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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Reactor Trip Database Management System Tae-Young Shin, Hyuk-Soon Lim, and Byung-Sik Lee(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Estimation of Internal Flooding Frequency for Screening Analysis of Flooding PSA by Using the Latest Generic Data and the Korean Plant Operation Data Sun Yeong Choi and Joon-Eon Yang(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Study on the Technical Acceptability of PRA for Future Plants Kju-Myeng Oh, Sang-Kyu Ahn, and Chang-Ju Lee(KINS) Jong-Tae Jeong(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of the Latest Generic Data for PSA Applications of Domestic Nuclear Plants Seok-Won Hwang, Ji-Yong Oh, and Byung-Sik Lee(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Current R&D Status and Considerations of Fire Protection SDP Namchul Cho, Jong-Seuk Park, and Chang-Ju Lee(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Combined Application of Fault Trees and Turbine Cycle Simulation in Generation Risk Assessment Gyunyoung Heo(KHU), Jin Kyun Park(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Regulatory PSA Model of Kori Units 2 for a Risk Informed Regulation Jin Hee Park, Ho-Gon Lim, Sang Hoon Han, and Dae Il Kang(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Approach to the Construction of a Single Top PSA Model for Fire Events Dae Il Kang, Sang Hoon Han, and Joon-Eon Yang(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Fault Tree Development of Kori Nuclear Unit 2 for Regulatory PSA Model Jae Won Lim, Hui Chang Yang, and Hyung Suk Kim(ENESYS) Jin Hee Park(KAERI) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) A SMART-IST Assessment for Radionuclide Release in the Wolsong 1 NPP Tech Mo Kim and Chul Jin Choi(KOPEC), Sung Min Kim(NHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Flow Characteristic Evaluation during LOCA Recirculation Transport based on CFD Analysis for OPR1000 Plant Jong Pil Park, Kyung Sik Choi, and Ji Hwan Joeng(PNU), Man Woong Kim(KINS) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of Steam and Gas-flow for APR1400 IRWST Using GOTHIC 6.1b Mun Soo Kim, Suk Ho Lee, and Han Gon Kim(KHNP) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) MTC Effect with the COLR for Reload Cores Il Tak Woo, Sang Rin Shon, Hag Joon Kim, and Sung Ju Cho(KNF) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Assessment of a LOFT L2-5 LBLOCA Uncertainty Based on ACE-RSM: Complementary Work for the OECD BEMUSE Phase-III Program Kwang-Il Ahn and Bub-Dong Chung(KAERI) John C. Lee(Univ., of Michigan) PDF보기 -
2009-Spring 제 5 분과 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Particle Tracking Model to Predict the Debris Transport on Containment Floor Yong Seok Bang, Gil-Soo Lee, Byung-Gil Huh, Deog-Yeon Oh, and Sweng Woong Woo(KINS) PDF보기 -
Last Modified : 1998-Autumn