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) | Prediction of Steam Generator Tube Behavior via Fluid-Structure Interaction Analysis | Dae Kyung Choi, Won Man Park, and Choengryul Choi(Elsoltec), Young-Jin Oh, Sang-Hoon Lee, and Kunwoo Yi(KEPCO E&C) | PDF보기 | - |
| 2024-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 13:00 | Lobby (3F) | Carbon-Boron Composites for the Canisters in Dry Spent Nuclear Fuel Casks | Hong In KIM and Young-Kook Lee(Yonsei Univ), Sunghwan Yeo, Sung Ho Kim, and Jun Hwan KIM(KAERI) | PDF보기 | - |
| 2024-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.9(Thu) 13:00 | Lobby (3F) | Determination of Negligible Creep Curve for P92 Steel | Woo-Gon Kim, Youngjin Roh, and Seonwha Kim(KETG), Ki-Ean Nam and Hyeong-Yeon Lee(KAERI) | PDF보기 | - |
| 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 | - |
Last Modified : 1998-Autumn
