Michael I. Ojovan is Chief Editor of journal “Science and Technology of Nuclear Installations”. He has been Nuclear Engineer of International Atomic Energy Agency (IAEA), works as Professor of Imperial College London and Associate Reader at the University of Sheffield, UK, Leading Scientist of Lomonosov Moscow State University and Institute of Geology of Ore Deposits, Petrography, Mineralogy and Geochemistry (IGEM) of Russian Academy of Sciences. He has published 15 monographs including the “Handbook of Advanced Radioactive Waste Conditioning Technologies” and three editions of “An Introduction to Nuclear Waste Immobilisation” by Elsevier. He has founded and led the IAEA International Predisposal Network (IPN) and the IAEA International Project on Irradiated Graphite Processing (GRAPA). M. Ojovan is known for the connectivity-percolation theory of glass transition, Sheffield model of viscosity of glasses and melts, theoretical bases of condensed Rydberg matter, metallic and glass-composite materials for nuclear waste immobilisation, and self-sinking capsules to investigate Earth’ deep interior. Web page: http://www.imperial.ac.uk/people/m.ojovan Web page: https://sciprofiles.com/profile/httpwwwimperialacukpeoplemojovan
Abstract Mass spectrometric analysis of newly formed surface on breaking a sodium borosilicate gl... more Abstract Mass spectrometric analysis of newly formed surface on breaking a sodium borosilicate glass bar revealed its significant enrichment with sodium, slight higher content of boron and depletion in Mg, Ca, Al, Ti and Mo compared the initial glass surface. This conforms to recent low energy ion observation of Almeida et al. and evidences on modified random network microstructure and medium range order in silicate glasses. The glass investigated was a borosilicate glass (wt.%) 48.2·SiO2 7.5·B2O3 2.5 ∙ Al2O3 1.5 ∙ Fe2O3 15.5 ∙ CaO 16.1 ∙ Na2O 8.7 ∙ Misc which is a simulant of high-sodium nuclear waste glass K-26. The glass bar after annealing was broken openly in air using a hammer. Laser Ablation System New Wave UP 213 coupled with laser ablation-inductively coupled plasma-mass spectrometry ICP-MS 4500 system was used for analyses. The mass spectrometric analysis comprised the elements: 95Mo, 11B, 23Na, 24Mg, 27Al, 30Si, 43Ca, and 47Ti. The laser ablation was taken samples from the freshly formed surface as well as from its initial surface of glass bars. The relative changes of average normalised mass spectrometric signal intensities on formation of a new glass surface were as follows: 1.14 for 11B, 1.35 for 23Na, 0.8 for 24Mg, 0.83 for 27Al, 0.75 for 43Ca. 0.76 for 47Ti and 0.77 for 95Mo. These data evidence on modified random network microstructure and show that the glass breaks along weaker ionic percolating channels formed by alkalis so resulting in alkali enriched surfaces. The results obtained may be useful for configuron percolation theory of glass transition, interpretation and controlling glass corrosion, as well as for potential applications in medicine and biology.
Handbook of Advanced Radioactive Waste Conditioning Technologies, 2011
Abstract: The generic approach of radioactive waste management is to use more reliable natural an... more Abstract: The generic approach of radioactive waste management is to use more reliable natural and engineered barrier systems for more hazardous waste. The guidance for treatment and conditioning of radioactive waste is based on data obtained on waste material characterization. Characterization of radioactive waste gives important waste material parameters and enables its classification according to national regulations. Although classification schemes are country dependent, there is a generic consensus that end points (e.g. storage and disposal) and conditioning methods (e.g. immobilization and packaging) depend on the level of radioactivity and radionuclide lifetime. Radioactive waste processing routes are specified herein using the new International Atomic Energy Agency (IAEA) radioactive waste classification scheme which is based on long-term safety of waste.
ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B, 2011
The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste manag... more The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and contai...
Abstract Mass spectrometric analysis of newly formed surface on breaking a sodium borosilicate gl... more Abstract Mass spectrometric analysis of newly formed surface on breaking a sodium borosilicate glass bar revealed its significant enrichment with sodium, slight higher content of boron and depletion in Mg, Ca, Al, Ti and Mo compared the initial glass surface. This conforms to recent low energy ion observation of Almeida et al. and evidences on modified random network microstructure and medium range order in silicate glasses. The glass investigated was a borosilicate glass (wt.%) 48.2·SiO2 7.5·B2O3 2.5 ∙ Al2O3 1.5 ∙ Fe2O3 15.5 ∙ CaO 16.1 ∙ Na2O 8.7 ∙ Misc which is a simulant of high-sodium nuclear waste glass K-26. The glass bar after annealing was broken openly in air using a hammer. Laser Ablation System New Wave UP 213 coupled with laser ablation-inductively coupled plasma-mass spectrometry ICP-MS 4500 system was used for analyses. The mass spectrometric analysis comprised the elements: 95Mo, 11B, 23Na, 24Mg, 27Al, 30Si, 43Ca, and 47Ti. The laser ablation was taken samples from the freshly formed surface as well as from its initial surface of glass bars. The relative changes of average normalised mass spectrometric signal intensities on formation of a new glass surface were as follows: 1.14 for 11B, 1.35 for 23Na, 0.8 for 24Mg, 0.83 for 27Al, 0.75 for 43Ca. 0.76 for 47Ti and 0.77 for 95Mo. These data evidence on modified random network microstructure and show that the glass breaks along weaker ionic percolating channels formed by alkalis so resulting in alkali enriched surfaces. The results obtained may be useful for configuron percolation theory of glass transition, interpretation and controlling glass corrosion, as well as for potential applications in medicine and biology.
Handbook of Advanced Radioactive Waste Conditioning Technologies, 2011
Abstract: The generic approach of radioactive waste management is to use more reliable natural an... more Abstract: The generic approach of radioactive waste management is to use more reliable natural and engineered barrier systems for more hazardous waste. The guidance for treatment and conditioning of radioactive waste is based on data obtained on waste material characterization. Characterization of radioactive waste gives important waste material parameters and enables its classification according to national regulations. Although classification schemes are country dependent, there is a generic consensus that end points (e.g. storage and disposal) and conditioning methods (e.g. immobilization and packaging) depend on the level of radioactivity and radionuclide lifetime. Radioactive waste processing routes are specified herein using the new International Atomic Energy Agency (IAEA) radioactive waste classification scheme which is based on long-term safety of waste.
ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B, 2011
The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste manag... more The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and contai...
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