Dr Michael J Ojovan
MSc PhD DSc FRANS MRS SGT
School of Chemical, Materials and Biological Engineering
Associate Reader in Materials Science and Waste Immobilisation
Full contact details
School of Chemical, Materials and Biological Engineering
Sir Robert Hadfield Building
Mappin Street
91Ö±²¥
S1 3JD
- Profile
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Michael Ojovan joined the Department in 2002, having previously spent more than 20 years at The Moscow Scientific and Industrial Association "Radon", the leading radioactive waste research institution of Russian Federation. He is a Fellow of the Russian Academy of Natural Sciences and a Technical Expert of the International Atomic Energy Agency.
He is noted for his works on metal matrix immobilisation, powder metal fuels, self-sustaining vitrification, glass composite materials, the study of the long-term behaviour of cementitious, bituminous and glassy wasteforms, configuron percolation theory of glass transition and the viscosity of amorphous materials. He has published 340 peer-reviewed scientific papers, 19 IAEA documents, 42 patents and 12 books, including three editions of monograph "An introduction to nuclear waste immobilisation" by Elsevier (2005, 2014 and 2019).
- Research interests
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Main research activities:
Structure and properties of amorphous materials, Viscosity, Glass-liquid transition. Crystalline and Glassy materials for nuclear waste immobilisation, Corrosion and long term performance of glasses, Waste processing technologies. Vitrification, Cementitious wasteforms.
Earlier works:
Pulsed laser deposition of thin semiconducting films. Coherent echo-spectroscopy of aerosol and bubble systems. Metastable and strongly excited systems and condensed Rydberg matter. Diffusion-driven instability of surfaces, electrical and radiation field instability of solids. Percolation effects in poly-dispersed systems. Microstructure of emulsions with discovery of their fractal microstructure.Key projects
- Feasibility study of acoustic emission monitoring of waste immobilising materials;
- Radiation damage in glass for acoustic emission analysis;
- Glass composite wasteforms for spent clinoptilolite immobilisation;
- In situ sintering of glass composite materials in deep geological repositories;
- Effects of gamma irradiation on nuclear waste glasses;
- Melting and viscosity of silica soda lime glasses;
- Defect mediated model for glass: viscosity-temperature relationships;
- High-temperature viscosity of melt oxides based on Doremus approach;
- Crystallisation and aqueous durability of nuclear waste glasses;
- Ceramics for actinide immobilisation;
- Cement immobilisation of NORM waste;
- Processing of irradiated graphite.
- Publications
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Journal articles
- . Materials, 12(21).
- . Journal of Nuclear Materials, 484, 357-366.
- . Journal of Non-Crystalline Solids, 357(15), 2989-3001.
- Crystallisation of a simulated borosilicate high-level waste glass produced on a full-scale vitrification line. Journal of Non-Crystalline Solids.
- . Journal of Nuclear Materials, 413(1), 47-52.
- . Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, 42(4), 837-851.
- The synthesis of graphite-glass composites intended for the immobilisation of waste irradiated graphite. Journal of Nuclear Materials.
- . Journal of Hazardous Materials, 187(1-3), 296-302.
- . J NUCL MATER, 396(2-3), 264-271.
- Glassy Wasteforms for Nuclear Waste Immobilization. Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, 1-15.
- . Journal of Non-Crystalline Solids, 356(44-49), 2534-2540.
- Connectivity and glass transition in disordered oxide systems. Journal of Non-Crystalline Solids.
- . Proceedings of the ICEM2007 - 11th International Conference on Environmental Remediation and Radioactive Waste Management(PART A), 631-638.
- Acoustic emission characterisation of cementitious wasteforms under three-point bending and compression. Materials Research Society Symposium Proceedings, 1124, 357-364.
- . Materials Research Society Symposium Proceedings, 1193, 663-672.
- . Materials Research Society Symposium Proceedings, 1193, 275-282.
- Tribochemical treatment for immobilisation of radioactive wastes. Materials Research Society Symposium Proceedings, 1124, 421-426.
- Properties and composition of cemented radioactive wastes extracted from the mound-type repository. Materials Research Society Symposium Proceedings, 1124, 333-338.
- Infrared spectroscopy structural analysis of corroded nuclear waste glass K-26. Materials Research Society Symposium Proceedings, 1124, 167-173.
- . Materials Research Society Symposium Proceedings, 1107, 75-82.
- . Materials Research Society Symposium Proceedings, 1107, 245-252.
- . Entropy, 10(3), 334-364.
- . Journal of Nuclear Materials, 372(2-3), 358-366.
- . Journal of Nuclear Materials, 375(3), 347-358.
- Frequency characteristics of acoustic emission signals from cementitious wasteforms With encapsulated Al. Materials Research Society Symposium Proceedings, 985, 373-378.
- Simulation of self-irradiation of high-sodium content nuclear waste glasses. Materials Research Society Symposium Proceedings, 985, 353-358.
- The effect of waste loading on the microstructure of glass composite waste forms for the immobilisation of spent clinoptilolite. Glass Technology: European Journal of Glass Science and Technology Part A, 48(3), 124-129.
- . J Hazard Mater, 138(3), 423-432.
- . ADV APPL CERAM, 105(1), 3-12.
- . Journal of Nuclear Materials, 358(1), 57-68.
- . Journal of Physics Condensed Matter, 18(50), 11507-11520.
- Corrosion of low level vitrified radioactive waste in a loamy soil. Glass Technology: European Journal of Glass Science and Technology Part A, 47(2), 48-55.
- . Materials Research Society Symposium Proceedings, 932, 721-726.
- . Proceedings of SPIE - The International Society for Optical Engineering, 6181.
- . J NUCL MATER, 340(1), 12-24.
- Reliability of cementation technology proved via long-term field tests. Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, 2005, 1082-1087.
- ION-exchange and diffusion parameters of simulant British (Magnox, 75/25 Blended waste) and Russian (K-26) glasses at 40-60°C. Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, 2005, 637-643.
- Development of glass-composite materials for radioactive waste immobilisation. Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, 2005, 341-348.
- Role of ion exchange in performance of nuclear waste immobilising glasses. Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, 2005, 357-364.
- . Journal of Nuclear Materials, 345(1), 84-85.
- An assessment of radionuclide release inventory based on long-term field tests of nuclear waste glass K-26. Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, 2005, 319-325.
- Vitrification processes for low, intermediate radioactive and mixed wastes. Glass Technology, 46(1), 28-35.
- Fragility of oxide melts as a thermodynamic parameter. Physics and Chemistry of Glasses, 46(1), 7-11.
- . Proceedings of the Institution of Mechanical Engineers, Part E: Journal of Process Mechanical Engineering, 218(4), 261-269.
- . Journal of Nuclear Materials, 335(3), 425-432.
- . JETP Letters, 79(12), 632-634.
- . Journal of Applied Physics, 95(7), 3803-3810.
- . JETP Letters, 79(2), 85-87.
- . Materials Research Society Symposium Proceedings, 824, 333-338.
- Secondary phases on the surface of real vitrified radioactive waste disposed in a loamy soil. Materials Research Society Symposium Proceedings, 807, 139-144.
- . Materials Research Society Symposium Proceedings, 824, 339-344.
- In situ sintering of waste forms in an underground disposal environment. Materials Research Society Symposium Proceedings, 807, 949-954.
- . Materials Research Society Symposium - Proceedings, 792, 75-80.
- . Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 2, 1293-1296.
- . Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 1, 543-546.
- . Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 2, 803-809.
- . Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 3, 1801-1806.
- Self sustaining vitrification for immobilisation of radioactive and toxic waste. Glass Technology, 44(6), 218-224.
- Effect of gas generation in matrices containing Ra-226 sources. Materials Research Society Symposium - Proceedings, 757, 609-614.
- Cold crucible vitrification of NPP operational waste. Materials Research Society Symposium - Proceedings, 757, 201-206.
- Investigation of reactor graphite processing with the carbon-14 retention. Materials Research Society Symposium - Proceedings, 757, 615-620.
- New Developments in Field Studies of Low Activity Waste Glass Corrosion and Contaminant Transport. Materials Research Society Symposium - Proceedings, 757, 83-95.
- . Materials Research Society Symposium - Proceedings, 713, 713-718.
- . Materials Research Society Symposium - Proceedings, 713, 365-371.
- Modelling of the waste form behaviour in a wet near-surface repository site over extended time periods. Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 3, 1647-1650.
- Requirements for the radiation monitoring systems in highly populated areas. Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 1, 589-591.
- Self-sustaining reactions for the processing technologies of chemically stable matrices incorporating carbon and zirconium wastes. Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 2, 1035-1039.
- Management of spent sealed radioactive sources at regional facilities "Radon" in Russia. Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM, 1, 81-86.
- Simulation of the waste glass behavior in a loamy soil of the wet repository site. Materials Research Society Symposium - Proceedings, 663, 837-842.
- Thermochemical approach on treating spent ion exchange resins. Materials Research Society Symposium - Proceedings, 663, 19-26.
- Ash and soil conditioning using exothermic metallic compositions. Materials Research Society Symposium - Proceedings, 663, 65-70.
- . Journal of Nuclear Materials, 298(1-2), 174-179.
- Surface self-diffusion instability in electric fields. Materials Research Society Symposium - Proceedings, 648.
- . Materials Research Society Symposium - Proceedings, 608, 141-146.
- . Materials Research Society Symposium - Proceedings, 608, 571-576.
- . Journal De Physique. IV : JP, 10(5).
- Graphite processing with carbon retention in a waste form. Materials Research Society Symposium - Proceedings, 608, 565-570.
- Optically induced condensation of impurity excitations in transparent solids. Materials Research Society Symposium - Proceedings, 588, 303-308.
- Condensed states and their decay in a system of excited cesium atoms. Chemical Physics Reports, 18(7), 1353-1380.
- . Materials Research Society Symposium - Proceedings, 556, 239-245.
- . Materials Research Society Symposium - Proceedings, 556, 961-966.
- Open site tests on corrosion of carbon steel containers for radioactive waste forms. Materials Research Society Symposium - Proceedings, 556, 903-909.
- . Materials Research Society Symposium - Proceedings, 556, 143-146.
- . Materials Research Society Symposium - Proceedings, 506, 971-972.
- . Materials Research Society Symposium - Proceedings, 506.
- Processing and characterization of glass composites for ash immobilization. Materials Research Society Symposium - Proceedings, 465.
- . Materials Research Society Symposium - Proceedings, 506.
- . Materials Research Society Symposium - Proceedings, 506.
- Waste glass leaching and alteration under conditions of open site tests. Materials Research Society Symposium - Proceedings, 465.
- Anomalous diffusion in radwaste glasses. Materials Research Society Symposium - Proceedings, 412.
- 7-years leaching tests of NPP vitrified radioactive waste. Materials Research Society Symposium - Proceedings, 412.
- . Applied Sciences, 14(10), 4319-4319.
- . Materials, 17(8), 1822-1822.
- . Sustainability, 15(20), 15134-15134.
- . International Journal of Molecular Sciences, 24(15), 12120-12120.
- . Processes, 9(9), 1679-1679.
Conference proceedings papers
- Glassy and glass composite nuclear wasteforms. Ceramic Transactions, Vol. 227 (pp 203-216)
- ON FLUIDIZATION OF BOROSILICATE GLASSES IN INTENSE RADIATION FIELDS. PROCEEDINGS OF THE 12TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL REMEDIATION AND RADIOACTIVE WASTE MANAGEMENT 2009, VOL 1 (pp 825-834)
- TRAINING ACTIVITIES AND PERSPECTIVES IN THE RADIOACTIVE WASTE MANAGEMENT AREA OF MOSCOW SIA "RADON". PROCEEDINGS OF THE 12TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL REMEDIATION AND RADIOACTIVE WASTE MANAGEMENT 2009, VOL 2 (pp 663-668)
- SYNTHESIS OF CRYSTALLINE CERAMICS FOR ACTINIDE IMMOBILISATION. ICEM2007: PROCEEDINGS OF THE 11TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL REMEDIATION AND RADIOACTIVE WASTE MANAGEMENT, PTS A AND B (pp 255-258)
- Electron irradiation and electron tomography studies of glasses and glass nanocomposites. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXXI, Vol. 1107 (pp 239-244)
- Acoustic emission monitoring of Al corrosion in cemented-based wasteforms. Acoustic Emission Testing, Vol. 13-14 (pp 223-229)
- Role of ion exchange in the corrosion of nuclear waste glasses. Scientific Basis for Nuclear Waste Management XXIX, Vol. 932 (pp 393-400)
- Crystallisation within simulated high level waste borositicate glass. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXVIII, Vol. 824 (pp 321-326)
- Vapour phase hydration of magnox waste glass. SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXVI, Vol. 757 (pp 183-188)
- Professional activities and memberships
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- International Atomic Energy Agency (IAEA), Nuclear Engineer, 2011-2018, Technical Expert, since 1993.
- The IAEA International Predisposal Network, 2016-2018: .
- The IAEA International Project on Irradiated Graphite Processing, 2014-2018 .
- The IAEA Benchmarking System for Operational Waste of WWER NPP’s 2014-2018 .
- Abdus Salam International Centre for Theoretical Physics, Trieste, Italy: Joint ICTP-IAEA Workshops on Radiation effects in nuclear wasteforms , Fundamental of Vitrification and International Schools on Actinides Immobilisation , and Nuclear Waste Vitrification .
- Russian Academy of Natural Sciences, Fellow, since 1996.
- Associate Editor of journal Innovations in Corrosion and Materials Science.
- Editorial Board Member of International Journal of Corrosion,
Science and Technology of Nuclear Installations,
European Researcher,
Journal of Nuclear Materials,
npj Materials Degradation. - International Commission on Glass, Nuclear Waste Vitrification Technical Committee TC 05, Society of Glass Technology, and Materials Research Society.