학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 12:00 302 (3F) Integrate Modeling Analysis of Secondary and Primary System for Small Modular Reactors Jungjin Bang, Seong-Su Jeon, Young Suk Bang, Bub Dong Chung, and Young Seok Bang(FNC Tech.) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:00 302 (3F) A Model of the Bubble Waiting Time in Forced Subcooled Boiling ManhLong Doan, Jeongmin Moon, Jinyeong Bak, Jae Jun Jeong, and Byongjo Yun(PNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:20 302 (3F) Experimental Investigation of the Bubble Behavior Under Rolling Oscillations Myungho Kim and Byoungjae Kim(CNU) PDF보기 PPT보기
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 -
Last Modified : 1998-Autumn