The Experts below are selected from a list of 282 Experts worldwide ranked by ideXlab platform
S. M. Dmitriev - One of the best experts on this subject based on the ideXlab platform.
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Investigating hydrodynamic characteristics and peculiarities of the Coolant Flow behind a spacer grid of a fuel rod assembly of the floating nuclear power unit
Thermophysics and Aeromechanics, 2016Co-Authors: S. M. Dmitriev, M. A. Legchanov, V. D. Sorokin, D. V. Doronkov, A. N. Pronin, D. N. Solncev, A. E. HrobostovAbstract:The results of experimental investigations of local hydrodynamics of a Coolant Flow in fuel rod assembly (FA) of KLT-40C reactor behind a plate spacer grid have been presented. The investigations were carried out on an aerodynamic rig using the gas-phase diffusive tracer test. An analysis of spatial distribution of absolute Flow velocity projections and distribution of tracer concentration allowed specifying a Coolant Flow pattern behind the plate spacer grid of the FA. On the basis of obtained experimental data the recommendations were provided to specify procedures for determining the Coolant Flow rates for the programs of cell-wise calculation of a core zone of KLT-40C reactor. Investigation results were accepted for the practical use in JSC “OKBM Afrikantov” to assess heat engineering reliability of cores of KLT-40C reactor and were included in a database for verification of CFD programs (CFD-codes).
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Experimental studies into the fluid dynamic performance of the Coolant Flow in the mixed core of the Temelin NPP VVER-1000 reactor
Nuclear Energy and Technology, 2015Co-Authors: S. M. Dmitriev, V. D. Sorokin, D. V. Doronkov, Ye.n. Polozkova, A. N. Pronin, A.ye. KhrobostovAbstract:Abstract The paper presents the results of studies into the interassembly Coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core. An aerodynamic test bench was used to study the Coolant Flow processes in a TVSA-type fuel assembly bundle. To obtain more detailed information on the Coolant Flow dynamics, a VVER-1000 reactor core fragment was selected as the test model, which comprised two segments of a TVSA-12 PLUS fuel assembly and one segment of a TVSA-T assembly with stiffening angles and an interassembly gap. The studies into the Coolant fluid dynamics consisted in measuring the velocity vector both in representative TVSA regions and inside the interassembly gap using a five-channel pneumometric probe. An analysis into the spatial distribution of the absolute Flow velocity projections made it possible to detail the TVSA spacer, mixing and combined spacer grid Flow pattern, identify the regions with the maximum transverse Coolant Flow, and determine the depth of the Coolant Flow disturbance propagation and redistribution in adjacent TVSA assemblies. The results of the studies into the interassembly Coolant interaction among the adjacent TVSA assemblies are used at OKBM Afrikantov to update the VVER-1000 core thermal-hydraulic analysis procedures and have been added to the database for verification of computational fluid dynamics (CFD) codes and for detailed cellwise analyses of the VVER-100 reactor cores.
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modeling of Coolant Flow in the fuel assembly of the reactor of a floating nuclear power plant using the logos cfd program
Journal of Engineering Physics, 2015Co-Authors: S. M. Dmitriev, M. A. Legchanov, A A Dobrov, A. E. KhrobostovAbstract:Results of computer modeling of Coolant Flow in the fuel assembly of the reactor of a floating nuclear power plant using the LOGOS CFD programs have been given. The possibility of using the obtained results to improve models built into the engineering programs of thermohydraulic calculation of nuclear-reactor cores has been considered.
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Combined numerical and experimental investigation into the Coolant Flow hydrodynamics and mass transfer behind the spacer grid in fuel assemblies of the floating power unit reactor
Nuclear Energy and Technology, 2015Co-Authors: S. M. Dmitriev, D. N. Solntsev, V. D. Sorokin, D. V. Doronkov, A. N. Pronin, A. E. KhrobostovAbstract:Abstract The results of experimental investigations into the local hydrodynamics and inter-cell mass transfer of the Coolant Flow in representative zones of the KLT-40C reactor FAs behind the plate-type spacer grid are presented. The investigations were conducted on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). A study into the spatial dispersion of the absolute Flow velocity projections and into the distribution of the tracer concentration allowed specify the Coolant Flow pattern behind the FA plate-type spacer grid of the KLT-40C reactor. The results of measuring the Flow friction coefficient in the plate-type spacer grid, depending on the Reynolds number, are presented. Based on the obtained experimental data, recommendations have been provided for updating the procedures to calculate the Coolant Flow rates for the KLT-40C reactor core by-channel codes. The results of investigating the Coolant Flow local hydrodynamics and mass transfer in the KLT-40C reactor FAs have been adopted for practical use by Afrikantov OKBM for estimating the heat-engineering reliability of the KLT-40C reactor cores and have been data based for verification of CFD codes and detailed by-channel calculation of the KLT-40C reactor core.
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combined numerical and experimental investigations of local hydrodynamics and Coolant Flow mass transfer in kvadrat type fuel assemblies of pwr reactors with mixing grids
Thermal Engineering, 2014Co-Authors: S. M. Dmitriev, A. E. Khrobostov, D. V. Doronkov, O B Samoilov, A V Varentsov, A A Dobrov, V. D. SorokinAbstract:Results of research works on studying local hydrodynamics and mass transfer for Coolant Flow in the characteristic zones of PWR reactor fuel assemblies in case of using belts of mixing spacer grids are presented. The investigations were carried out on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). Certain specific features pertinent to Coolant Flow in the fuel rod bundles of Kvadrat-type fuel assemblies were revealed during the experiments. The obtained study results were included in the database for verifying computation fluid dynamics computer codes and detailed cell-wise calculations of reactor cores with Kvadrat-type fuel assemblies. The obtained results can also be used for more exact determination of local Coolant Flow hydrodynamic and mass transfer characteristics in assessing thermal reliability of PWR reactor cores.
V. D. Sorokin - One of the best experts on this subject based on the ideXlab platform.
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Investigating hydrodynamic characteristics and peculiarities of the Coolant Flow behind a spacer grid of a fuel rod assembly of the floating nuclear power unit
Thermophysics and Aeromechanics, 2016Co-Authors: S. M. Dmitriev, M. A. Legchanov, V. D. Sorokin, D. V. Doronkov, A. N. Pronin, D. N. Solncev, A. E. HrobostovAbstract:The results of experimental investigations of local hydrodynamics of a Coolant Flow in fuel rod assembly (FA) of KLT-40C reactor behind a plate spacer grid have been presented. The investigations were carried out on an aerodynamic rig using the gas-phase diffusive tracer test. An analysis of spatial distribution of absolute Flow velocity projections and distribution of tracer concentration allowed specifying a Coolant Flow pattern behind the plate spacer grid of the FA. On the basis of obtained experimental data the recommendations were provided to specify procedures for determining the Coolant Flow rates for the programs of cell-wise calculation of a core zone of KLT-40C reactor. Investigation results were accepted for the practical use in JSC “OKBM Afrikantov” to assess heat engineering reliability of cores of KLT-40C reactor and were included in a database for verification of CFD programs (CFD-codes).
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Experimental studies into the fluid dynamic performance of the Coolant Flow in the mixed core of the Temelin NPP VVER-1000 reactor
Nuclear Energy and Technology, 2015Co-Authors: S. M. Dmitriev, V. D. Sorokin, D. V. Doronkov, Ye.n. Polozkova, A. N. Pronin, A.ye. KhrobostovAbstract:Abstract The paper presents the results of studies into the interassembly Coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core. An aerodynamic test bench was used to study the Coolant Flow processes in a TVSA-type fuel assembly bundle. To obtain more detailed information on the Coolant Flow dynamics, a VVER-1000 reactor core fragment was selected as the test model, which comprised two segments of a TVSA-12 PLUS fuel assembly and one segment of a TVSA-T assembly with stiffening angles and an interassembly gap. The studies into the Coolant fluid dynamics consisted in measuring the velocity vector both in representative TVSA regions and inside the interassembly gap using a five-channel pneumometric probe. An analysis into the spatial distribution of the absolute Flow velocity projections made it possible to detail the TVSA spacer, mixing and combined spacer grid Flow pattern, identify the regions with the maximum transverse Coolant Flow, and determine the depth of the Coolant Flow disturbance propagation and redistribution in adjacent TVSA assemblies. The results of the studies into the interassembly Coolant interaction among the adjacent TVSA assemblies are used at OKBM Afrikantov to update the VVER-1000 core thermal-hydraulic analysis procedures and have been added to the database for verification of computational fluid dynamics (CFD) codes and for detailed cellwise analyses of the VVER-100 reactor cores.
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Combined numerical and experimental investigation into the Coolant Flow hydrodynamics and mass transfer behind the spacer grid in fuel assemblies of the floating power unit reactor
Nuclear Energy and Technology, 2015Co-Authors: S. M. Dmitriev, D. N. Solntsev, V. D. Sorokin, D. V. Doronkov, A. N. Pronin, A. E. KhrobostovAbstract:Abstract The results of experimental investigations into the local hydrodynamics and inter-cell mass transfer of the Coolant Flow in representative zones of the KLT-40C reactor FAs behind the plate-type spacer grid are presented. The investigations were conducted on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). A study into the spatial dispersion of the absolute Flow velocity projections and into the distribution of the tracer concentration allowed specify the Coolant Flow pattern behind the FA plate-type spacer grid of the KLT-40C reactor. The results of measuring the Flow friction coefficient in the plate-type spacer grid, depending on the Reynolds number, are presented. Based on the obtained experimental data, recommendations have been provided for updating the procedures to calculate the Coolant Flow rates for the KLT-40C reactor core by-channel codes. The results of investigating the Coolant Flow local hydrodynamics and mass transfer in the KLT-40C reactor FAs have been adopted for practical use by Afrikantov OKBM for estimating the heat-engineering reliability of the KLT-40C reactor cores and have been data based for verification of CFD codes and detailed by-channel calculation of the KLT-40C reactor core.
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combined numerical and experimental investigations of local hydrodynamics and Coolant Flow mass transfer in kvadrat type fuel assemblies of pwr reactors with mixing grids
Thermal Engineering, 2014Co-Authors: S. M. Dmitriev, A. E. Khrobostov, D. V. Doronkov, O B Samoilov, A V Varentsov, A A Dobrov, V. D. SorokinAbstract:Results of research works on studying local hydrodynamics and mass transfer for Coolant Flow in the characteristic zones of PWR reactor fuel assemblies in case of using belts of mixing spacer grids are presented. The investigations were carried out on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). Certain specific features pertinent to Coolant Flow in the fuel rod bundles of Kvadrat-type fuel assemblies were revealed during the experiments. The obtained study results were included in the database for verifying computation fluid dynamics computer codes and detailed cell-wise calculations of reactor cores with Kvadrat-type fuel assemblies. The obtained results can also be used for more exact determination of local Coolant Flow hydrodynamic and mass transfer characteristics in assessing thermal reliability of PWR reactor cores.
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Experimental studies of hydrodynamic and mass-transfer properties of Coolant Flow in VVER fuel assemblies TVSA
Atomic Energy, 2013Co-Authors: S. M. Dmitriev, S. S. Borodin, M. A. Legchanov, D. N. Solntsev, V. D. Sorokin, A. E. KhrobostovAbstract:The results of experimental studies of the local hydrodynamics and mass transfer of Coolant in the characteristic zone of VVER fuel assemblies using mixing lattices of structurally different types are presented. These studies were performed on an aerodynamic stand by the method of impurity diffusion for several experimental scaled models. The studies were performed on a section of self-similar Flow, so that the results can be used to convert to natural conditions of Coolant Flow in the core in regular TVSA. These studies refine the local and mass-transfer characteristics of Coolant Flow in order to reduce the conservatism in the evaluation of the heat-engineering reliability of the VVER core with TVSA fuel assemblies. The results also comprise a database for verifying CFD codes and programs for cellular calculation of a VVER core.
M. A. Hazrat - One of the best experts on this subject based on the ideXlab platform.
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a review on air Flow and Coolant Flow circuit in vehicles cooling system
International Journal of Heat and Mass Transfer, 2012Co-Authors: S C Pang, Mohd Abul Kalam, Haji Hassan Masjuki, M. A. HazratAbstract:Engine cooling system plays an important role to maintain the operating temperature of engine. The Coolant circuit initiates by picking up heat at water jackets. With the pressure gradient exists in Coolant circuit, hot Coolant Flows out from engine to radiator or to bypass circuit (during cold start). The under hood air Flow carries heat away at radiator after the air Flows through numerous hood components. The Coolant Flow circuit and air Flow circuit meet each other and exchange heat at radiator. Extensive researches are carried out to study vehicles’ cooling system extensively either numerically or experimentally. The research covers many individual topics which include numerical modelling of engine cooling system, under hood air Flow, heat transfer at water jacket, heat transfer at radiator and Coolants’ after-boiling phenomenon.
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A review on air Flow and Coolant Flow circuit in vehicles' cooling system
International Journal of Heat and Mass Transfer, 2012Co-Authors: S C Pang, Mohd Abul Kalam, Haji Hassan Masjuki, M. A. HazratAbstract:Engine cooling system plays an important role to maintain the operating temperature of engine. The Coolant circuit initiates by picking up heat atwater jackets. With the pressure gradient exists in Coolant circuit, hot Coolant Flows out from engine to radiator or to bypass circuit (during cold start). The under hood air Flow carries heat away at radiator after the air Flows through numerous hood components. The Coolant Flow circuit and air Flow circuit meet each other and exchange heat at radiator. Extensive researches are carried out to study vehicles' cooling system extensively either numerically or experimentally. The research covers many individual topics which include numerical modelling of engine cooling system, under hood air Flow, heat transfer at water jacket, heat transfer at radiator and Coolants' after-boiling phenomenon. © 2012 Elsevier Ltd. All rights reserved.
A. E. Khrobostov - One of the best experts on this subject based on the ideXlab platform.
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modeling of Coolant Flow in the fuel assembly of the reactor of a floating nuclear power plant using the logos cfd program
Journal of Engineering Physics, 2015Co-Authors: S. M. Dmitriev, M. A. Legchanov, A A Dobrov, A. E. KhrobostovAbstract:Results of computer modeling of Coolant Flow in the fuel assembly of the reactor of a floating nuclear power plant using the LOGOS CFD programs have been given. The possibility of using the obtained results to improve models built into the engineering programs of thermohydraulic calculation of nuclear-reactor cores has been considered.
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Combined numerical and experimental investigation into the Coolant Flow hydrodynamics and mass transfer behind the spacer grid in fuel assemblies of the floating power unit reactor
Nuclear Energy and Technology, 2015Co-Authors: S. M. Dmitriev, D. N. Solntsev, V. D. Sorokin, D. V. Doronkov, A. N. Pronin, A. E. KhrobostovAbstract:Abstract The results of experimental investigations into the local hydrodynamics and inter-cell mass transfer of the Coolant Flow in representative zones of the KLT-40C reactor FAs behind the plate-type spacer grid are presented. The investigations were conducted on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). A study into the spatial dispersion of the absolute Flow velocity projections and into the distribution of the tracer concentration allowed specify the Coolant Flow pattern behind the FA plate-type spacer grid of the KLT-40C reactor. The results of measuring the Flow friction coefficient in the plate-type spacer grid, depending on the Reynolds number, are presented. Based on the obtained experimental data, recommendations have been provided for updating the procedures to calculate the Coolant Flow rates for the KLT-40C reactor core by-channel codes. The results of investigating the Coolant Flow local hydrodynamics and mass transfer in the KLT-40C reactor FAs have been adopted for practical use by Afrikantov OKBM for estimating the heat-engineering reliability of the KLT-40C reactor cores and have been data based for verification of CFD codes and detailed by-channel calculation of the KLT-40C reactor core.
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combined numerical and experimental investigations of local hydrodynamics and Coolant Flow mass transfer in kvadrat type fuel assemblies of pwr reactors with mixing grids
Thermal Engineering, 2014Co-Authors: S. M. Dmitriev, A. E. Khrobostov, D. V. Doronkov, O B Samoilov, A V Varentsov, A A Dobrov, V. D. SorokinAbstract:Results of research works on studying local hydrodynamics and mass transfer for Coolant Flow in the characteristic zones of PWR reactor fuel assemblies in case of using belts of mixing spacer grids are presented. The investigations were carried out on an aerodynamic rig using the admixture diffusion method (the tracer-gas method). Certain specific features pertinent to Coolant Flow in the fuel rod bundles of Kvadrat-type fuel assemblies were revealed during the experiments. The obtained study results were included in the database for verifying computation fluid dynamics computer codes and detailed cell-wise calculations of reactor cores with Kvadrat-type fuel assemblies. The obtained results can also be used for more exact determination of local Coolant Flow hydrodynamic and mass transfer characteristics in assessing thermal reliability of PWR reactor cores.
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Experimental studies of hydrodynamic and mass-transfer properties of Coolant Flow in VVER fuel assemblies TVSA
Atomic Energy, 2013Co-Authors: S. M. Dmitriev, S. S. Borodin, M. A. Legchanov, D. N. Solntsev, V. D. Sorokin, A. E. KhrobostovAbstract:The results of experimental studies of the local hydrodynamics and mass transfer of Coolant in the characteristic zone of VVER fuel assemblies using mixing lattices of structurally different types are presented. These studies were performed on an aerodynamic stand by the method of impurity diffusion for several experimental scaled models. The studies were performed on a section of self-similar Flow, so that the results can be used to convert to natural conditions of Coolant Flow in the core in regular TVSA. These studies refine the local and mass-transfer characteristics of Coolant Flow in order to reduce the conservatism in the evaluation of the heat-engineering reliability of the VVER core with TVSA fuel assemblies. The results also comprise a database for verifying CFD codes and programs for cellular calculation of a VVER core.
S C Pang - One of the best experts on this subject based on the ideXlab platform.
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a review on air Flow and Coolant Flow circuit in vehicles cooling system
International Journal of Heat and Mass Transfer, 2012Co-Authors: S C Pang, Mohd Abul Kalam, Haji Hassan Masjuki, M. A. HazratAbstract:Engine cooling system plays an important role to maintain the operating temperature of engine. The Coolant circuit initiates by picking up heat at water jackets. With the pressure gradient exists in Coolant circuit, hot Coolant Flows out from engine to radiator or to bypass circuit (during cold start). The under hood air Flow carries heat away at radiator after the air Flows through numerous hood components. The Coolant Flow circuit and air Flow circuit meet each other and exchange heat at radiator. Extensive researches are carried out to study vehicles’ cooling system extensively either numerically or experimentally. The research covers many individual topics which include numerical modelling of engine cooling system, under hood air Flow, heat transfer at water jacket, heat transfer at radiator and Coolants’ after-boiling phenomenon.
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A review on air Flow and Coolant Flow circuit in vehicles' cooling system
International Journal of Heat and Mass Transfer, 2012Co-Authors: S C Pang, Mohd Abul Kalam, Haji Hassan Masjuki, M. A. HazratAbstract:Engine cooling system plays an important role to maintain the operating temperature of engine. The Coolant circuit initiates by picking up heat atwater jackets. With the pressure gradient exists in Coolant circuit, hot Coolant Flows out from engine to radiator or to bypass circuit (during cold start). The under hood air Flow carries heat away at radiator after the air Flows through numerous hood components. The Coolant Flow circuit and air Flow circuit meet each other and exchange heat at radiator. Extensive researches are carried out to study vehicles' cooling system extensively either numerically or experimentally. The research covers many individual topics which include numerical modelling of engine cooling system, under hood air Flow, heat transfer at water jacket, heat transfer at radiator and Coolants' after-boiling phenomenon. © 2012 Elsevier Ltd. All rights reserved.