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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2017-Spring 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 11:40 삼다홀 A (3F) Experimental Study of Two-Phase Critical Flow for Supercritical CO2 application Min Seok Kim(KAIST), Bong Seong Oh(KAIST), Jin Su Kwon(KAIST), and Jeong Ik Lee(KAIST) PDF보기 -
2017-Spring 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 12:00 삼다홀 A (3F) Enhanced Thermal Margin of Spent Fuel Dry Storage Cask Applying Hybrid Control Rod Kyung Mo Kim(UNIST), Yeong Shin Jeong(UNIST), and In Cheol Bang(UNIST) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 09:00 삼다홀 B (3F) Modified Reynolds Stress Model for Turbulent Bubbly Flows Seung-Jun Lee(KAERI), Ji Hyun Sohn(KAERI), Han Young Yoon(KAERI), and Byoung Jae Kim(Chungnam National University) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 09:20 삼다홀 B (3F) CUPID Simulation of Siphon Break Experiments Ik Kyu Park, Han Young Yoon, and Hong Beom Park(KAERI) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 09:40 삼다홀 B (3F) Simulation of Boron Dilution Benchmark using CUPID Code Yun-Je Cho(KAERI), Jae-Ryong Lee(KAERI), and Han-Young Yoon(KAERI) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 10:00 삼다홀 B (3F) Steady-state Thermal-hydraulic Analysis of PWR Whole Reactor Core in Subchannel Scale Using CUPID Seok Jong Yoon(SNU), Seul Been Kim(SNU), Goon Cherl Park(SNU), and Hyoung Kyu Cho(SNU) PDF보기 PPT보기
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 10:20 삼다홀 B (3F) A Computational Investigation for Steam Condensation on a Flat Plate in the Presence of Non-condensable Gas Using a CUPID Code MinSeok Ko((KNHP CRI).), YeonJoon Choo((KNHP CRI).), and SoonJoon Hong((KNHP CRI).) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 11:00 삼다홀 B (3F) Thermal Hydraulic Analysis of PWR Steam Generator using CUPID-SG: Coupling of the Primary and Secondary Coolant Models Han Young Yoon(KAERI), Ik Kyu Park(KAERI), Jar Ryong Lee(KAERI), Seung Jun Lee(KAERI), and Han Sol Kim(KAERI) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 11:20 삼다홀 B (3F) GOTHIC Multi-Dimensional Analysis for Containment Implemented with Passive Containment Cooling System (PCCS) Seong-Su Jeon((KNHP CRI).), Yeon-Jun Choo((KNHP CRI).), and Soon-Joon Hong((KNHP CRI).) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 11:40 삼다홀 B (3F) CFD analysis of steam jet injection in a hybrid SIT Byong Guk Jeon(KAERI), Sung-Uk Ryu(KAERI), and Dong Jin Euh(KAERI) PDF보기 -
2017-Spring 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 12:00 삼다홀 B (3F) THAI-HM2 Benchmark Study with STAR-CCM+ Code Simulation Sang Yun Shin(NSRC, CAU), Hoe-Yeol Kim(NSRC, CAU), Sang June Hahn(PTND, CAU), and Dong-Wook Jerng(NSRC, CAU) PDF보기 -
2017-Spring 5C : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 09:00 301 (3F) (초청발표1) Severe Accident Mitigation Features in Korean Advanced NPP Young Tae Moon and In Seon Yeo(KEPCO E&C) PDF보기 -
2017-Spring 5C : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 09:30 301 (3F) Examination of SBO Emergency Operating Procedures of APR1400 using MARS code Shin Eom(KINGS) and Seung Jong Oh(KINGS) PDF보기 -
2017-Spring 5C : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 09:50 301 (3F) SAMG Supporting Computational Aid Development Using MAAP-ISAAC Code for PHWR YongMann SONG(KAERI), SooYong PARK(KAERI), DongHa KIM(KAERI), and JinHo SONG(KAERI) PDF보기 -
2017-Spring 5C : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 10:10 301 (3F) MELCOR assessment of sequential severe accident mitigation actions under SGTR accident Wonjun Choi(HYU), Joongoo Jeon(HYU), Nam Kyung Kim(HYU), and Sung Joong Kim(HYU) PDF보기 -
Last Modified : 1998-Autumn