tests showed that Ca and Si are co-precipitating at short times decreasing the normalised mass loss. This is evident from the Ca and Si phases which are most probable to precipitate out of solution as suggested by the geochemical modelling results from PhREEQC In order to understand the mechanisms of alteration layer formation of the UK HLW glasses, vapour hydration tests (VHT) were performed. Results from the time dependant VHT experiments have shown changes in the mechanisms of alteration layer formation with the addition of the simulated Blend waste to the base glasses. It was also shown that iron may be a suppressor to zinc dissolution. Both a Ca and Zn doped Blend waste glass and a base glass doped with Fe Zn and Zr did not show significant layers of zinc in the alteration layer as shown in the Ca and Zn doped base glass in both the reproducibility or time-dependant VHT experiments. Giesler et al. have similar results to the VHT results in this study, which correlate to an interface-coupled dissolution-reprecipitation mechanism when simulated Blend waste is added to the base glasses (Giesler, T. et. al., J. Non-Cryst. Solids 356 (2010) 1458). However, further.