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Results 221-230 of 247 (Search time: 0.007 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Flow Boiling CHF Characteristics of Magnetic Nanofluid Under the Magnetic Field Condition Lee, Taeseung; Lee, Jong Hyuk; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-18 | |
| A critical heat flux model for flow boiling in the IVR conditions Park, Hae Min; Carnevali, Sofia; Gaudier, Fabrice; Jeong, Yong Hoon, 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017, International Congress on Advances in Nuclear Power Plants, ICAPP, 2017-04 | |
| Experimental CHF Study on the Effect of Heater Material and Coolant Additives for the Top of the Reactor Vessel Lower Head Park, Hae Min; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-16 | |
| CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions KAM, DONG HOON; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01 | |
| Preliminary Design Study of an Innovative High-Performance Nuclear Thermal Rocket Utilizing LEU Fuel Nam, Seung Hyun; Venneri, Paolo; Choi, Jae Young; Jeong, Yong Hoon; Chang, Soon-Heung, Nuclear and Emerging Technologies for Space (NETS-2015), American Nuclear Society (ANS), 2015-02-24 | |
| INNOVATIVE NUCLEAR THERMAL ROCKET CONCEPT UTILIZING LEU FUEL FOR SPACE APPLICATION Nam, Seung Hyun; Venneri, Paolo; Choi, Jae Young; Jeong, Yong Hoon; Chang, Soon-Heung, The 23rd International Conference on Nuclear Engineering, Japan Nuclear Safety Institute, 2015-05-20 | |
| RANS Simulation of Turbulent Swept Flow over a Wire in a Channel for Core Thermal Hydraulic Design You, Byung-Hyun; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01 | |
| Effect of Wettability and Two-phase Flow Conditions on Flow Boiling CHF Enhancement for Slug Flow Park, Hae Min; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01 | |
| Design and Evaluation of Passive Decay-heat Removal System Using Mercury Thermosyphon You, Byung-Hyun; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-16 | |
| Effect of Material and Additives on CHF for IVR-ERVC Strategy Park, Hae Min; Jeong, Yong Hoon, 2013 winter meeting and Nuclear Technology EXPO(American Nuclear Society), American Nuclear Society, 2013-11-12 |
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