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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:00 203 (2F) Calibration of Fuel Assembly Mockup of Advanced Research Reactor Taeil Kim, Yohan Lee, Donkoan Hwang, WooHyun Jung, Nakjun Choi, and HangJin Jo(POSTECH), Jonghark Park, Hyung Min Son, Huiyung Kim, Kiwon Song(KAERI) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:20 203 (2F) Numerical Simulation for ROCOM PTS Test using Generalized k-ω Turbulence Model Dong-Hyeon Choi and Yoon-Suk Chang(KHU) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 09:40 203 (2F) Parametric Study of the Fuel Salt Drain System Design of K-MSR Dongyeol Yeo, Chan Lee, and Gyeong-Hoi Koo(KAERI) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 10:00 203 (2F) Review of Prediction Capability of System Analysis Code for Density Wave Oscillation Dong-Young Lee, Seong-Su Jeon, Jan Hruskovic, YoungJae Park, and Jungjin Bang(FNC Tech.) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 10:20 203 (2F) Rolling Motion Effect on Differential Pressure Measurement in NEOUL-R Flow Boiling Experiment Hyukjae Ko, Jin-Seong Yoo, Heepyo Hong, Ja Hyun Ku, Giwon Bae, Goon-Cherl Park, and Hyong Kyu Cho(SNU) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 11:00 203 (2F) Sensitivity Assessment of Gas Injection Effect in Terms of Natural Circulation Performance through Adiabatic Two-Phase Experiment Won Jun Choi, Jae Hyung Park, Seung Gyu Hyeon, and Sung Joong Kim(HYU) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 11:20 203 (2F) Temperature Prediction of Cladding in CANDU Spent Fuel Dry Storage Canister using CFD Code and Uncertainty Analysis Tae Gang Lee and Jae Jun Jeong(Pusan National Univ.), Tae Hyung Na(KHNP CRI) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 11:40 203 (2F) Verification Methods of Pressure Matrix Integration and Reduction for Implicit Coupling of Two Codes Using One Code Kum Ho Han, Bub-Dong Chung, and Soon-Joon Hong(FNC Tech.), Jaeseok Heo(KAERI) PDF보기 -
2024-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.10(Fri) 12:00 203 (2F) Development of Molten Salt Reactor related Thermal Hydraulic Properties for Safety Analysis with AMESIM Code Seon Gon Kim, Han Seop Song, and Jae Ho Jeong(Gachon Univ.), Sang Hwan Kim(KRISO) PDF보기 -
2024-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 13:30 202B (2F) Development of a Mean Bubble Size Correlation under Pool Scrubbing Conditions Erol Bicer, Yeon-Jun Choo, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2024-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 13:50 202B (2F) Development of Regulatory Audit Codes for Performance Analysis of Cr-coated ATF Fuel Joosuk Lee, Hyedong Jeong, Sarah Kang, Seulbeen Kim, Jangkeun Park, Byunggil Huh, and Yongseok Choi(KINS) PDF보기 -
2024-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 14:10 202B (2F) Comparative Assessment of Two-phase Crossflow Behavior of System Codes in Bundle Yunseok Lee and Taewan Kim(Incheon National Univ.) PDF보기 -
2024-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 14:50 202B (2F) Analysis of Inadvertent Operation of the Emergency Core Cooling System During Shutdown Cooling System Operation on APR1400 Using SPACE Code Ye Eun An, Se Young Ro, Sang Jin Lee, Min Shin Jung, and Seok Jeong Park(KEPCO E&C) PDF보기 -
2024-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 15:10 202B (2F) Development of Robustness Assessment Methodology for Performance Issue on Passive Safety System Jehee Lee, Seong-Su Jeon, and Youngjae Park(FNC Tech.), Ju-Yeop Park(KINS) PDF보기 -
2024-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 5.9(Thu) 15:30 202B (2F) MARS-KS Analysis on an Integral Effect Test of CLOF for the SMART Design Hyun-Sik Park, Jin-Hwa Yang, Byong-Guk Jeon, and Hwang Bae(KAERI) PDF보기 PPT보기
Last Modified : 1998-Autumn