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KEYWORD_EN: Creep 15 result(s) found
 
1. INFLUENCE OF MECHANICAL ALLOYING ATMOSPHERES ON THE MICROSTRUCTURES AND MECHANICAL PROPERTIES OF 15Cr ODS STEELS

Noh, Sanghoon;Choi, Byoung-Kwon;Kang, Suk Hoon;Kim, Tae Kyu;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 857-862
 
2. STEAM GENERATOR TUBE INTEGRITY ANALYSIS OF A TOTAL LOSS OF ALL HEAT SINKS ACCIDENT FOR WOLSONG NPP UNIT 1

Lim, Heok-Soon;Song, Tae-Young;Chi, Moon-Goo;Kim, Seoung-Rae;
Nuclear Engineering and Technology, vol. 46, iss. 1, 2014, pp. 39-46
 
3. PREDICTION OF DIAMETRAL CREEP FOR PRESSURE TUBES OF A PRESSURIZED HEAVY WATER REACTOR USING DATA BASED MODELING

Lee, Jae-Yong;Na, Man-Gyun;
Nuclear Engineering and Technology, vol. 44, iss. 4, 2012, pp. 355-362
 
4. DIAMETRAL CREEP PREDICTION OF THE PRESSURE TUBES IN CANDU REACTORS USING A BUNDLE POSITION-WISE LINEAR MODEL

Lee, Sung-Han;Kim, Dong-Su;Lee, Sim-Won;No, Young-Gyu;Na, Man-Gyun;Lee, Jae-Yong;Kim, Dong-Hoon;Jang, Chang-Heui;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 301-308
 
5. THE EFFECTS OF CREEP AND HYDRIDE ON SPENT FUEL INTEGRITY DURING INTERIM DRY STORAGE

Kim, Hyun-Gil;Jeong, Yong-Hwan;Kim, Kyu-Tae;
Nuclear Engineering and Technology, vol. 42, iss. 3, 2010, pp. 249-258
 
6. FEASIBILITY OF AN INTEGRATED STEAM GENERATOR SYSTEM IN A SODIUM-COOLED FAST REACTOR SUBJECTED TO ELEVATED TEMPERATURE SERVICES

Koo, Gyeong-Hoi;Lee, Jae-Han;
Nuclear Engineering and Technology, vol. 41, iss. 8, 2009, pp. 1115-1126
 
7. CLADDING TO SUSTAIN CORROSION, CREEP AND GROWTH AT HIGH BURN-UPS

Wikmark, Gunnar;Hallstadius, Lars;Yueh, Ken;
Nuclear Engineering and Technology, vol. 41, iss. 2, 2009, pp. 143-148
 
8. RESULTS OF THERMAL CREEP TEST ON HIGHLY IRRADIATED ZIRLO

Quecedo, M.;Lloret, M.;Conde, J.M.;Alejano, C.;Gago, J.A.;Fernandez, F.J.;
Nuclear Engineering and Technology, vol. 41, iss. 2, 2009, pp. 179-186
 
9. EVALUATION AND TEST OF A CRACK INITIATION FOR A 316 SS CYLINDRICAL Y-JUNCTION STRUCTURE IN A LIQUID METAL REACTOR

Park, Chang-Gyu;Kim, Jong-Bum;Lee, Jae-Han;
Nuclear Engineering and Technology, vol. 38, iss. 3, 2006, pp. 293-300
 
10. 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, vol. 37, iss. 6, 2005, pp. 565-574