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dc.contributor.author김성중-
dc.date.accessioned2019-12-10T20:28:30Z-
dc.date.available2019-12-10T20:28:30Z-
dc.date.issued2018-12-
dc.identifier.citationINTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v. 127, pt. B, page. 182-195en_US
dc.identifier.issn0017-9310-
dc.identifier.issn1879-2189-
dc.identifier.urihttps://www.sciencedirect.com/science/article/abs/pii/S001793101830958X?via%3Dihub-
dc.identifier.urihttps://repository.hanyang.ac.kr/handle/20.500.11754/121170-
dc.description.abstractThe 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.sponsorshipThe 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.isoen_USen_US
dc.publisherPERGAMON-ELSEVIER SCIENCE LTDen_US
dc.subjectCritical heat fluxen_US
dc.subjectBoiling curveen_US
dc.subjectLiquid subcoolingen_US
dc.subjectTwo-phase boundary layer flowen_US
dc.subjectFlow reversalen_US
dc.subjectCondensation-induced water hammeren_US
dc.titleSubcooling effect on boiling heat transfer of inclined downward-facing surface under low flow and pressureen_US
dc.typeArticleen_US
dc.relation.volume127-
dc.identifier.doi10.1016/j.ijheatmasstransfer.2018.07.064-
dc.relation.page182-195-
dc.relation.journalINTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER-
dc.contributor.googleauthorJeong, Uiju-
dc.contributor.googleauthorKim, Sung Joong-
dc.relation.code2018000700-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentDEPARTMENT OF NUCLEAR ENGINEERING-
dc.identifier.pidsungjkim-
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COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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