Imperial College London

DrMichaelOjovan

Faculty of EngineeringDepartment of Materials

Visiting Professor
 
 
 
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m.ojovan Website CV

 
 
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Location

 

Royal School of MinesSouth Kensington Campus

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Summary

 

Publications

Publication Type
Year
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260 results found

Drace Z, Ojovan MI, Samanta SK, 2022, Challenges in Planning of Integrated Nuclear Waste Management, Sustainability (Switzerland), Vol: 14

Planning for integrated nuclear waste management (INWM) entails consideration of all generated waste from energy generation, nuclear fuel cycle and institutional facilities as well as waste from decommissioning and remediation of nuclear facilities, legacy waste, and eventual accident waste and requires establishment of different planning scenarios as well as control milestones to allow for adequate flexibility to address inevitable changes. An early assessment of waste management needs from development and use of advanced reactors and innovative nuclear fuel cycles is required to aid design and operation of such facilities as well as to understand their impact to overall waste management planning. Major prerequisites for approach to planning and establishment of INWM plans are discussed briefly. It is pointed out that five most important challenges in establishing and implementing the INWM plan needs to be addressed: (i) inventory; (ii) time frame for an integrated plan; (iii) assessment of facility needs; (iv) costs estimation (life-cycle cost analyses) and (v) funding and financing. The INWM has to promote strategic thinking within a broad framework resulting in a sustainable and sensible outcome for nuclear waste management at a strategic and national level.

Journal article

Ojovan MI, Steinmetz HJ, 2022, Approaches to Disposal of Nuclear Waste, Energies, Vol: 15

We present a concise mini overview on the approaches to the disposal of nuclear waste currently used or deployed. The disposal of nuclear waste is the end point of nuclear waste management (NWM) activities and is the emplacement of waste in an appropriate facility without the intention to retrieve it. The IAEA has developed an internationally accepted classification scheme based on the end points of NWM, which is used as guidance. Retention times needed for safe isolation of waste radionuclides are estimated based on the radiotoxicity of nuclear waste. Disposal facilities usually rely on a multi-barrier defence system to isolate the waste from the biosphere, which comprises the natural geological barrier and the engineered barrier system. Disposal facilities could be of a trench type, vaults, tunnels, shafts, boreholes, or mined repositories. A graded approach relates the depth of the disposal facilities’ location with the level of hazard. Disposal practices demonstrate the reliability of nuclear waste disposal with minimal expected impacts on the environment and humans.

Journal article

Yudintsev SV, Nickolsky MS, Ojovan MI, Stefanovsky OI, Nikonov BS, Ulanova ASet al., 2022, Zirconolite polytypes and murataite polysomes in matrices for the REE-actinide fraction of HLW, Materials, Vol: 15, ISSN: 1996-1944

Electron backscatter diffraction (EBSD) has been used for more than 30 years for analyzing the structure of minerals and artificial substances. In recent times, EBSD has been widely applied for investigation of irradiated nuclear fuel and matrices for the immobilization of radioactive waste. The combination of EBSD and scanning electron microscopy (SEM/EDS) methods allows researchers to obtain simultaneously data on a specimen's local composition and structure. The article discusses the abilities of SEM/EDS and EBSD techniques to identify zirconolite polytype modifications and members of the polysomatic murataite-pyrochlore series in polyphase ceramic matrices, with simulations of Pu (Th) and the REE-actinide fraction (Nd) of high-level radioactive waste.

Journal article

Ojovan MI, 2022, Challenges in the long-term behaviour of highly radioactive materials, Sustainability, Vol: 14, Pages: 2445-2445, ISSN: 2071-1050

Journal article

Ojovan MI, Louzguine-Luzgin DV, 2022, On Structural Rearrangements during the Vitrification of Molten Copper, MATERIALS, Vol: 15

Journal article

Tournier RF, Ojovan MI, 2022, Multiple Melting Temperatures in Glass-Forming Melts, SUSTAINABILITY, Vol: 14

Journal article

Tournier RF, Ojovan MI, 2021, Comments about a recent publication entitled “Improving glass forming ability of off-eutectic metallic glass formers by manipulating primary crystallization reactions”, Scripta Materialia, Vol: 205, Pages: 114039-114039, ISSN: 1359-6462

Journal article

Ojovan MI, Tournier RF, 2021, On Structural Rearrangements Near the Glass Transition Temperature in Amorphous Silica., Materials (Basel), Vol: 14, ISSN: 1996-1944

The formation of clusters was analyzed in a topologically disordered network of bonds of amorphous silica (SiO2) based on the Angell model of broken bonds termed configurons. It was shown that a fractal-dimensional configuron phase was formed in the amorphous silica above the glass transition temperature Tg. The glass transition was described in terms of the concepts of configuron percolation theory (CPT) using the Kantor-Webman theorem, which states that the rigidity threshold of an elastic percolating network is identical to the percolation threshold. The account of configuron phase formation above Tg showed that (i) the glass transition was similar in nature to the second-order phase transformations within the Ehrenfest classification and that (ii) although being reversible, it occurred differently when heating through the glass-liquid transition to that when cooling down in the liquid phase via vitrification. In contrast to typical second-order transformations, such as the formation of ferromagnetic or superconducting phases when the more ordered phase is located below the transition threshold, the configuron phase was located above it.

Journal article

Nabakhtiani G, Giorgadze I, Ojovan MI, 2021, IAEA-Assisted Treatment of Liquid Radioactive Waste at the Saakadze Site in Georgia, PROCESSES, Vol: 9

Journal article

Kochkin B, Malkovsky V, Yudintsev S, Petrov V, Ojovan Met al., 2021, Problems and perspectives of borehole disposal of radioactive waste, Progress in Nuclear Energy, Vol: 139, Pages: 1-9, ISSN: 0149-1970

An overview is given of status of projects for the disposal of radioactive waste in very deep boreholes in crystalline rocks which demonstrates all main pros and cons of this technology. New opportunities offered by drilling long horizontal drillholes in ductile formations can provide the basis for projects that have the potential to overcome many of the disadvantages of deep boreholes. The concept of disposal in horizontal drillholes brings together the technologies of borehole and mined repositories using the advantages of both, and therefore deserves an expert discussion at international level.

Journal article

Tournier RF, Ojovan MI, 2021, Dewetting temperatures of prefrozen and grafted layers in solid ultrathin films viewed as melt-memory effects, Physica B: Condensed Matter, Vol: 611, Pages: 1-10, ISSN: 0921-4526

Undercooled phase exists behind glass phase with superheated medium-range order between Tg and Tn+ > Tm. The ordered volume fraction stays equal to the percolation threshold F ≅ 0.15 of broken bonds up to Tn+. The difference ΔTg between Tg(bulk) of films with thickness (h > h0) and Tg(h) of ultrathin films of thickness (h < h0) is a linear function of (h-ho). Dense layer with minimum thickness hr is grafted against substrate by isothermal annealing, rinsed to reduce film thickness below hr/F, and finally dewetted at Tg. Similar thickness prepared and annealed near Tm and heated above Tm contains residual crystallized layer dewetting at Tn+. The prefrozen layer reproduces the glassy grafted layer in a crystallized state up to Tn+. Melting heat and melting temperature Tm are linear functions of h for h < h0. Prefrozen layers are due to melt-memories leading to new scenarios of crystallization.

Journal article

Tournier RF, Ojovan MI, 2021, Building and breaking bonds by homogenous nucleation in glass-forming melts leading to transitions in three liquid states, Materials, Vol: 14, ISSN: 1996-1944

The thermal history of melts leads to three liquid states above the melting temperatures Tm containing clusters—bound colloids with two opposite values of enthalpy +Δεlg × ΔHm and −Δεlg × ΔHm and zero. All colloid bonds disconnect at Tn+ > Tm and give rise in congruent materials, through a first-order transition at TLL = Tn+, forming a homogeneous liquid, containing tiny superatoms, built by short-range order. In non-congruent materials, (Tn+) and (TLL) are separated, Tn+ being the temperature of a second order and TLL the temperature of a first-order phase transition. (Tn+) and (TLL) are predicted from the knowledge of solidus and liquidus temperatures using non-classical homogenous nucleation. The first-order transition at TLL gives rise by cooling to a new liquid state containing colloids. Each colloid is a superatom, melted by homogeneous disintegration of nuclei instead of surface melting, and with a Gibbs free energy equal to that of a liquid droplet containing the same magic atom number. Internal and external bond number of colloids increases at Tn+ or from Tn+ to Tg. These liquid enthalpies reveal the natural presence of colloid–colloid bonding and antibonding in glass-forming melts. The Mpemba effect and its inverse exist in all melts and is due to the presence of these three liquid states.

Journal article

Ojovan MI, 2021, The Modified Random Network (MRN) model within the Configuron Percolation Theory (CPT) of glass transition, Ceramics, Vol: 4, Pages: 121-134, ISSN: 2571-6131

A brief overview is presented of the modified random network (MRN) model in glass science emphasizing the practical outcome of its use. Then, the configuron percolation theory (CPT) of glass–liquid transition is concisely outlined, emphasizing the role of the actual percolation thresholds observed in a complex system. The MRN model is shown as an important tool enabling to understand within CPT the reduced percolation threshold in complex oxide systems.

Journal article

Ojovan M, 2021, Glass formation, Encyclopedia of Glass Science, Technology, History, and Culture, Editors: Richet, Publisher: Wiley

Book chapter

Tournier RF, Ojovan MI, 2021, Undercooled phase behind the glass phase with superheated medium-range order above glass transition temperature, Physica B: Condensed Matter, Vol: 602, Pages: 1-17, ISSN: 0921-4526

Rapidly quenched glass formers are amorphous and transformed into glass phases by relaxing enthalpy during the first heating. Two liquids give rise, at first, to an intermediate Phase 3 below T3 < Tg respecting the entropy constraints and then, the enthalpy increases towards that of the glass phase up to Tg. The negative activation energy shows that Phase 3 is hidden behind the glassy phase acting as an intermediate invasive phase during the second cooling. Phase 3 carries a medium-range order above Tg which can be superheated above the melting temperature up to Tn+. The two-liquid state model predicts the thermodynamic properties as well as the relaxation times from liquids 1 to 2. The configuron model is successfully applied to 54 glasses explaining the transitions by percolation and an ‘ordered’ fraction equal to the critical threshold Φc = 0.15 ± 0.01 from Tg to Tn+.

Journal article

Varlakov A, Zherebtsov A, Ojovan MI, Petrov Vet al., 2021, Long-term irradiation effects in cementitious systems, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 161-180, ISBN: 9780128183298

This chapter is an overview of main processes and effects in cementitious materials which occur under the exposure of ionizing radiation. The information provided should be useful for regulators and waste managers since it shows the possibility of extending the application of such materials in immobilization of not only intermediate-level waste, but also some types of high-level waste. Cementitious materials are known to be used in nuclear industry for a long time to construct facilities exposed to high irradiation doses (pools for spent nuclear fuel, nuclear research and power reactors, high-energy particle accelerators, hot cells, high-level waste dry casks, medical facilities using nuclear systems and X-rays, etc.). These materials are convenient for immobilization of different types of liquid and solid radioactive waste. However, currently cements can be only used as matrices for low- and intermediate-level waste. This is due to the doubts about their stability toward higher radiation doses. The main results of radiation damage are typically mechanical weakening, release of hydrogen gas, and cracking that can lead to the destruction of the matrix and enhanced release of radionuclides in contact with groundwater. In this chapter, we have overviewed main effects of ionization radiation on cementitious materials and on applicability of such materials as immobilizing materials suitable for radioactive waste of higher activities.

Book chapter

Rahman ROA, Ojovan MI, 2021, Techniques to test cementitious systems through their life cycles, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 407-430, ISBN: 9780128183298

Varying techniques are used within the nuclear industry to verify SSC’s design, qualify the used cementitious materials, and inspect/oversight the quality of the fresh and hardened cementitious SSC’s. These techniques were very helpful in improving our understanding for important processes that can occur in these SSC’s under normal operating conditions and behind the design basis conditions and assist in improving the prediction of the SSC’s performance under these conditions. In this chapter, examples of different techniques that could be used to characterize cementitious materials will be introduced. The role of large-scale testing in improving the design of nuclear cementitious SSC’s will be highlighted by providing examples of these tests for reactor containment and radioactive waste packages. Nondestructive tests as inspection/oversight tools for cementitious SSC’s during construction and operational phases will be presented by overviewing different techniques used in this respect. Finally, the application of testing techniques in qualifying cementitious materials, reactor containment, and cementitious waste packages will be overviewed by presenting the qualification requirement in ACI 349 and their respective ASTM tests, the leak tests, and durability tests, respectively.

Book chapter

Rahman ROA, Ojovan MI, 2021, Innovative and conventional cementitious systems in nuclear industry-Safety aspect, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 49-87, ISBN: 9780128183298

Cementitious components, structures, and systems (SSC’s) are being used in different facilities within the nuclear industry to provide and support different operational, safety, and security functions. The main functions of these systems are to support the structural integrity of the facilities, provide shielding, support operational function, and ensure containment. Depending on the types of facility, the cementitious systems are designed to address various normal operating conditions and deviations from these conditions. This chapter introduces the role of cementitious systems in ensuring the safety of different nuclear facilities. Within this context, the hazards that exist in nuclear facilities and the nuclear safety concepts and principles will be introduced. Four facilities were selected to be presented in this chapter, namely, nuclear reactor, spent fuel storage, radioactive disposal facility, and the International Thermonuclear Experimental Reactor (ITER). For each facility, the main components will be introduced; then the international and national guidelines on safety classification and system, structure, and component categorization will be discussed; finally conventional and innovative cementitious systems will be presented.

Book chapter

Rahman ROA, Ojovan MI, 2021, Sustainability of cementitious structures, systems, and components (SSC’s): Long-term environmental stressors, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 181-232, ISBN: 9780128183298

In nuclear industry, the service life of the cementitious structures, systems, and components (SSC’s) in nuclear power plant and spent fuel storage facilities extends over several decades and in radioactive waste disposal in the range of several hundreds of years. The operational experience in these facilities proved the sustainability of these SSC’s. During normal operation, cementitious SSC’s are exposed to environmental stressors that initiate degradation processes that might affect their performances. The long-term experience in using cementitious materials provides a clear understanding for these processes and allows the prediction of the extent of the degradation damage. In this chapter, relevant environmental stressors and the degradation processes will be presented with special focus on the degradation mechanisms and the factors that affect them in Portland cement and the models that could be used to predict the degradation behavior. Durability of calcium aluminate, calcium sulfoaluminate, and magnesium phosphate cements will be highlighted. Finally, codes and standards that could be used for durability design will be overviewed.

Book chapter

Rahman ROA, Ojovan MI, 2021, Considerations in construction of nuclear cements: Materials, technologies, and management systems, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 271-295, ISBN: 9780128183298

Construction is a major preoperational phase in the facility life cycle; this phase includes different activities that are conducted in a regulated manner to ensure the safe and secure operation of the facility. This chapter is devoted to presents topics related to the construction of cementitious structures in nuclear power plants. In this respect, cement-based materials and conventional and advanced technologies related to the cement mix design, reinforcement, concrete placement, and modularization will be presented. Lessons learned from the construction activities will be discussed to highlight considerations related to project management, quality assurance, foundation constructions, and lifting.

Book chapter

Rahman ROA, Ojovan MI, 2021, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, ISBN: 9780128183298

Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, edited by Dr. Rahman and Dr. Ojovan, presents the latest knowledge and research on the management of cementitious systems within nuclear power plants. The book covers aging, development and updates on regulatory frameworks on a global scale, the development of cementitious systems for the immobilization of problematic wastes, and the decommissioning and decontamination of complex cementitious systems. The book’s editors and their team of experts combine their practical knowledge to provide the reader with a thorough understanding on the sustainability of lifecycle management of cementitious systems within the nuclear industry. Sections provide a comparative tool that presents national regulations concerning cementitious systems within nuclear power plants, check international and national evaluation results of the sustainability of different systems, help in the development of performance test procedures, and provide a guide on aging nuclear power plants and the long-term behavior of these systems in active and passive safety environments.

Book

Rahman ROA, Ojovan MI, 2021, Behavior of cementitious SSC’s in mitigating accidents, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 233-267, ISBN: 9780128183298

This chapter is devoted to present the factors that affect the sustainability of cementitious SSC’s under accidental conditions. In this respect, accidents in nuclear facilities, their scale, and initiators will be introduced. The types of hazard that can initiate an accident will be presented, and extent of damage in cementitious SSC’s in previous accidents will be reviewed. Methods to predict the behavior of cementitious SSC’s under accidental case will be summarized. Three cases were selected to be included in this chapter that represent different accidental conditions in three facilities, namely, radioactive waste disposal, dry spent fuel storage, and nuclear reactor containment. In each case, the development of the accidental conditions will be presented and models that could be used to describe the behavior of the respective cementitious SSC’s will be reviewed.

Book chapter

Rahman ROA, Ojovan MI, 2021, Preface, ISBN: 9780128183298

Book

Rahman ROA, Ojovan MI, 2021, Hydration process: Kinetics and thermodynamics, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 125-160, ISBN: 9780128183298

Cements are hydraulic binders that react with water to form solidified phases; the hydration reaction plays an important role in determining the behavior of the cementitious systems through their life cycle. This chapter addresses the hydration reaction kinetics and thermodynamics and their impacts on the properties of the cement-based systems. In this respect, the hydration reactions and their roles in determining the setting time, mechanical properties, and heat release during the hydration process will be presented by overviewing the principals and advances in studying the kinetics of alite as the main and fast reacted major unhydrated cement phase. Properties of the hydrated Portland cement-based materials will be summarized, and the factors that control the hydration process will be discussed. The focus of this section is to identify the links between the factors that affect the hydration reactions and the attained cement properties. Hydration of innovative cements including calcium aluminate cement that is used for radioactive waste conditioning and is considered as a part of the low-pH cement in geological disposal will be overviewed, and main properties of these hydrated cements will be highlighted.

Book chapter

Laraia M, Rahman ROA, Ojovan MI, 2021, Terms and glossary relevant to nuclear cementitious systems, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 629-646, ISBN: 9780128183298

Book chapter

Rahman ROA, Ojovan MI, 2021, Life cycle of nuclear cementitious structures, systems, and components, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 89-121, ISBN: 9780128183298

Cementitious SSC’s are long-lived, and their life cycle starts outside the nuclear industry and extends during the operational, closure, and postclosure phases of the nuclear facility. This chapter introduces the life cycle of the cementitious systems in active and passive safety environments by introducing to preoperational, operational, and postoperational phases. In this respect, life cycle management will be introduced and the preoperational phases of different cement-based materials will be summarized. The design phase will be highlighted with a special reference to the design phase for radioactive waste disposal facility. The international guideline and national regulations and codes and standards used to design the nuclear reactor containment will be briefed. The international atomic energy agency guidelines for the design of spent fuel storage will be presented. Finally, operational and postoperational phases will be briefly introduced.

Book chapter

Rahman ROA, Ojovan MI, 2021, Introduction to the nuclear industry sustainability, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 3-47, ISBN: 9780128183298

Nuclear industry has supported human civilization since the discovery of the radioactivity phenomena. Recently, the role of the nuclear industry was redefined to illustrate its importance in supporting the sustainable development goals adopted by the United Nations. This chapter aims to introduce to the nuclear industry, basic principles and its various applications in supporting human life and identify key aspects that can affect the sustainability of the nuclear industry. In this respect, material stability and radioactivity will be introduced and the basic principles for the application of natural and induced radioactivity will be highlighted. The development of the international radiation protection standards and the development of the integrated national regulatory framework will be summarized. The current applications of the nuclear technologies and isotopic techniques in supporting the sustainable development goals will be presented, the anticipated trends toward an improved performance are identified, and the sustainability indicators in the energy sectors will be overviewed.

Book chapter

Rahman ROA, Ojovan MI, 2021, Age management and maintenance of cementitious SSC’s during operation phase, Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, Pages: 385-405, ISBN: 9780128183298

Age management programs aims to achieve a sustainable, reliable, and economic operation and end of life cycle management of nuclear facilities. In this chapter, important considerations on the age management and maintenance of cementitious SSC’s are overviewed. In this respect, the most recent standards and guides that were issued to support the aging management, conditions assessment, and maintenance for cementitious SSC’s in nuclear power plants, being model for nuclear facilities, were presented. The lesson learned from the age-related change detection in different nuclear power plant structures and requirements for dry spent fuel storage age management were reviewed. Considerations on maintenance optimization and preventive and remedial actions were highlighted.

Book chapter

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