The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure
The Critical Heat Flux (CHF) prediction under high pressure condition, even close to the vicinity of the critical pressure of water, is an important issue. Although there are many empirical CHF correlations, most of them have covered the pressure under 15MPa. In this study, based on the CHF experime...
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| Format: | Article |
| Language: | English |
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Wiley
2019-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2019/3695685 |
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| author | Wei Liu Jianqiang Shan Shinian Peng Guangming Jiang Yu Liu |
| author_facet | Wei Liu Jianqiang Shan Shinian Peng Guangming Jiang Yu Liu |
| author_sort | Wei Liu |
| collection | DOAJ |
| description | The Critical Heat Flux (CHF) prediction under high pressure condition, even close to the vicinity of the critical pressure of water, is an important issue. Although there are many empirical CHF correlations, most of them have covered the pressure under 15MPa. In this study, based on the CHF experiment database of upflow boiling in vertical round tube from 15MPa to the vicinity of the critical pressure of water, the Katto, Bowring, Hall-Mudawar, Alekseev correlations, and Groeneveld LUT-2006 are comparatively studied. With an error analysis of the predicted CHF to the experiment database, the prediction capability and the applicability of these correlations are evaluated and the parametric trends of CHF varying with pressure from 15MPa to critical pressure are proposed. Simultaneously, according to the characteristics of Departure from Nucleate Boiling (DNB) type CHF under high pressure condition, the constitutive correlations of Weisman & Pei model are proposed. The prediction results of three entrainment and deposition correlations of Kataoka, Celata, and Hewitt corresponding to the Dry-Out (DO) type CHF are analyzed. Based on the two improved models above, a comprehensive CHF mechanistic model under high pressure condition combining the DNB and DO type CHF is established. The verification based on the experiment database of upflow boiling in vertical round tube and the parametric trends analysis of CHF varying with thermal-hydraulic and geometric parameters are carried out. Findings of this study have a positive effect on further development of CHF prediction method for universal CHF mechanism, especially under high pressure region. |
| format | Article |
| id | doaj-art-e96b6fc4e9924f948bfbbf8ec4e34c04 |
| institution | DOAJ |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2019-01-01 |
| publisher | Wiley |
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| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-e96b6fc4e9924f948bfbbf8ec4e34c042025-08-20T03:21:08ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832019-01-01201910.1155/2019/36956853695685The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High PressureWei Liu0Jianqiang Shan1Shinian Peng2Guangming Jiang3Yu Liu4State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610213, ChinaSchool of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaState Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610213, ChinaState Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610213, ChinaState Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610213, ChinaThe Critical Heat Flux (CHF) prediction under high pressure condition, even close to the vicinity of the critical pressure of water, is an important issue. Although there are many empirical CHF correlations, most of them have covered the pressure under 15MPa. In this study, based on the CHF experiment database of upflow boiling in vertical round tube from 15MPa to the vicinity of the critical pressure of water, the Katto, Bowring, Hall-Mudawar, Alekseev correlations, and Groeneveld LUT-2006 are comparatively studied. With an error analysis of the predicted CHF to the experiment database, the prediction capability and the applicability of these correlations are evaluated and the parametric trends of CHF varying with pressure from 15MPa to critical pressure are proposed. Simultaneously, according to the characteristics of Departure from Nucleate Boiling (DNB) type CHF under high pressure condition, the constitutive correlations of Weisman & Pei model are proposed. The prediction results of three entrainment and deposition correlations of Kataoka, Celata, and Hewitt corresponding to the Dry-Out (DO) type CHF are analyzed. Based on the two improved models above, a comprehensive CHF mechanistic model under high pressure condition combining the DNB and DO type CHF is established. The verification based on the experiment database of upflow boiling in vertical round tube and the parametric trends analysis of CHF varying with thermal-hydraulic and geometric parameters are carried out. Findings of this study have a positive effect on further development of CHF prediction method for universal CHF mechanism, especially under high pressure region.http://dx.doi.org/10.1155/2019/3695685 |
| spellingShingle | Wei Liu Jianqiang Shan Shinian Peng Guangming Jiang Yu Liu The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure Science and Technology of Nuclear Installations |
| title | The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure |
| title_full | The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure |
| title_fullStr | The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure |
| title_full_unstemmed | The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure |
| title_short | The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure |
| title_sort | study of critical heat flux in upflow boiling vertical round tube under high pressure |
| url | http://dx.doi.org/10.1155/2019/3695685 |
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