-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Plant Application of SPACE-mTRAN Coupled Code System Seung Wook Lee, Hyo Chan Kim, Yong Sik Yang, and Kyung-Doo Kim(KAERI), Jin-Hyuk Hong(EDT) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Sensitivity Analysis of Operator Recovery Actions for Multiple Steam Generator Tube Rupture Event in OPR1000 MinJeong Kim(KHNP CRI) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Evaluation of Sensitivity Study on the Reactor Power Effect for Complete Flow Blockages of Plate-type Fuel Assembly Jong-Pil Park(KAERI) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Extension of the SPACE Code Capability into Thermal-Hydraulic Analysis for Ocean Nuclear Reactor Byoung Jae Kim and Young Seock An(CNU), Seung Wook Lee(KAERI) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Numerical Demonstration of an Unmanned Reactor Based on Passive Infinite Cooling System Byoung Jae Kim and Nam Kyu Ryu(CNU), Sung Jae Yi(KAERI) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) CFD Analysis of Steam Flow at TI-SGTR Accident Induced by MSSV Stuck-Open Faults Wung Jae Wang and Man Sung Yim(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Model Development for Condensate Collection from Passive Containment Cooling System and Return to In-Containment Refueling Water Storage Tank Jin Chul Kang, Jong ho Kim, and Jae sik Jeung(KEPCO E&C) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Void Fraction Predictability of System Codes Based on PSBT Bundle Test Yunseok Lee, Yeongjae Lee, and Taewan Kim(INU) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Computational Analysis of Wall Condensation in the Presence of Non-condensable Gas Mixture Containing a Light Gas with CUPID Chang Won Lee and Hyoung Kyu Cho(SNU) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Assessment of SPACE Code for Loss of Ultimate Heat Sink in OPR1000 Doo-hyuk Kang and Jae-seung Suh(SENTECH) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Application of Adjoint Based Node Optimization Method to MARS Jae Jun Lee, Min-Gil Kim, Seongmin Son, and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Coupling of FLUENT and ANLHTP for Steady-state Thermal Analysis of a Heat Pipe Cooled Reactor Core San Lee and Hyoung Kyu Cho(SNU), Changho Lee and Taek K. Kim(ANL) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Study of the Artificial Neural Networks to Replace the Constitutive Equations in the Reactor Safety Analysis Code ChoHwan Oh, Sung Gil Shin, Seongmin Son, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Calculation of SGTR with HPSI Failure in OPR1000 using SPACE Code Dong-ha Lee, Yeon-sik Cho, and Jae-seung Suh(SENTECH) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Sensitivity Analysis of Reflood Model with RBHT Experiment Wonwoong Lee and Jeong Ik Lee(KAIST) PDF보기 -
Last Modified : 1998-Autumn