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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Results of OECD-NEA THAI Test HM-2 Benchmark Study with MELCOR Code Jung-Jae Lee, Han-Chul Kim, and Key-Yong Sung(KINS) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) APR1400 Containment Simulation with CONTAIN Code Moonkyu Hwang and Bub Dong Chung(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Estimation of Common Cause Failure Parameters for Emergency Service Water System Pump of Kori Unit 2 Dae Il Kang, Mee Jung Hwang, Sang Hoon Han, and Jin Hee Park(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Sensitivity Analyses of Core Damage Frequency on the Design Alternatives for SFR-600 Conceptual Design Tae Woon Kim, Sang Hoon Han, and Hae-Yong Jeong(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Technical Considerations for the Systems Analysis in SMART PSA NamChul Cho and Chang-Ju Lee(KINS) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Proposed Approach for Enhancing Design Safety Assurance of Future Plants Kju-Myeong Oh, Sang-Kyu Ahn, and Chang-Ju Lee(KINS) Inn Seock Kim(ISSA Tech.) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on LOCA Frequency and Contribution to Risk of Nuclear Power Plant Seong Soo Choi, Dong Sik Jin, and Poong Oh Kim(ACT Co.,Ltd.) Inn Seock Kim(ISSA Tech.) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Study on the Regulatory Requirement of Event Frequency Change by Facility Improvement and Modification in Wolsong Unit 1 Kilyoo Kim and Jinhee Park(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Comparison between Heinrich's Law and the Number of Events in Domestic Nuclear Power Plants Sun Yeong Choi and Joon-Eon Yang(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of In-Core Damage for Feeder Stagnation Break in CANDU Jong Yeob Jung and Joo Hwan Park(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of Worldwide Regulatory Framework for On-Line Maintenance Sang-Kyu AHN, Kyu-Myung OH, and Chang-Ju Lee(KINS) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design of Nanoparticle Engineered Safety Injection Tank Myoung-suk Kang, Changhyun Jee, Sangjun Park, and Gyunyoung Heo(KHU) In Choel Bang(UNIST) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Application of a New Approach for Estimating LOCA and SGTR Frequencies Ho-Jun Jeon, Ji-Yong Oh, and Moon-Goo Chi(KHNP) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Evaluation of the Unexpected Trip Limits Using the Quality Control Approach Hyun-woo Lee and Moosung Jae(HYU) Kilyoo Kim(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal Field of Moderator Circulation in CANDU-6 Reactor Tae Kwang Eom, Sung Je Hong, and Jae Young Lee(HGU) PDF보기 -
Last Modified : 1998-Autumn