| contributor author | S. G. Bankoff | |
| contributor author | T. E. Rehm | |
| date accessioned | 2017-05-08T23:32:34Z | |
| date available | 2017-05-08T23:32:34Z | |
| date copyright | October, 1990 | |
| date issued | 1990 | |
| identifier issn | 1528-8919 | |
| identifier other | JETPEZ-26679#607_1.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/106887 | |
| description abstract | An experimental apparatus was used to simulate the annulus formed by a single tube passing through a tube support plate (TSP) in the steam generator of a PWR nuclear power plant. It was found that the extent of thin film evaporation, compared to nucleate boiling, is larger for smaller annuli, with a transition at 0.203 mm gap width to a local dryout/rewet condition. A model was developed that predicts an increasing extent of surface dryout/rewet prior to critical heat flux (CHF). A CHF correlation was developed by modification of a pool boiling CHF correlation, and the Chen (1966) correlation was modified to allow prediction of the two-phase heat transfer coefficient. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Convective Boiling in Narrow Concentric Annuli | |
| type | Journal Paper | |
| journal volume | 112 | |
| journal issue | 4 | |
| journal title | Journal of Engineering for Gas Turbines and Power | |
| identifier doi | 10.1115/1.2906213 | |
| journal fristpage | 607 | |
| journal lastpage | 613 | |
| identifier eissn | 0742-4795 | |
| keywords | Boiling | |
| keywords | Annulus | |
| keywords | Critical heat flux | |
| keywords | Pressurized water reactors | |
| keywords | Nuclear power stations | |
| keywords | Pool boiling | |
| keywords | Nucleate boiling | |
| keywords | Heat transfer coefficients | |
| keywords | Evaporation | |
| keywords | Thin films AND Boilers | |
| tree | Journal of Engineering for Gas Turbines and Power:;1990:;volume( 112 ):;issue: 004 | |
| contenttype | Fulltext | |
