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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) 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 -
2009-Autumn 제1분과 : 원자로시스템기술 HEAT TRANSFER EXPERIMENT IN A RADIALLY SEPARATED TUBE BUNDLE TYPE DTBSG(II) JONG-HYEUN CHOI, BYOUNG-HAE CHOI, JONG-MAN KIM, JI-YOUNG JEONG, AND BYUNG-HO KIM(KAERI) PDF보기 -
2009-Autumn 제1분과 : 원자로시스템기술 THERMAL-FLUID AND SAFETY ANALYSIS OF THE TRU DEEP-BURN MHR CORE JI SU JUN, HONG SIK LIM, AND CHANG KEUN JO(KAERI) FRANCESCO VENNERI(LOGOS TECHNOLOGIES) PDF보기 -
Last Modified : 1998-Autumn