187 results on '"Hand, Russell J."'
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2. Nuclear Waste Vitrification and Chemical Durability
3. Structural and thermophysical behaviour of barium zinc aluminoborosilicate glasses for potential application in SOFCs
4. The dissolution of simulant UK Ca/Zn-modified nuclear waste glass: the effect of increased waste loading
5. Applying laboratory methods for durability assessment of vitrified material to archaeological samples
6. Forty years of durability assessment of nuclear waste glass by standard methods
7. Soda-Lime-Silica Glasses
8. The dissolution of simulant UK Ca/Zn-modified nuclear waste glass: Insight into Stage III behavior
9. Glass structure and crystallization in boro-alumino-silicate glasses containing rare earth and transition metal cations: a US-UK collaborative program
10. The Formation of Pitted Features on the International Simple Glass during Dynamic Experiments at Alkaline pH
11. Vibration analysis of cracked beam based on Reddy beam theory by finite element method.
12. Micro- and Nanoscale Surface Analysis of Late Iron Age Glass from Broborg, a Vitrified Swedish Hillfort
13. Silicon oxycarbide glass for the immobilisation of irradiated graphite waste
14. Mechanical properties of soda–lime–silica glasses with varying alkaline earth contents
15. Physical and optical properties of the International Simple Glass
16. Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes
17. MoO3 incorporation in magnesium aluminosilicate glasses
18. Effect of network connectivity on behavior of synthetic Broborg hillfort glasses
19. Evaluation of novel leaching assessment of nuclear waste glasses
20. Vibration analysis of cracked beam based on Reddy beam theory by finite element method
21. Corrosion of the International Simple Glass under acidic to hyperalkaline conditions
22. Encapsulation of TRISO particle fuel in durable soda-lime-silicate glasses
23. Effect of network connectivity on behavior of synthetic Broborg hillfort glasses.
24. Zn nanodot patterning in borosilicate glasses by electron irradiation
25. Fractographic analysis of epoxy coated glass
26. Chemical structure and dissolution behaviour of CaO and ZnO containing alkali-borosilicate glass
27. M0O3 incorporation in alkaline earth aluminosilicate glasses
28. Modelling the strengthening of glass using epoxy based coatings
29. The Use of High Durability Alumino-Borosilicate Glass for the Encapsulation of High Temperature Reactor (HTR) Fuel
30. The Effect of γ-radiation on Mechanical Properties of Model UK Nuclear Waste Glasses
31. CeO 2 nano-precipitation in borosilicate glasses: A redox study using EELS
32. Mechanical properties of silicate glasses as a function of composition
33. Surface hydration and nanoindentation of silicate glasses
34. Thermal treatment of nuclear fuel-containing Magnox sludge radioactive waste
35. Effects of composition and phase relations on mechanical properties and crystallization of silicate glasses
36. Mechanical Properties of Inorganic Glasses
37. Analytical STEM of Borosilicate Glasses Containing Molybdates.
38. Vapour Phase Hydration of Blended Oxide - Magnox Waste Glasses
39. The Structural Chemistry of Molybdenum in Model High Level Nuclear Waste Glasses, Investigated by MO K-Edge X-Ray Absorption Spectroscopy
40. Short communication: The dissolution of UK simulant vitrified high-level-waste in groundwater solutions
41. Corrosion of alkali–borosilicate waste glass K-26 in non-saturated conditions
42. Glass Development for Vitrification of Wet Intermediate Level Waste (WILW) from Decommissioning of the Hinkley Point ‘A’ Site
43. Immobilisation of Simulated Plutonium-Contaminated Material in Phosphate Glass: An Initial Scoping Study
44. Survey of Potential Glass Compositions for the Immobilisation of the UK’s Separated Plutonium Stocks
45. Vitrification of an intermediate level Magnox sludge waste
46. Vapour Phase Hydration of Magnox Waste Glass
47. Comment on “Preliminary assessment of modified borosilicate glasses for chromium and ruthenium immobilization”, by Farid and Rahman
48. Immobilisation of Prototype Fast Reactor raffinate in a barium borosilicate glass matrix
49. Incorporation and phase separation of Cl in alkaline earth aluminosilicate glasses
50. Corrigendum to “The dissolution rates of simulated UK Magnox – ThORP blend nuclear waste glass as a function of pH, temperature and waste loading” [Miner. Mag. 79, (2015) 1529–1542]
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