Full metadata record
DC Field | Value | Language |
---|---|---|
dc.contributor.author | 김성중 | - |
dc.date.accessioned | 2019-12-10T20:28:30Z | - |
dc.date.available | 2019-12-10T20:28:30Z | - |
dc.date.issued | 2018-12 | - |
dc.identifier.citation | INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v. 127, pt. B, page. 182-195 | en_US |
dc.identifier.issn | 0017-9310 | - |
dc.identifier.issn | 1879-2189 | - |
dc.identifier.uri | https://www.sciencedirect.com/science/article/abs/pii/S001793101830958X?via%3Dihub | - |
dc.identifier.uri | https://repository.hanyang.ac.kr/handle/20.500.11754/121170 | - |
dc.description.abstract | The present study investigated the physical processes responsible for the variation in the boiling curve and critical heat flux (CHF) caused by liquid subcooling under atmospheric pressure in a rectangular flow channel; the flow channel was oriented 10 degrees upward from the horizon. Bubble dynamics were examined using a high-speed camera and optical fiber microprobes. A solid copper block was utilized as a test heater and mounted above the flow channel to simulate the passive cooling system of an ex-vessel core catcher designed for nuclear power plants. Low mass flux and subcooling conditions ranging from 40-300 kg/m(2) s and 5-25 K, respectively, were applied at the inlet of the test section. At the mass flux value of 40 kg/m(2) s, large sliding bubbles were attributed to a key criterion for enhanced boiling heat transfer when the liquid subcooling was varied up to 15 K. The results showed that the CHF was weakly dependent on the degree of liquid subcooling, which deviates from the general trend reported by many researchers. A repetitive flow reversal along with a pressure shock appeared, owing to the rapid condensation at the exit, which added complexity to the analysis of the CHF. This study provides physical insights for understanding the subcooled flow boiling heat transfer mechanism (including the CHF) based on sophisticated experimental measurements, such as the visual capture of boiling dynamics using highspeed video and local void fraction. (C) 2018 Elsevier Ltd. All rights reserved. | en_US |
dc.description.sponsorship | The authors gratefully acknowledge the late Dr. In-Cheol Chu for his technical support in setting the void fraction measurement system, and also for his invaluable advice in undertaking this work. This research was also supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT) (Nos. NRF-2017M2B2A9A02049735 and NRF-2016R1A5A1013919). | en_US |
dc.language.iso | en_US | en_US |
dc.publisher | PERGAMON-ELSEVIER SCIENCE LTD | en_US |
dc.subject | Critical heat flux | en_US |
dc.subject | Boiling curve | en_US |
dc.subject | Liquid subcooling | en_US |
dc.subject | Two-phase boundary layer flow | en_US |
dc.subject | Flow reversal | en_US |
dc.subject | Condensation-induced water hammer | en_US |
dc.title | Subcooling effect on boiling heat transfer of inclined downward-facing surface under low flow and pressure | en_US |
dc.type | Article | en_US |
dc.relation.volume | 127 | - |
dc.identifier.doi | 10.1016/j.ijheatmasstransfer.2018.07.064 | - |
dc.relation.page | 182-195 | - |
dc.relation.journal | INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER | - |
dc.contributor.googleauthor | Jeong, Uiju | - |
dc.contributor.googleauthor | Kim, Sung Joong | - |
dc.relation.code | 2018000700 | - |
dc.sector.campus | S | - |
dc.sector.daehak | COLLEGE OF ENGINEERING[S] | - |
dc.sector.department | DEPARTMENT OF NUCLEAR ENGINEERING | - |
dc.identifier.pid | sungjkim | - |
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