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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2024-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 11:00 203 (2F) Preliminary Experiment for Validation of Fission Product Flotation System in Passive Molten Salt Fast Reactor Yun Sik Cho, Hyo Jun Ahn, Do Won Lee, and Sung Joong Kim(HYU) PDF보기 -
Last Modified : 1998-Autumn