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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:40 302 (3F) Influence of Inlet Turbulent Boundary Conditions on Bubble Diameter Calculation Erol Bicer, Seong-Su Jeon, Yeon-Jun Choo, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 10:00 302 (3F) Heat Partitioning Model with Bubble Tracking Method Considering Conjugate Heat Transfer Ja Hyun Ku, Heepyo Hong, and Hyoung Kyu Cho(SNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 10:40 302 (3F) Experimental Study for Evaluation of Re-wetting Velocity on Micropillar Structures Using Particle Image Velocimetry (PIV) Technique Hyeon Taek Nam, Hyunmuk Park, Yoomyeong Lee, Seungro Lee, and Donghwi Lee(JBNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 11:00 302 (3F) Numerical Investigation of DNB for a Subcooled Flow Boiling in an Oscillating Pipe Namkyu Ryu and Byoungjae Kim(CNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 11:20 302 (3F) A Parametric Study on Pool Boiling CHF Phenomenon in Heaving Conditions: The Effects of Heaving Periods Do Yeon Kim, Su Cheong Park, Seonho Choi, and Dong In Yu(PKNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 11:40 302 (3F) Flow Boiling CHF Behavior according to Liquid Subcooling on the ATF-coated Tube Namgook Kim and Sung Joong Kim(HYU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 12:00 302 (3F) Critical Heat Flux Tests on Accident Tolerant Fuel Cladding Under PWR and BWR Conditions Donghwi Lee(JBNU), Tiago Augusto Moreira and Mark H.Anderson(University of Wisconsin-Madison) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:30 301 (3F) Study on Performance Evaluation Methodology for Passive Safety System Jeehee Lee, Seong-Su Jeon, and Su Hyun Hwang(FNC Tech.), Ju-Yeop Park(KINS) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:50 301 (3F) Development of Regulatory Audit Methodologies for Cr-coated ATF Cladding: A Scoping Analysis on LOCA Safety Joosuk Lee, Hyedong Jeong, and Kyunglok Baek(KINS) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:10 301 (3F) High-fidelity Numerical Investigation on Structural Integrity for SFR Fuel Cladding during Design Basis Events SeoYoon Choi and JaeHo Jeong(Gachon Univ.), HyungKyu Kim(KAERI) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:30 301 (3F) Analysis of a CEA Ejection Scenario for the Korean APR1400 Reactor using BEPU Approach Ditsietsi Malale, Saja Rababah, Sebastian Dzien, and Aya Diab(KINGS) PDF보기 -
2023-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:50 301 (3F) System Code Analysis of MSGTR Mitigation with Passive Auxiliary Feedwater System Seongsu Jeon, Youngjae Park, Jaeho Bae, Jungjin Bang, and Youngwook Chung(FNC Tech.), Dohyun Hwang(KHNP) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:00 301 (3F) Analysis of Natural Circulation Characteristics of Passive Molten Salt Fast Reactor by using OpenFOAM Simulation Juhyeong Lee, Sangtae Kim, and Sung Joong Kim(HYU), Yonghee Kim(KAIST) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:20 301 (3F) Selecting Optimal Heat Transfer Chloride Salt for Molten Salt Fast Reactor Sungwook Choi, Taeyoen Min, In Woo Son, Sunghyun Yoo, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:40 301 (3F) Assessment of Helium Bubbling Effect on Natural Circulation Applicable for Passive Molten Salt Fast Reactor Wonjun Choi, Jae Hyung Park, Juhyeong Lee, Jihun Lim, Yunsik Cho, Sangtae Kim, and Sung Joong Kim(HYU), Yonghee Kim(KAIST), Youngsoo Yoon(Gachon Univ.) PDF보기 -
Last Modified : 1998-Autumn