On the One-Dimensional Modeling of Vertical Upward Bubbly Flow
The one-dimensional two-fluid model approach has been traditionally used in thermal-hydraulics codes for the analysis of transients and accidents in water–cooled nuclear power plants. This paper investigates the performance of RELAP5/MOD3 predicting vertical upward bubbly flow at low velocity condit...
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| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2018-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2018/2153019 |
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| author | C. Peña-Monferrer C. Gómez-Zarzuela S. Chiva R. Miró G. Verdú J. L. Muñoz-Cobo |
| author_facet | C. Peña-Monferrer C. Gómez-Zarzuela S. Chiva R. Miró G. Verdú J. L. Muñoz-Cobo |
| author_sort | C. Peña-Monferrer |
| collection | DOAJ |
| description | The one-dimensional two-fluid model approach has been traditionally used in thermal-hydraulics codes for the analysis of transients and accidents in water–cooled nuclear power plants. This paper investigates the performance of RELAP5/MOD3 predicting vertical upward bubbly flow at low velocity conditions. For bubbly flow and vertical pipes, this code applies the drift-velocity approach, showing important discrepancies with the experiments compared. Then, we use a classical formulation of the drag coefficient approach to evaluate the performance of both approaches. This is based on the critical Weber criteria and includes several assumptions for the calculation of the interfacial area and bubble size that are evaluated in this work. A more accurate drag coefficient approach is proposed and implemented in RELAP5/MOD3. Instead of using the Weber criteria, the bubble size distribution is directly considered. This allows the calculation of the interfacial area directly from the definition of Sauter mean diameter of a distribution. The results show that only the proposed approach was able to predict all the flow characteristics, in particular the bubble size and interfacial area concentration. Finally, the computational results are analyzed and validated with cross-section area average measurements of void fraction, dispersed phase velocity, bubble size, and interfacial area concentration. |
| format | Article |
| id | doaj-art-0082cae78fd24ec8904afde205c35d44 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2018-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-0082cae78fd24ec8904afde205c35d442025-02-03T01:10:31ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832018-01-01201810.1155/2018/21530192153019On the One-Dimensional Modeling of Vertical Upward Bubbly FlowC. Peña-Monferrer0C. Gómez-Zarzuela1S. Chiva2R. Miró3G. Verdú4J. L. Muñoz-Cobo5Department of Mechanical Engineering and Construction, Universitat Jaume I, Campus del Riu Sec, 12080 Castelló de la Plana, SpainResearch Institute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Camí de Vera, s/n, 46022 València, SpainDepartment of Mechanical Engineering and Construction, Universitat Jaume I, Campus del Riu Sec, 12080 Castelló de la Plana, SpainResearch Institute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Camí de Vera, s/n, 46022 València, SpainResearch Institute for Industrial, Radiophysical and Environmental Safety, Universitat Politècnica de València, Camí de Vera, s/n, 46022 València, SpainInstitute for Energy Engineering, Universitat Politècnica de València, Camí de Vera, s/n, 46022 València, SpainThe one-dimensional two-fluid model approach has been traditionally used in thermal-hydraulics codes for the analysis of transients and accidents in water–cooled nuclear power plants. This paper investigates the performance of RELAP5/MOD3 predicting vertical upward bubbly flow at low velocity conditions. For bubbly flow and vertical pipes, this code applies the drift-velocity approach, showing important discrepancies with the experiments compared. Then, we use a classical formulation of the drag coefficient approach to evaluate the performance of both approaches. This is based on the critical Weber criteria and includes several assumptions for the calculation of the interfacial area and bubble size that are evaluated in this work. A more accurate drag coefficient approach is proposed and implemented in RELAP5/MOD3. Instead of using the Weber criteria, the bubble size distribution is directly considered. This allows the calculation of the interfacial area directly from the definition of Sauter mean diameter of a distribution. The results show that only the proposed approach was able to predict all the flow characteristics, in particular the bubble size and interfacial area concentration. Finally, the computational results are analyzed and validated with cross-section area average measurements of void fraction, dispersed phase velocity, bubble size, and interfacial area concentration.http://dx.doi.org/10.1155/2018/2153019 |
| spellingShingle | C. Peña-Monferrer C. Gómez-Zarzuela S. Chiva R. Miró G. Verdú J. L. Muñoz-Cobo On the One-Dimensional Modeling of Vertical Upward Bubbly Flow Science and Technology of Nuclear Installations |
| title | On the One-Dimensional Modeling of Vertical Upward Bubbly Flow |
| title_full | On the One-Dimensional Modeling of Vertical Upward Bubbly Flow |
| title_fullStr | On the One-Dimensional Modeling of Vertical Upward Bubbly Flow |
| title_full_unstemmed | On the One-Dimensional Modeling of Vertical Upward Bubbly Flow |
| title_short | On the One-Dimensional Modeling of Vertical Upward Bubbly Flow |
| title_sort | on the one dimensional modeling of vertical upward bubbly flow |
| url | http://dx.doi.org/10.1155/2018/2153019 |
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