The Experts below are selected from a list of 4044 Experts worldwide ranked by ideXlab platform
Yuri A. Kuzma-kichta - One of the best experts on this subject based on the ideXlab platform.
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Reflooding investigation on light water reactor model fuel assemblies and debris under the loss of coolant Accident simulation
High Temperature, 2017Co-Authors: S. S. Bazyuk, N. Ya. Parshin, E. B. Popov, Yuri A. Kuzma-kichta, D. M. SoldatkinAbstract:The reflooding investigations of large-scale model fuel assemblies and sphere beds under Design Basis Accident and Beyond Design Accident of Light Water Reactors WWER and PWR are presented. The generalizing correlation on the quench front velocity for model fuel rod assemblies and sphere beds was developed on the base of heat balance and Leidenfrost temperature correlation. It is shown that reflooding duration calculation results of model fuel assemblies and sphere beds are in good agreement with the experimental data.
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A balance procedure for calculating the model fuel assemblies reflooding during Design Basis Accident and its verification on PARAMETER test facility
Thermal Engineering, 2013Co-Authors: S. S. Bazyuk, N. Ya. Parshin, E. B. Popov, D. M. Soldatkin, D. N. Ignat’ev, Yuri A. Kuzma-kichtaAbstract:A balance procedure is proposed for estimating the main parameters characterizing the process of model fuel assemblies reflooding of a VVER reactor made on different scales under the conditions of a Design Basis Accident by subjecting them to bottom reflooding^1. The proposed procedure satisfactorily describes the experimental data obtained on PARAMETER test facility in the temperature range up to 1200°C. The times of fuel assemblies quenching by bottom reflooding calculated using the proposed procedure are in satisfactory agreement with the experimental data obtained on model fuel assemblies of VVER- and PWR-type reactors and can be used in developing measures aimed at enhancing the safety of nuclear power stations.
S. S. Bazyuk - One of the best experts on this subject based on the ideXlab platform.
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Reflooding investigation on light water reactor model fuel assemblies and debris under the loss of coolant Accident simulation
High Temperature, 2017Co-Authors: S. S. Bazyuk, N. Ya. Parshin, E. B. Popov, Yuri A. Kuzma-kichta, D. M. SoldatkinAbstract:The reflooding investigations of large-scale model fuel assemblies and sphere beds under Design Basis Accident and Beyond Design Accident of Light Water Reactors WWER and PWR are presented. The generalizing correlation on the quench front velocity for model fuel rod assemblies and sphere beds was developed on the base of heat balance and Leidenfrost temperature correlation. It is shown that reflooding duration calculation results of model fuel assemblies and sphere beds are in good agreement with the experimental data.
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A balance procedure for calculating the model fuel assemblies reflooding during Design Basis Accident and its verification on PARAMETER test facility
Thermal Engineering, 2013Co-Authors: S. S. Bazyuk, N. Ya. Parshin, E. B. Popov, D. M. Soldatkin, D. N. Ignat’ev, Yuri A. Kuzma-kichtaAbstract:A balance procedure is proposed for estimating the main parameters characterizing the process of model fuel assemblies reflooding of a VVER reactor made on different scales under the conditions of a Design Basis Accident by subjecting them to bottom reflooding^1. The proposed procedure satisfactorily describes the experimental data obtained on PARAMETER test facility in the temperature range up to 1200°C. The times of fuel assemblies quenching by bottom reflooding calculated using the proposed procedure are in satisfactory agreement with the experimental data obtained on model fuel assemblies of VVER- and PWR-type reactors and can be used in developing measures aimed at enhancing the safety of nuclear power stations.
E. S. Mukhtarov - One of the best experts on this subject based on the ideXlab platform.
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A combined thermal and strength analysis of the behavior of a VVER-440 reactor’s vessel during an Accident involving core melting
Thermal Engineering, 2006Co-Authors: N. G. Rassokhin, V. D. Loktionov, E. S. MukhtarovAbstract:Results from parametric calculations of the thermal and strength behavior of a VVER-440 reactor’s vessel during a beyond-Design-Basis Accident are presented. The ranges of gage pressure inside the vessel and the conditions of externally cooling the reactor with water are presented under which the corium that appears in the reactor vessel during a severe Accident can be held there for a long time.
A. V. Smirnov - One of the best experts on this subject based on the ideXlab platform.
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An investigation of the survivability of fuel-rod claddings during the first stage of the maximum Design Basis Accident at a nuclear power station with a VVER reactor
Thermal Engineering, 2006Co-Authors: G. V. Karetnikov, Yu. A. Bezrukov, A. S. Bogdanov, A. M. Trushin, V. P. Onshin, A. V. SmirnovAbstract:The survivability of single tubular cpecimens of fuel-rod claddings made of E110 and E635 alloys is experimentally investigated in the range of maximum temperature peaks 760–1450°C and pressure differences of 1–12 MPa across the cladding under conditions of the maximum rates of heating (61–227 K/s) and cooling (6–276 K/s) typical of the first stage of the maximum Design Basis Accident at an nuclear power station with a VVER reactor. The extent to which the experimental conditions simulate the standard conditions is analyzed.
D. M. Soldatkin - One of the best experts on this subject based on the ideXlab platform.
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Reflooding investigation on light water reactor model fuel assemblies and debris under the loss of coolant Accident simulation
High Temperature, 2017Co-Authors: S. S. Bazyuk, N. Ya. Parshin, E. B. Popov, Yuri A. Kuzma-kichta, D. M. SoldatkinAbstract:The reflooding investigations of large-scale model fuel assemblies and sphere beds under Design Basis Accident and Beyond Design Accident of Light Water Reactors WWER and PWR are presented. The generalizing correlation on the quench front velocity for model fuel rod assemblies and sphere beds was developed on the base of heat balance and Leidenfrost temperature correlation. It is shown that reflooding duration calculation results of model fuel assemblies and sphere beds are in good agreement with the experimental data.
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A balance procedure for calculating the model fuel assemblies reflooding during Design Basis Accident and its verification on PARAMETER test facility
Thermal Engineering, 2013Co-Authors: S. S. Bazyuk, N. Ya. Parshin, E. B. Popov, D. M. Soldatkin, D. N. Ignat’ev, Yuri A. Kuzma-kichtaAbstract:A balance procedure is proposed for estimating the main parameters characterizing the process of model fuel assemblies reflooding of a VVER reactor made on different scales under the conditions of a Design Basis Accident by subjecting them to bottom reflooding^1. The proposed procedure satisfactorily describes the experimental data obtained on PARAMETER test facility in the temperature range up to 1200°C. The times of fuel assemblies quenching by bottom reflooding calculated using the proposed procedure are in satisfactory agreement with the experimental data obtained on model fuel assemblies of VVER- and PWR-type reactors and can be used in developing measures aimed at enhancing the safety of nuclear power stations.