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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Spring 제 10 분과 : 원자력 계측제어 및 자동원격(Nuclear I&C and Automatic Remote Systems) Development of a Valve Actuation Simulator by Using the Interactive Control Features of the MARS Code Sung Won Bae, Hyung Kyu Cho, S. W. Lee, and K. D. Kim(KAERI) Han Gi Lee and Yang Hwan Kim(KHNP) PDF보기 -
2010-Spring 제 10 분과 : 원자력 계측제어 및 자동원격(Nuclear I&C and Automatic Remote Systems) Development of Turbine-leading Power Maneuvering Strategy for a Sodium-cooled Fast Reactor Seong-Hwan Seong, Han-Ok Kang, and Seong-O Kim(KAERI) PDF보기 -
2010-Spring 제 10 분과 : 원자력 계측제어 및 자동원격(Nuclear I&C and Automatic Remote Systems) Simulation for Remote Operation for REX10 Nuclear Reactor Sim Won Lee, Dong Su Kim, and Man Gyun Na(CSU) Yoon Joon Lee(JEJUNU) Yeon-Gun Lee and Goon Cherl Par PDF보기 -
2010-Spring 제 10 분과 : 원자력 계측제어 및 자동원격(Nuclear I&C and Automatic Remote Systems) Spurious Activation of Digital Plant Protection System in Nuclear Power Plants M. Khalaquzzaman and Poong Hyun Seong(KAIST) Hyun Gook Kang and Man Cheol Kim(KAERI) PDF보기 -
2010-Spring 제 10 분과 : 원자력 계측제어 및 자동원격(Nuclear I&C and Automatic Remote Systems) Development of a Plant Health Index Monitor Gyunyoung Heo(KHU) Sang Ha An(KAIST) Ho Joon Seo(BNF Tech.) Cho Kim(KOSEP) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 INELASTIC ANALYSIS OF THE CREEP FATIGUE DAMAGE FOR A REACTOR INTERNAL STRUCTURE S. H. KIM AND G. H. KOO(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 PRE-ANALYSIS OF PHENIX END-OF-LIFE THERMAL-HYDRAULIC TESTS WITH THE MARS-LMR CODE HAE-YONG JEONG, KWI-SEOK HA, YOUNG-MIN KWON, WON-PYO CHANG, SU-DONG SUK, AND YONG- BUM LEE(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 DEVELOPMENT OF PRELIMINARY PIRTS OF THERMAL-HYDRAULIC PHENOMENA FOR KALIMER-600 YOUNG-MIN KWON, HAE-YONG JEONG, KWI-SEOK HA, AND WON-PYO CHANG(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 PARTIAL LOAD STUDY FOR KALIMER IN ONCE-THROUGH MODE OF A SUPERHEATED STEAM GENERATOR EUI KWANG KIM AND SEONG-O KIM(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 A CORRELATED ACTIVE ACOUSTIC LEAK DETECTION IN A SFR STEAM GENERATOR TAE-JOON KIM, JI-YOUNG JEONG, JONG-MAN KIM, BYUNG-HO KIM, YOUNG-IL KIM, AND DOHEE HAHN(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 CORE DESIGN STUDIES FOR A 300 MWE TRU BURNER REACTOR HOON SONG, SANG JI KIM, AND YEONG IL KIM(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 THE MULTI-DIMENSIONAL ANALYSIS METHOD DEVELOPMENT FOR SODIUM POOL OF SFR USING MARSLMR CODE SEUNG MIN WOO, HAE MIN PARK, AND SOON HEUNG CHANG(KAIST) KWI SEOK HA(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 WASTAGE BEHAVIOR OF MODIFIED 9CR-1MO STEEL TUBE MATERIAL BY SODIUM-WATER REACTION JI-YOUNG JEONG, JONG-MAN KIM, TAE-JOON KIM, JONG-HYEUN CHOI, AND BYUNG-HO KIM(KAERI) NAM-COOK PARK(C PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 THE DEVELOPMENT OF A NEW CONCEPT FOR A DOUBLE WALL TUBE STEAM GENERATOR HO-YUN NAM, BYOUNG-HAE CHOI, JONG-MAN KIM, AND BYUNG-HO KIM(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 A COMPARATIVE STUDY OF MATRA-LMR/FB FOR LOCAL FLOW BLOCKAGES WITH SABRE4 WON-PYO CHANG, KI-SUK HA, AND YONG-BUM LEE(KAERI) PDF보기 -
Last Modified : 1998-Autumn