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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| 主要な著者: | , , , , |
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| フォーマット: | Artigo |
| 言語: | Inglês |
| 出版事項: |
Wiley
2019-01-01
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| シリーズ: | Science and Technology of Nuclear Installations |
| オンライン･アクセス: | http://dx.doi.org/10.1155/2019/3695685 |
| タグ: |
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