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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 10:00 301 (3F) Investigation of Computational Dynamic Modeling of Helical Once-Through Steam Generator for Integrated System Analysis Keon Yeop Kim, Youngsuk Bang, So Eun Shin, Haneul Na, and Yeon Jun Choo(FNC Tech.) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 10:20 301 (3F) CFD Study of Two-phase Flow Pressure Drop in Helical Tube Steam Generator Doh Hyeon Kim, Seunghwan Oh, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:00 301 (3F) Influence of Coil Thickness on Natural Convection Heat Transfer of Helical Coil Dong Ho Shin and Bum Jin Chung(KHU) PDF보기 -
2023-Spring 5F : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:20 301 (3F) Experimental Design Procedure for Tubes in Turbulent Cross Flow Dong Seok Oh, Heung Seok Kang, Kang Hee Lee, Chan Lee, and Soo Ho Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn