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No Article Title /Author/Journal Title/Publication Year Cited
DEPENDENCY OF SINGLE-PHASE FAC OF CARBON AND LOW-ALLOY STEELS FOR NPP SYSTEM PIPING ON PH, ORIFICE DISTANCE AND MATERIAL/
[Moon, Jeong-Ho;Chung, Hung-Ho;Sung, Ki-Woung;Kim, Uh-Chul;Rho, Jae-Seong;] / Nuclear Engineering and Technology / 2005     		0
A NEW BOOK: 'LIGHT-WATER REACTOR MATERIALS'/
[OLANDER DONALD R.;MOTTA ARTHUR T.;] / Nuclear Engineering and Technology / 2005     		0
HOT CHANNEL ANALYSIS CAPABILITY OF THE BEST-ESTIMATE MULTI-DIMENSIONAL SYSTEM CODE, MARS 3.0/
[JEONG J.-J.;BAE S. W.;HWANG D. H.;LEE W. J.;CHUNG B. D.;] / Nuclear Engineering and Technology / 2005     		1
SAFETY STUDIES ON HYDROGEN PRODUCTION SYSTEM WITH A HIGH TEMPERATURE GAS-COOLED REACTOR/
[TAKEDA TETSUAKI;] / Nuclear Engineering and Technology / 2005     		0
COMPARISON OF DRYOUT POWER DATA BETWEEN CANFLEX MK-V AND CANFLEX MK-IV BUNDLE STRINGS IN UNCREPT AND CREPT CHANNELS/
[JUN JI SU;LEUNG L.K.H.;] / Nuclear Engineering and Technology / 2005     		0
RHODIUM SELF-POWERED NEUTRON DETECTOR'S LIFETIME FOR KOREAN STANDARD NUCLEAR POWER PLANTS/
[YOO CHOON SUNG;KIM BYOUNG CHUL;PARK JONG-HO;FERO ARNOLD H.;ANDERSON S. L.;] / Nuclear Engineering and Technology / 2005     		1
AN EXPERIMENTAL STUDY ON AIR-WATER COUNTERCURRENT FLOW LIMITATION IN THE UPPER PLENUM WITH A MULTI-HOLE PLATE/
[NO HEE CHEON;LEE KYUNG-WON;SONG CHUL-HWA;] / Nuclear Engineering and Technology / 2005     		0
STATUS AND PERSPECTIVE OF TWO-PHASE FLOW MODELLING IN THE NEPTUNE MULTISCALE THERMAL-HYDRAULIC PLATFORM FOR NUCLEAR REACTOR SIMULATION/
[BESTION DOMINIQUE;GUELFI ANTOINE;DEN/EER/SSTH CEA-GRENOBLE,;] / Nuclear Engineering and Technology / 2005     		0
ANALYSES OF FLUID FLOW AND HEAT TRANSFER INSIDE CALANDRIA VESSEL OF CANDU-6 REACTOR USING CFD/
[YU SEON-OH;KIM MANWOONG;KIM HHO-JUNG;] / Nuclear Engineering and Technology / 2005     		0
DEVELOPMENT OF INTERFACIAL AREA TRANSPORT EQUATION/
[ISHII MAMORU;KIM SEUNGJIN;KELLY JOSEPH;] / Nuclear Engineering and Technology / 2005     		0