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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Analysis of LOAF(Loss of All Feed Water) Accident Using OPR1000 Simulator Do Hyun Hwang, Myeong Soo Lee, Jin Hyuk Hong, and Su Jin Byon(KEPCO RI) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Simulation of SMART Startup Operation Seong Wook Lee, Kyoo Hwan Bae, and Suhn Choi(KAERI) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) An Introduction of Behavior-based Safety Program in Nuclear Power Plants Yonghee Lee and Yong-Hee Lee(KAERI) Hyeon-Kyo Lim(CBNU) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Understanding Team Communication Characteristics Using Social Network Analysis Ar Ryum Kim, Seung Woo Lee, and Poong Hyun Seong(KAIST) Jin Kyun Park((KAERI) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Load-following Operation for PWRs Using Fuzzy Model Predictive Control Sim Won Lee, Jae Hwan Kim, and Man Gyun Na(CSU) Keuk Jong Yu(KHNP) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Performance Test of System Identification Methods for a Nuclear Reactor Keuk Jong Yu and Han Gon Kim(KHNP) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Analysis of One Feedwater Pump Stop Event of KALIMER-600 Seung-Hwan SEONG, Han-Ok KANG, and Seong-O KIM(KAERI) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) Conceptual Design of a Combined Power Generation Unit at the NPP Seaside Kyung H. Cha(KAERI) PDF보기 -
2011-Spring 제10분과 : 원자력계측제어 및 자동원격(Nuclear I&C and Automatic Remote Control) A Nuclear Safety System based on Industrial Computer Ji-Hyeon Kim, Do-Young Oh, Nam-Hoon Lee, Chang-Ho Kim, and Jae-Hack Kim(KEPCO E&C) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) LACANES Benchmarking of Thermal Hydraulic Loop Models for LBE Integral Test Loop Phase-I: isothermal steady state forced convection Jae Hyun Cho, Jun Lim, and Il Sooon Hwang(SNU) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Evaluation of Applicability of LWR General Design Requirements to SFR Young Gill Yune, Changwook Huh, Hyung Joon Ahn, Jaeho Song, and Kyun-Tae Kim(KINS) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Study on Deterministic Regulatory Framework for the Development of Safety Analysis System of Sodium Fast Reactors Soon Joon HONG, Su Hyun HWANG, Yeon Joon CHOO, and Byung Chul LEE(FNC Tech) Young Gill YUNE, Chang W PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Preliminary Acceptance Criteria for Safety Analysis of KALIMER-600 SFR Young-Min KWON, Kwi-Lim LEE, Kwi-Seok HA, Won-Pyo Chang, and Hae-Yong JEONG(KAERI) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) Potential Improvements of Supercritical Recompression CO2 Brayton Cycle Coupled with KALIMER-600 by Modifying Critical Point of CO2 Woo Seok Jeong, Jeong Ik Lee, Yong Hoon Jeong, and Hee Cheon NO(KAIST) PDF보기 -
2010-Autumn 제1분과 : 원자로시스템기술(Reactor System Technology) A Design of He-Molten Salt Intermediate Heat Exchanger for VHTR Hui-Seong Jeong and Kwang-Hyun Bang(KMU) PDF보기 -
Last Modified : 1998-Autumn