DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR
The last decades development of applied calculation methods of nuclear reactor thermal and hydraulic processes are marked by the rapid growth of the High Performance Computing (HPC), which contribute to the active introduction of Computational Fluid Dynamics (CFD). The use of such programs to justif...
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Belarusian National Technical University
2017-09-01
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| Series: | Приборы и методы измерений |
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| Online Access: | https://pimi.bntu.by/jour/article/view/323 |
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| author | S. M. Dmitriev A. E. Khrobostov A. A. Barinov V. G. Glavny |
| author_facet | S. M. Dmitriev A. E. Khrobostov A. A. Barinov V. G. Glavny |
| author_sort | S. M. Dmitriev |
| collection | DOAJ |
| description | The last decades development of applied calculation methods of nuclear reactor thermal and hydraulic processes are marked by the rapid growth of the High Performance Computing (HPC), which contribute to the active introduction of Computational Fluid Dynamics (CFD). The use of such programs to justify technical and economic parameters and especially the safety of nuclear reactors requires comprehensive verification of mathematical models and CFD programs. The aim of the work was the development and adaptation of a measuring system having the characteristics necessary for its application in the verification test (experimental) facility. It’s main objective is to study the processes of coolant flow mixing with different physical properties (for example, the concentration of dissolved impurities) inside a large-scale reactor model. The basic method used for registration of the spatial concentration field in the mixing area is the method of spatial conductometry. In the course of the work, a measurement complex, including spatial conductometric sensors, a system of secondary converters and software, was created. Methods of calibration and normalization of measurement results are developed. Averaged concentration fields, nonstationary realizations of the measured local conductivity were obtained during the first experimental series, spectral and statistical analysis of the realizations were carried out.The acquired data are compared with pretest CFD-calculations performed in the ANSYS CFX program. A joint analysis of the obtained results made it possible to identify the main regularities of the process under study, and to demonstrate the capabilities of the designed measuring system to receive the experimental data of the «CFD-quality» required for verification.The carried out adaptation of spatial sensors allows to conduct a more extensive program of experimental tests, on the basis of which a databank and necessary generalizations will be created. The received information allows to answer a number of questions related to scaling up the results of CFD calculations at the fullscale parameters of pressurized nuclear reactors. |
| format | Article |
| id | doaj-art-7a3f909cbd174d1a804ace02163df7d3 |
| institution | Kabale University |
| issn | 2220-9506 2414-0473 |
| language | English |
| publishDate | 2017-09-01 |
| publisher | Belarusian National Technical University |
| record_format | Article |
| series | Приборы и методы измерений |
| spelling | doaj-art-7a3f909cbd174d1a804ace02163df7d32025-02-03T05:16:49ZengBelarusian National Technical UniversityПриборы и методы измерений2220-95062414-04732017-09-018320321310.21122/2220-9506-2017-8-3-203-213280DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTORS. M. Dmitriev0A. E. Khrobostov1A. A. Barinov2V. G. Glavny3Nizhny Novgorod State Technical University named after R.E. AlekseevNizhny Novgorod State Technical University named after R.E. AlekseevNizhny Novgorod State Technical University named after R.E. AlekseevS.S. Kutateladze Institute of Thermophysics, Siberian Division of the Russian Academy of SciencesThe last decades development of applied calculation methods of nuclear reactor thermal and hydraulic processes are marked by the rapid growth of the High Performance Computing (HPC), which contribute to the active introduction of Computational Fluid Dynamics (CFD). The use of such programs to justify technical and economic parameters and especially the safety of nuclear reactors requires comprehensive verification of mathematical models and CFD programs. The aim of the work was the development and adaptation of a measuring system having the characteristics necessary for its application in the verification test (experimental) facility. It’s main objective is to study the processes of coolant flow mixing with different physical properties (for example, the concentration of dissolved impurities) inside a large-scale reactor model. The basic method used for registration of the spatial concentration field in the mixing area is the method of spatial conductometry. In the course of the work, a measurement complex, including spatial conductometric sensors, a system of secondary converters and software, was created. Methods of calibration and normalization of measurement results are developed. Averaged concentration fields, nonstationary realizations of the measured local conductivity were obtained during the first experimental series, spectral and statistical analysis of the realizations were carried out.The acquired data are compared with pretest CFD-calculations performed in the ANSYS CFX program. A joint analysis of the obtained results made it possible to identify the main regularities of the process under study, and to demonstrate the capabilities of the designed measuring system to receive the experimental data of the «CFD-quality» required for verification.The carried out adaptation of spatial sensors allows to conduct a more extensive program of experimental tests, on the basis of which a databank and necessary generalizations will be created. The received information allows to answer a number of questions related to scaling up the results of CFD calculations at the fullscale parameters of pressurized nuclear reactors.https://pimi.bntu.by/jour/article/view/323measuring systemspatial conductometrynuclear reactorcomputational fluid dynamicsturbulent flows |
| spellingShingle | S. M. Dmitriev A. E. Khrobostov A. A. Barinov V. G. Glavny DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR Приборы и методы измерений measuring system spatial conductometry nuclear reactor computational fluid dynamics turbulent flows |
| title | DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR |
| title_full | DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR |
| title_fullStr | DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR |
| title_full_unstemmed | DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR |
| title_short | DEVELOPMENT AND ADAPTATION OF VORTEX REALIZABLE MEASUREMENT SYSTEM FOR BENCHMARK TEST WITH LARGE SCALE MODEL OF NUCLEAR REACTOR |
| title_sort | development and adaptation of vortex realizable measurement system for benchmark test with large scale model of nuclear reactor |
| topic | measuring system spatial conductometry nuclear reactor computational fluid dynamics turbulent flows |
| url | https://pimi.bntu.by/jour/article/view/323 |
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