Professor Russell J Hand
MA PhD MEd CPhys MInstP CPhys FSGT FHEA
Department of Materials Science and Engineering
Director of Learning & Teaching
Professor of Glass Science & Engineering, Past-President of the Society of Glass Technology
+44 114 222 5465
Full contact details
Department of Materials Science and Engineering
Sir Robert Hadfield Building
Russell Hand joined the Department in 1989, from Cambridge University, as the Redland Research Fellow.
He was appointed to a Lectureship in 1990 (Senior Lecturer 2001; Reader 2010; Professor 2012) and in 1999 obtained an MEd in Teaching and Learning for University Lecturers.
From 2001 to 2012 he served as Sub-Dean for Undergraduate Affairs in the Faculty of Engineering and then Deputy FLTD Engineering. From 2013 to 2015 he was course director for the cross-Faculty Aerospace Engineering degrees.
Between 2014 and 2017, Russell was Head of the Interdisciplinary Programmes Office, Faculty of Engineering.
- Research interests
Russell has wide-ranging research interests in glass with a particular foci on waste vitrification (linked to the Immobilisation Science Laboratory) and the mechanical properties of glass. Please contact Russell directly for details of currently available PhD projects.
- Radioactive waste vitrification
Research is focussed on glass composition development for the immobilisation of "difficult" anionic species and legacy wastes into vitreous wasteforms. His group is currently working on developing novel glasses for the vitrification of Mo containing wastes and understanding the crystallisation of Mo containing phases in current waste glass compositions.
- Sensing using reinforcing fibres in polymer matrix composites
Research is focussed on developing novel glasses for reinforcing fibres that can be used for both chemical and damage sensing in polymer matrix composites. This research is being undertaken in collaboration with CSIC.
- Durability of nuclear waste glasses
Research is focussed on understanding the effects of high pH environments on the durability of nuclear waste glasses using laboratory-based durability test methods. In addition, he is responsible for the field-based long term glass burial site at Ballidon (a limestone environment), an experiment now in its 44th year, and which involves collaboration with Dr Strachan from Pacific North-West National Laboratory, USA.
- Mechanical properties of glasses
Research is focussed on examining the effects of composition on the mechanical properties of silicate glasses. His group has previously demonstrated the important role of MgO in these glasses and we are currently investigating this further. We have also studied the mechanical properties of nuclear borosilicate glasses. His group is also focussing on assessing the changes in near surface mechanical properties of glasses due to hydration by nanoindentation and at the effects of high-temperature mechanical contact on surface damage and thus the practical strength of bulk glass.
- Radioactive waste vitrification
- Localised extended (“vermiform”) features formed during glass dissolution. Journal of Non-Crystalline Solids, 608, 122230-122230.
- Micro- and Nanoscale Surface Analysis of Late Iron Age Glass from Broborg, a Vitrified Swedish Hillfort. Microscopy and Microanalysis, 29(1), 50-68.
- Effect of network connectivity on behavior of synthetic Broborg Hillfort glasses. Journal of the American Ceramic Society.
- Vibration analysis of cracked beam based on Reddy beam theory by finite element method. Journal of Vibration and Control.
- Applying laboratory methods for durability assessment of vitrified material to archaeological samples. npj Materials Degradation, 5(1).
- Forty years of durability assessment of nuclear waste glass by standard methods. npj Materials Degradation, 5(1).
- Structural and thermophysical behaviour of barium zinc aluminoborosilicate glasses for potential application in SOFCs. Journal of Non-Crystalline Solids, 572. View this article in WRRO
- Effects of composition and phase relations on mechanical properties and crystallization of silicate glasses. Journal of the American Ceramic Society.
- Thermal treatment of nuclear fuel-containing Magnox sludge radioactive waste. Journal of Nuclear Materials. View this article in WRRO
- Short communication : the dissolution of UK simulant vitrified high-level-waste in groundwater solutions. Journal of Nuclear Materials. View this article in WRRO
- The dissolution of simulant UK Ca/Zn-modified nuclear waste glass : insight into Stage III behavior. MRS Advances, 5(3-4), 103-109. View this article in WRRO
- Investigation of the role of Mg and Ca in the structure and durability of aluminoborosilicate glass. Journal of Non-Crystalline Solids, 512(1), 41-52. View this article in WRRO
- Physical and optical properties of the International Simple Glass. npj Materials Degradation, 3(1). View this article in WRRO
- Vitrification of an intermediate level Magnox sludge waste. Journal of Nuclear Materials, 515, 392-400. View this article in WRRO
- Glass structure and crystallization in boro-alumino-silicate glasses containing rare earth and transition metal cations: a US-UK collaborative program. MRS Advances, 4(17-18), 1029-1043.
- The Formation of Pitted Features on the International Simple Glass during Dynamic Experiments at Alkaline pH. MRS Advances, 4(17-18), 993-999. View this article in WRRO
- Corrosion of the International Simple Glass under acidic to hyperalkaline conditions. npj Materials Degradation, 2. View this article in WRRO
- Immobilisation of Prototype Fast Reactor raffinate in a barium borosilicate glass matrix. Journal of Nuclear Materials, 508, 203-211. View this article in WRRO
- Incorporation and phase separation of Cl in alkaline earth aluminosilicate glasses. Journal of Nuclear Materials, 507, 135-144. View this article in WRRO
- 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]. Mineralogical Magazine, 82(4), 939-942.
- Letter to the Editor: Concentrated Solar (CS) thermal melting versus photovoltaic (PV) based electric melting. Glass Technology: European Journal of Glass Science and Technology Part A, 58(5), 156-158. View this article in WRRO
- Comment on “Preliminary assessment of modified borosilicate glasses for chromium and ruthenium immobilization”, by Farid and Rahman. Materials Chemistry and Physics, 192, 29-32.
- Glass melting using concentrated solar thermal energy. Glass Technology: European Journal of Glass Science and Technology Part A, 58(2), 41-48. View this article in WRRO
- Evaluation of novel leaching assessment of nuclear waste glasses. MRS Advances. View this article in WRRO
- Alteration layer formation of Ca- and Zn-oxide bearing alkali borosilicate glasses for immobilisation of UK high level waste: A vapour hydration study. Journal of Nuclear Materials, 479, 639-646. View this article in WRRO
- Dissolution of molybdate anions in borosilicate glasses for nuclear waste vitrification use. Materials China, 35(7), 496-503. View this article in WRRO
- Silicon oxycarbide glass for the immobilisation of irradiated graphite waste. Journal of Nuclear Materials, 469, 51-56. View this article in WRRO
- Mechanical properties of soda–lime–silica glasses with varying alkaline earth contents. Journal of Non-Crystalline Solids, 429, 190-197. View this article in WRRO
- The initial dissolution rates of simulated UK Magnox–ThORP blend nuclear waste glass as a function of pH, temperature and waste loading. Mineralogical Magazine, 79(6), 1529-1542. View this article in WRRO
- Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes. Journal of Nuclear Materials, 462, 321-328. View this article in WRRO
- Zn nanodot patterning in borosilicate glasses by electron irradiation. Journal of Materials Research, 30(12), 1914-1924. View this article in WRRO
- MoO3 incorporation in magnesium aluminosilicate glasses. Journal of Nuclear Materials, 458, 335-342. View this article in WRRO
- Effect of ZnO and CaO on alkali borosilicate glass waste-form immobilizing simulated mixed HLW. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 49(7), 1159-1164.
- Investigation of the mechanical properties and fracture morphology of glass ceramic fibers. Advanced Manufacturing: Polymer & Composites Science, 1(2), 120-127.
- Leaching behaviour of cementitious nuclear wasteforms containing caesium and strontium. Advances in Applied Ceramics, 113(8), 447-452. View this article in WRRO
- Use of concentrated radiation for solar powered glass melting experiments. Solar Energy, 109, 174-182. View this article in WRRO
- Selective behaviour of dilute Fe3 + ions in silicate glasses: An Fe K-edge EXAFS and XANES study. Journal of Non-Crystalline Solids, 387, 47-56.
- Graphite immobilisation in iron phosphate glass composite materials produced by microwave and conventional sintering routes. Journal of Nuclear Materials, 454(1-3), 343-351.
- Thermal treatment of simulant plutonium contaminated materials from the Sellafield site by vitrification in a blast-furnace slag. Journal of Nuclear Materials, 444(1-3), 186-199. View this article in WRRO
- Vitrification of UK intermediate level radioactive wastes arising from site decommissioning. Initial laboratory trials. GLASS TECHNOLOGY-EUROPEAN JOURNAL OF GLASS SCIENCE AND TECHNOLOGY PART A, 54(1), 1-19.
- Evolution of the modulus and hardness of the tin and air sides of float glass as a function of hydration time. GLASS TECHNOLOGY-EUROPEAN JOURNAL OF GLASS SCIENCE AND TECHNOLOGY PART A, 54(1), 36-41.
- The effect of γ-radiation on mechanical properties of model UK nuclear waste glasses. Materials Research Society Symposium Proceedings, 1518, 41-46.
- The use of high durability alumino-borosilicate glass for the encapsulation of High Temperature Reactor (HTR) fuel. Materials Research Society Symposium Proceedings, 1518, 3-8.
- Formation of alteration products during dissolution of vitrified ILW in a high-pH calcium-rich solution. Journal of Nuclear Materials, 442(1-3), 33-45.
- The effect of uranium oxide additions on the structure of alkali borosilicate glasses. Journal of Non-Crystalline Solids, 378, 282-289.
- Encapsulation of TRISO particle fuel in durable soda-lime-silicate glasses. Journal of Nuclear Materials.
- Dissolution of vitrified wastes in a high-pH calcium-rich solution. Journal of Nuclear Materials, 435(1-3), 112-122.
- Chemical durability of vitrified wasteforms: Effects of pH and solution composition. Mineralogical Magazine, 76(8), 2919-2930.
- Smart composite materials for self-sensing and self-healing. PLASTICS RUBBER AND COMPOSITES, 41(4-5), 215-224.
- Vitrification of UK intermediate level radioactive wastes arising from site decommissioning: Property modelling and selection of candidate host glass compositions. Glass Technology: European Journal of Glass Science and Technology Part A, 53(3), 83-100.
- The effects of γ-radiation on model vitreous wasteforms intended for the disposal of intermediate and high level radioactive wastes in the United Kingdom. Journal of Nuclear Materials, 429(1-3), 353-367.
- The effects of γ-radiation on model vitreous wasteforms intended for the disposal of intermediate and high level radioactive wastes in the United Kingdom. Journal of Nuclear Materials.
- Fractographic analysis of epoxy coated glass. Ceramics International, 38(3), 2543-2549.
- Optical self-sensing of impact damage in composites using E-glass cloth. Smart Materials and Structures, 21(4).
- The Liquidus Temperature of Nuclear Waste Glasses: An International Round-Robin Study. INTERNATIONAL JOURNAL OF APPLIED GLASS SCIENCE, 2(4), 321-333.
- Corrosion of glass contact refractories for the vitrification of radioactive wastes: a review. INT MATER REV, 56(4), 226-242.
- Predicting the preference for charge compensation in silicate glasses. PHYS CHEM GLASSES-B, 52(2), 64-67.
- Composition-structure relationships in simplified nuclear waste glasses: 1. Mixed alkali borosilicate glasses. Journal of the American Ceramic Society, 94(1), 151-159.
- Modelling the strengthening of glass using epoxy based coatings. Journal of the European Ceramic Society, 31(15), 2783-2791.
- CHARACTERISATION OF THERMO-MECHANICAL PROPERTIES OF MgO-Al2O3-SiO2 GLASS CERAMIC WITH DIFFERENT HEAT TREATMENT TEMPERATURES. Journal of Materials Science.
- Mechanical properties of nuclear waste glasses. Journal of Nuclear Materials, 408(2), 188-193.
- Composition-structure relationships in simplified nuclear waste glasses: 2. the effect of ZrO2 additions. Journal of the American Ceramic Society, 94(1), 78-85.
- The structural role of Zr within alkali borosilicate glasses for nuclear waste immobilisation. Journal of Non-Crystalline Solids, 357(7), 1647-1656.
- Vitrification of legacy and intermediate level radioactive wastes: Opportunities and challenges. Nuclear Future, 6(5), 250-254.
- Comparison of glass hydration layer thickness measured by transmission electron microscopy and nanoindentation. MATER LETT, 64(9), 1041-1044.
- A multi-spectroscopic investigation of sulphur speciation in silicate glasses and slags. GLASS TECHNOL-PART A, 51(2), 63-80.
- CeO2 nano-precipitation in borosilicate glasses: A redox study using EELS. J EUR CERAM SOC, 30(4), 831-838.
- Surface hydration and nanoindentation of silicate glasses. J NON-CRYST SOLIDS, 356(2), 102-108. View this article in WRRO
- Mechanical properties of silicate glasses as a function of composition. Journal of Non-Crystalline Solids, 356(44-49), 2417-2423.
- Concerning the use of standards for identifying coordination environments in glasses. Journal of Physics: Conference Series, 217(1).
- A novel indentation based method to determine the threshold stress intensity factor for sub-critical crack growth in glass. Glass Technology: European Journal of Glass Science and Technology Part A, 51(4), 156-160.
- Calibrating a nanoindenter for very shallow depth indentation using equivalent contact radius. PHILOS MAG, 90(13), 1819-1832.
- A Micromechanical Model to Predict Mechanical Durability of Glass Multifilament Bundles in Rubber Composite. J ENG MATER-T ASME, 132(1).
- Effects of modifier additions on the thermal properties, chemical durability, oxidation state and structure of iron phosphate glasses. J NON-CRYST SOLIDS, 355(28-30), 1526-1538.
- Elastic properties of some bulk metallic glasses. J NON-CRYST SOLIDS, 355(6), 335-339.
- The immobilisation of a chloride containing actinide waste surrogate in calcium aluminosilicate glasses. Ceramic Transactions, 207, 69-80.
- Structural studies of iron in vitrified toxic wastes. Hyperfine Interactions, 192(1-3), 37-42.
- Nuclear Waste Vitrification and Chemical Durability, Advanced Structured Materials (pp. 243-263). Springer Nature Singapore
- Mechanical Properties of Inorganic Glasses (pp. 379-390). Wiley
- Soda-Lime-Silica Glasses, Reference Module in Materials Science and Materials Engineering Elsevier
- Soda-Lime-Silica Glasses, Encyclopedia of Materials: Technical Ceramics and Glasses: Volume 1-3 (pp. V2-483-V2-495).
- Structural studies of iron in vitrified toxic wastes, ISIAME 2008 (pp. 539-544). Springer Berlin Heidelberg
Conference proceedings papers
- The HADES facility for high activity decommissioning engineering & science: part of the UK national nuclear user facility. IOP Conference Series: Materials Science and Engineering, Vol. 818. Manchester, UK, 4 February 2020 - 5 February 2020. View this article in WRRO
- Evaluation of Novel Leaching Assessment for Nuclear Waste Glasses. Proceedings of Waste Management 2018
- Interactions between Simulant Vitrified Nuclear Wastes and high pH solutions: A Natural Analogue Approach. MRS Advances, Vol. 2(12) (pp 669-674) View this article in WRRO
- Practical demonstration of fibre evanescent wave spectroscopy for cure monitoring of epoxy resins using novel h-glass fibres. ICCM International Conferences on Composite Materials, Vol. 2015-July
- MoO3 incorporation in alkaline earth aluminosilicate glasses. MRS Proceedings, Vol. 1744 (pp 67-72)
- Structural glass fibres for optical damage, cure and moisture ingress sensing in advanced reinforced polymer composites. ICCM International Conferences on Composite Materials, Vol. 2013-July (pp 4052-4060)
- Electron beam induced structure changes in borosilicate and borophosphate glasses: a comparison by energy loss spectroscopy. PHYSICS AND CHEMISTRY OF GLASSES-EUROPEAN JOURNAL OF GLASS SCIENCE AND TECHNOLOGY PART B, Vol. 50(6) (pp 378-383)
- Incorporation and speciation of sulphur in glasses for waste immobilisation. GLASS TECHNOLOGY-EUROPEAN JOURNAL OF GLASS SCIENCE AND TECHNOLOGY PART A, Vol. 50(3) (pp 135-138)
- Structural studies of iron in vitrified toxic wastes. ISIAME 2008 (pp 539-544)
- Glass Development for Vitrification of Wet Intermediate Level Waste (WILW) From Decommissioning of the Hinkley Point 'A' Site. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXXII, Vol. 1124 (pp 161-166)
- Chemical Monitoring of Composite Matrices by Evanescent Wave Spectroscopy. EMBODING INTELLIGENCE IN STRUCTURES AND INTEGRATED SYSTEMS, Vol. 56 (pp 297-302)
- Teaching interests
As well as being an active researcher Russell makes significant contributions to learning and teaching within the Department of Materials Science and Engineering and the Faculty of Engineering. He is currently Head of the Interdisciplinary Programmes Office (IPO) in the Faculty of Engineering.
This is the unit responsible for the administration of the cross-Faculty degrees Aerospace Engineering, Bioengineering and MEng Engineering as well as the Science & Engineering Foundation Year. He is also Director of Learning and Teaching within Materials Science & Engineering.
Russell’s teaching, particularly in glasses on which he delivers a specialist Masters level module (MAT4442), is informed by his research interests. He is also in charge of Amrophous materials Industrial Training Programme (MAT3335).
He currently contributes to first-year undergraduate modules for Materials Science & Engineering students and Aerospace Engineering students on the mechanical properties of materials (MAT1730 and MEC192) and a Masters module on heat and materials (MAT6667/9).
Russell also contributes to a first-year option on materials and the environment (MAT1920).