The Experts below are selected from a list of 122355 Experts worldwide ranked by ideXlab platform
Vladimir Petrochenko - One of the best experts on this subject based on the ideXlab platform.
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Lead-Bismuth and Lead as Coolants for Fast Reactors
World Journal of Nuclear Science and Technology, 2020Co-Authors: Georgy Toshinsky, A. V. Dedul, O. G. Komlev, A. V. Kondaurov, Vladimir PetrochenkoAbstract:Fast reactors used lead-bismuth eutectic (LBE) and lead as Coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type of reactors can be simultaneously more safely and more cheaply. As all other Coolants, LBE and lead coolant (LC) possess the certain virtues and shortcomings. The presented report includes the comparative analysis of characteristic properties of those Coolants, their impact on reactor safety, reliability and operating characteristics. The conclusion is made about promising usage of FRs with these Coolants in future NP after the experience in operating of the prototypes of such reactors has been obtained.
Georgy Toshinsky - One of the best experts on this subject based on the ideXlab platform.
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Lead-Bismuth and Lead as Coolants for Fast Reactors
World Journal of Nuclear Science and Technology, 2020Co-Authors: Georgy Toshinsky, A. V. Dedul, O. G. Komlev, A. V. Kondaurov, Vladimir PetrochenkoAbstract:Fast reactors used lead-bismuth eutectic (LBE) and lead as Coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type of reactors can be simultaneously more safely and more cheaply. As all other Coolants, LBE and lead coolant (LC) possess the certain virtues and shortcomings. The presented report includes the comparative analysis of characteristic properties of those Coolants, their impact on reactor safety, reliability and operating characteristics. The conclusion is made about promising usage of FRs with these Coolants in future NP after the experience in operating of the prototypes of such reactors has been obtained.
A. P. Sorokin - One of the best experts on this subject based on the ideXlab platform.
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Physical Chemistry and Technology of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look
Atomic Energy, 2020Co-Authors: V. V. Alekseev, Yu. A. Kuzina, A. P. SorokinAbstract:The results of studies on the physical chemistry, mass transfer, and technology of alkali liquid-metal coolant are reported. The state of the coolant is determined by the interaction coolant-impurities-structural materials- protective gas. The impurity sources and their intensity were determined: sodium and sodium-potassium alloy – oxygen, hydrogen (tritium), carbon, products of corrosion of structural materials, nitrogen, and the protective gas, lithium- nitrogen. The following data were obtained on the impurities in the coolant: form, equilibrium concentration, solubility, reaction kinetics, and mechanisms of heterogeneous and homogeneous mass transfer. It was shown that the required concentration of the impurities in sodium and the sodium-potassium alloy guaranteeing the design-basis parameters and a low rate of corrosion of the structural materials is achieved on purification by means of cold traps. Deeper purification of Coolants in high temperature NPF intended for use in space is achieved by means of getters (hot traps). The behavior of tritium and hydrogen in the sodium loops in NPP with fast reactors was studied. A new combined system is proposed for purification from impurities in high-temperature NPF for hydrogen production at sodium temperature ~900°C.
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Use of liquid metals in nuclear and thermonuclear engineering, and in other innovative technologies
Thermal Engineering, 2014Co-Authors: V. I. Rachkov, A. D. Efanov, F. A. Kozlov, M. N. Arnol’dov, S. G. Kalyakin, N. I. Loginov, Yu. I. Orlov, A. P. SorokinAbstract:By now, a good deal of experience has been gained with using liquid metals as Coolants in nuclear power installations; extensive knowledge has been gained about the physical, thermophysical, and physicochemical properties of these Coolants; and the scientific principles and a set of methods and means for handling liquid metals as Coolants for nuclear power installations have been elaborated. Prototype and commercialgrade sodium-cooled NPP power units have been developed, including the BOR-60, BN-350, and BN-600 power units (the Soviet Union); the Rapsodie, Phenix, and Superphenix power units (France), the EBR-II power unit (the United States); and the PFR power unit (the United Kingdom). In Russia, dedicated nuclear power installations have been constructed, including those with a lead-bismuth coolant for nuclear submarines and with sodium-potassium alloy for spacecraft (the Buk and Topol installations), which have no analogs around the world. Liquid metals (primarily lithium and its alloy with lead) hold promise for use in thermonuclear power engineering, where they can serve not only as a coolant, but also as tritium-producing medium. In this article, the physicochemical properties of liquid metal Coolants, as well as practical experience gained from using them in nuclear and thermonuclear power engineering and in innovative technologies are considered, and the lines of further research works are formulated. New results obtained from investigations carried out on the Pb-Bi and Pb for the SVBR and BREST fast-neutron reactors (referred to henceforth as fast reactors) and for controlled accelerator systems are described.
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Sodium as a coolant for fast reactors
Atomic Energy, 2010Co-Authors: V. M. Poplavskii, A. D. Efanov, F. A. Kozlov, A. P. Sorokin, A. S. Korol'kov, Yu. E. ShtyndaAbstract:The results of a comparative analysis and choice of sodium as the coolant for fast reactors are presented. The facilities developed for removing impurities present in the sodium coolant and monitoring their content are described. The modeling of the mass transfer of impurities in Coolants and the development of new liquid-metal Coolants are examined. The results of an analysis of the anomalous situations in fast reactors, and methods for removing coolant residues from equipment and salvaging wastes are presented. It is shown that the technical solutions adopted provide reliable protection from accidents. New problems of sodium technology are formulated in application to the development of a new generation of fast reactors.
E. A. Motkova - One of the best experts on this subject based on the ideXlab platform.
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Simulating the corrosion of zirconium alloys in the water coolant of VVER reactors
Thermal Engineering, 2013Co-Authors: V. G. Kritskii, I. G. Berezina, E. A. MotkovaAbstract:A model for predicting the corrosion of cladding zirconium alloys depending on their composition and operating conditions is proposed. Laws of thermodynamics and chemical kinetics of the reactions through which the multicomponent zirconium alloy is oxidized in the reactor coolant constitute the physicochemical heart of the model. The developed version of the model is verified against the results obtained from tests of fuel rod claddings made of commercial-grade and experimental zirconium alloys carried out by different researchers under autoclave and reactor conditions. It is shown that the proposed model adequately describes the corrosion of alloys in Coolants used at nuclear power stations. It is determined that, owing to boiling of coolant and its acidification in a VVER-1200 reactor, Zr-1% Nb alloys with additions of iron and oxygen must be more resistant to corrosion than the commercial-grade alloy E110.
Gary Rosengarten - One of the best experts on this subject based on the ideXlab platform.
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experimental investigation of using zno nanofluids as Coolants in a pem fuel cell
International Journal of Hydrogen Energy, 2017Co-Authors: R Islam, Bahman Shabani, John Andrews, Gary RosengartenAbstract:Abstract In this paper we report on an experimental study conducted on the thermo-electrical performance of a small-scale (i.e. 2.4 kW) Proton Exchange Membrane Fuel Cell (PEMFC), in which both conventional 50/50 water-Ethylene Glycol (EG), and 50/50 water-EG based ZnO nanofluids were used as Coolants. PEMFCs are a promising alternative to Internal Combustion Engines (ICEs) for automotive applications. However, among other challenges, the large-sized cooling system of PEMFCs (i.e. the radiator) imposes a great challenge for this application. Using nanofluids as Coolants has the potential to address this challenge. Employing selected nanofluids as Coolants, with maximum 0.5 vol% nanoparticle concentration, showed no change in the electrical power outputs of the stack based on its polarisation curve, whereas the cooling capacity of the system was improved 29% compared with that while using 50/50 water-EG as coolant. The experimental investigation reported here confirmed the earlier theoretical finding that the frontal area of the radiator (i.e. used for fuel cell cooling) could be reduced by about 27% when nanofluids (0.5 vol%) replaced conventional EG/water Coolants. Using 0.5 vol% ZnO nanofluid also showed just less than 10% increase in the pumping power compared to when the conventional 50/50 water-EG was used as coolant. It is concluded in this study that up to 0.5 vol% ZnO nanofluid can be applied to the PEMFC cooling system without affecting any electrical performance of the system.