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
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 dif...
| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
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National Research Nuclear University (MEPhI)
2015-09-01
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| Series: | Nuclear Energy and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2452303815000138 |
| _version_ | 1818362892213288960 |
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| author | S.M. Dmitriev D.V. Doronkov A.N. Pronin D.N. Solntsev V.D. Sorokin A.E. Khrobostov |
| author_facet | S.M. Dmitriev D.V. Doronkov A.N. Pronin D.N. Solntsev V.D. Sorokin A.E. Khrobostov |
| author_sort | S.M. Dmitriev |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-12-13T21:39:48Z |
| format | Article |
| id | doaj.art-731d97ac6958422292fccb1316ecf7c7 |
| institution | Directory Open Access Journal |
| issn | 2452-3038 |
| language | English |
| last_indexed | 2024-12-13T21:39:48Z |
| publishDate | 2015-09-01 |
| publisher | National Research Nuclear University (MEPhI) |
| record_format | Article |
| series | Nuclear Energy and Technology |
| spelling | doaj.art-731d97ac6958422292fccb1316ecf7c72022-12-21T23:30:35ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382015-09-0111545910.1016/j.nucet.2015.11.012Combined numerical and experimental investigation into the coolant flow hydrodynamics and mass transfer behind the spacer grid in fuel assemblies of the floating power unit reactorS.M. DmitrievD.V. DoronkovA.N. ProninD.N. SolntsevV.D. SorokinA.E. KhrobostovThe 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.http://www.sciencedirect.com/science/article/pii/S2452303815000138floating power unitCoreFuel assembliesSpacer gridCoolant flow hydrodynamicsCoolant flow mass transferFlow friction coefficients |
| spellingShingle | S.M. Dmitriev D.V. Doronkov A.N. Pronin D.N. Solntsev V.D. Sorokin A.E. Khrobostov 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 floating power unit Core Fuel assemblies Spacer grid Coolant flow hydrodynamics Coolant flow mass transfer Flow friction coefficients |
| title | 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 |
| title_full | 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 |
| title_fullStr | 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 |
| title_full_unstemmed | 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 |
| title_short | 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 |
| title_sort | 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 |
| topic | floating power unit Core Fuel assemblies Spacer grid Coolant flow hydrodynamics Coolant flow mass transfer Flow friction coefficients |
| url | http://www.sciencedirect.com/science/article/pii/S2452303815000138 |
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