Partition method of wall friction and interfacial drag force model for horizontal two-phase flows
The improvement of thermal-hydraulic analysis techniques is essential to ensure the safety and reliability of nuclear power plants. The one-dimensional two-fluid model has been adopted in state-of-the-art thermal-hydraulic system codes. Current constitutive equations used in the system codes reach a...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
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Elsevier
2022-04-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321005982 |
| _version_ | 1818774378108682240 |
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| author | Takashi Hibiki Jae Jun Jeong |
| author_facet | Takashi Hibiki Jae Jun Jeong |
| author_sort | Takashi Hibiki |
| collection | DOAJ |
| description | The improvement of thermal-hydraulic analysis techniques is essential to ensure the safety and reliability of nuclear power plants. The one-dimensional two-fluid model has been adopted in state-of-the-art thermal-hydraulic system codes. Current constitutive equations used in the system codes reach a mature level. Some exceptions are the partition method of wall friction in the momentum equation of the two-fluid model and the interfacial drag force model for a horizontal two-phase flow. This study is focused on deriving the partition method of wall friction in the momentum equation of the two-fluid model and modeling the interfacial drag force model for a horizontal bubbly flow. The one-dimensional momentum equation in the two-fluid model is derived from the local momentum equation. The derived one-dimensional momentum equation demonstrates that total wall friction should be apportioned to gas and liquid phases based on the phasic volume fraction, which is the same as that used in the SPACE code. The constitutive equations for the interfacial drag force are also identified. Based on the assessments, the Rassame-Hibiki correlation, Hibiki-Ishii correlation, Ishii-Zuber correlation, and Rassame-Hibiki correlation are recommended for computing the distribution parameter, interfacial area concentration, drag coefficient, and relative velocity covariance of a horizontal bubbly flow, respectively. |
| first_indexed | 2024-12-18T10:40:11Z |
| format | Article |
| id | doaj.art-4ac40748f6284f90bc4dbfdd57c68dae |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-18T10:40:11Z |
| publishDate | 2022-04-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-4ac40748f6284f90bc4dbfdd57c68dae2022-12-21T21:10:40ZengElsevierNuclear Engineering and Technology1738-57332022-04-0154414951507Partition method of wall friction and interfacial drag force model for horizontal two-phase flowsTakashi Hibiki0Jae Jun Jeong1Department of Mechanical Engineering, City University of Hong Kong, 83 Tat Chee Avenue, Kowloon Tong, Hong Kong, China; Corresponding author.School of Mechanical Engineering, Pusan National University, Geumjeong-gu, Busan, 46241, Republic of Korea; Corresponding author.The improvement of thermal-hydraulic analysis techniques is essential to ensure the safety and reliability of nuclear power plants. The one-dimensional two-fluid model has been adopted in state-of-the-art thermal-hydraulic system codes. Current constitutive equations used in the system codes reach a mature level. Some exceptions are the partition method of wall friction in the momentum equation of the two-fluid model and the interfacial drag force model for a horizontal two-phase flow. This study is focused on deriving the partition method of wall friction in the momentum equation of the two-fluid model and modeling the interfacial drag force model for a horizontal bubbly flow. The one-dimensional momentum equation in the two-fluid model is derived from the local momentum equation. The derived one-dimensional momentum equation demonstrates that total wall friction should be apportioned to gas and liquid phases based on the phasic volume fraction, which is the same as that used in the SPACE code. The constitutive equations for the interfacial drag force are also identified. Based on the assessments, the Rassame-Hibiki correlation, Hibiki-Ishii correlation, Ishii-Zuber correlation, and Rassame-Hibiki correlation are recommended for computing the distribution parameter, interfacial area concentration, drag coefficient, and relative velocity covariance of a horizontal bubbly flow, respectively.http://www.sciencedirect.com/science/article/pii/S1738573321005982Two-fluid modelThermal-hydraulic system codeWall friction partitionHorizontal flowInterfacial drag force |
| spellingShingle | Takashi Hibiki Jae Jun Jeong Partition method of wall friction and interfacial drag force model for horizontal two-phase flows Nuclear Engineering and Technology Two-fluid model Thermal-hydraulic system code Wall friction partition Horizontal flow Interfacial drag force |
| title | Partition method of wall friction and interfacial drag force model for horizontal two-phase flows |
| title_full | Partition method of wall friction and interfacial drag force model for horizontal two-phase flows |
| title_fullStr | Partition method of wall friction and interfacial drag force model for horizontal two-phase flows |
| title_full_unstemmed | Partition method of wall friction and interfacial drag force model for horizontal two-phase flows |
| title_short | Partition method of wall friction and interfacial drag force model for horizontal two-phase flows |
| title_sort | partition method of wall friction and interfacial drag force model for horizontal two phase flows |
| topic | Two-fluid model Thermal-hydraulic system code Wall friction partition Horizontal flow Interfacial drag force |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321005982 |
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