-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Integration of Fluid Dynamics and Solid Mechanics Models for FSI Simulation Using GPU-based SPH Framework Tae Hoon Lee, So Hyun Park, and Eung Soo Kim(SNU) PDF보기 -
2020-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Sensitivity Analysis of the Heat Loss on the Pressurizer for ATLAS Integral Effect Test Facility KYUNGHO NAM and Tae-woo Kim(KHNP CRI) PDF보기 -
2020-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Steam Line Break Accident Analysis with Multi-scale/Multi-physics Methodology Jae Ryong Lee, Ik Kyu Park, and Han Young Yoon(KAERI) PDF보기 -
2020-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Implementation of Fuel Relocation and Oxide Thermal Barrier Model into MARS-KS/FRAPTRAN Coupled Code System Hyochan Kim, Sunguk Lee, Jangsoo Oh, and Yongsik Yang(KAERI), Joosuk Lee(KINS) PDF보기 -
2020-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line A Simulation of Main Steam Line Break Accidents Using Coupled MASTER/CUPID/MARS Code Ik-Kyu Park, Jae Ryong Lee, and Han Young Yoon(KAERI) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Assessment of Subcooled Boiling Model under High Pressure Condition using CUPID Yun-je Cho, SeongJun Lee, and Han-young Yoon(KAERI) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line An Empirical Correlation for the Onset of Flow Instability in Narrow Vertical Rectangular Channels Tae-Wook Ha(KAERI), Myeong-Kwan Seo, Byong-Jo Yun, and Jae Jun Jeong(PNU) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line A Study on Hydrogen Explosion Possibility in the Containment Filtered Venting System During Severe Accident Gi Hyeon Choi, Ji-Hwan Hwang, and Dong-Wook Jerng(CAU), TaeWoon Kim(NESS,KAERI) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Modelling of the Droplet Entrainment Phenomena for the Simulation of Reflood Phase During a Large-break Loss-of-coolant Accident in a Pressurized Water Reactor Jee Min Yoo, Byong Jo Yun, and Jae Jun Jeong(PNU) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Reactor Core Simulation During a SLB Accident by ASTRA and CUPID Coupling Dae-gwang Hong, Jin-woo Park, Jae-don Choi, and Joo-il Yoon(KEPCO NF), Ik-kyu Park and Jae-ryong Lee(KAERI) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line The Transient Thermal Analysis at a Nuclear Containment Wall during LOCA for an Analysis of a PCM Behavior Yonadan Choi and Yong Hoon Jeong(KAIST) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Modeling of the Wake-induced Lift Force Acting on an Unbounded Bubble at Arbitrary Reynolds Number Wooram Lee and Jae-Young Lee(HGU) PDF보기 -
2020-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Analysis of Nodalization Uncertainty for Higher-order Numerical Scheme under RBHT Experimental Conditions Wonwoong Lee and Jeong Ik Lee(KAIST) PDF보기 -
2020-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Subcooled CHF Model for Narrow Rectangular Channel under Downward Flow Condition Huiyung Kim, Jinhoon Kang, Jae Jun Jeong, and Byongjo Yun(PNU) PDF보기 -
2020-Spring 5E : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Investigation of CHF for IVR-ERVC Condition using a Hydrogen Evolving System Jeong-Won Han, Dong-Young Lee, Hae-Kyun Park, and Bum-Jin Chung(KHU) PDF보기 -
Last Modified : 1998-Autumn