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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2024-Spring 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.9(Thu) 13:00 Lobby (3F) Short-Term Corrosion Characteristics of Molten Salt Reactor Materials and Cladding Ji-Hyun Yoon, Giseung Shin, Chaewon Kim, Hyeon-Geun Lee, and Chang Hwa Lee(KAERI), Jeoung Han Kim(Hanbat National Univ.) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 09:00 202B (2F) Analysis of Heat Flux Partitioning Model for Copper and SUS304 using High Speed Camera at Low Heat Flux Se Hyeon Park and HangJin Jo(POSTECH) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 09:20 202B (2F) Experimental Observation of Flow Boiling CHF on Heater Rod with Axially Cosine Shape Power Distribution under Rolling Condition Heepyo Hong, Jin-Seong Yoo, Hyukjae Ko, Ja Hyun Ku, Giwon Bae, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 09:40 202B (2F) Experimental Performance Evaluation of a Printed Circuit Type Multi-stream Heat Exchanger with Helium Loop for Hydrogen Production Sin-Yeob Kim, Sung-Deok Hong, Byung-Ha Park, and Chan-Soo Kim(KAERI) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 10:00 202B (2F) Experimental Studies for Hydraulic Characteristics of Corrugated Channel for Printed Circuit Steam Generator (PCSG) Taemin An, Armanto Simanjuntak, and Jaeyoung Lee(Handong Global Univ.) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 10:20 202B (2F) Mass Transfer Experiment on Natural Convection Heat Transfer in a Vertical Plate at Under High Rayleigh Number Conditions Dong-Gyu Lee, Seong-Il Beak, and Bum-Jin Chung(KHU) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:00 202B (2F) Numerical Analysis of Melting/Solidification Problems using OpenFOAM Erol Bicer, Youngjae Park, Youcho Choi, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:20 202B (2F) Prediction Methodology of Critical Heat Flux on a Heater Rod Under Inclined and Rolling Conditions Based on Bubble Tracking Method and Continuum Percolation Theory Geon-Woo Kim and Jae Soon Kim(KINS), Hyoung Kyu Cho(SNU) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:40 202B (2F) Probabilistic Neural Network Approach for Critical Heat Flux Prediction with Uncertainty Quantification Kyung Mo Kim(KENTECH) PDF보기 -
2024-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 12:00 202B (2F) Thermal-hydraulic Performance Analysis of Zigzag Channel PCHE according to Bending Angle Yoomyeong Lee and Donghwi Lee(Jeonbuk National Univ.), Seongmin Lee, Hong Beom Park, and Kyoungwoo Seo(KAERI) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 09:00 203 (2F) Applicability of GeN-Foam to Fast-Spectrum Molten Salt Reactors with BeO Reflector and Preliminary Analysis Wooseong Park and Yong Hoon Jeong(KAIST) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 09:20 203 (2F) Influences of Bed Height on Mixed Convection Heat Transfer in a Packed Bed Seong-Il Baek and Bum-Jin Chung(KHU) PDF보기 PPT보기
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 09:40 203 (2F) Validation of the Transient Heat Pipe Code with the SAFE-30 Experiment San Lee, Ye Sung Kim, and Hyoung Kyu Cho(SNU) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 10:00 203 (2F) Scaling Analysis for Conceptual Design of Steel Containment Vessel in i-SMR Integral Effect Test Facility Jin-Hwa Yang, Byoung-Uhn Bae, Hwang Bae, and Kyoung-Ho Kang(KAERI) PDF보기 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 10:20 203 (2F) Design Consideration of ECCS Valve for Integral Type SMR Jan Hruskovic, Youngjae Park, Youcho Choi, Young Seok Bang, Seong-Su Jeon, and Soon-Joon Hong(FNC Tech.) PDF보기 -
Last Modified : 1998-Autumn