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AUTHOR_KR:Deok-Gyeong Seong 205 result(s) found
 
1. DETECTION OF ODSCC IN SG TUBES DEPENDING ON THE SIZE OF THE CRACK AND ON THE PRESENCE OF SLUDGE DEPOSITS

Chung, Hansub;Kim, Hong-Deok;Kang, Yong-Seok;Lee, Jae-Gon;Nam, Minwoo;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 869-874
 
2. INFLUENCE OF SIGNAL-TO-NOISE RATIO ON EDDY CURRENT SIGNALS OF CRACKS IN STEAM GENERATOR TUBES

Hur, Do Haeng;Choi, Myung Sik;Shim, Hee-Sang;Lee, Deok Hyun;Yoo, One;
Nuclear Engineering and Technology, vol. 46, iss. 6, 2014, pp. 883-888
 
3. A REVIEW ON THE ODSCC OF STEAM GENERATOR TUBES IN KOREAN NPPS

CHUNG HANSUB ; KIM HONG-DEOK ; OH SEUNGJIN ; BOO MYUNG HWAN ; NA KYUNG-HWAN ; YUN EUNSUP ; KANG YONG-SEOK ; KIM WANG-BAE ; LEE JAE GON ; KIM DONG-JIN ; KIM HONG PYO
Nuclear Engineering and Technology, vol. 45, iss. 4, 2013, pp. 513-522
 
4. Patterns of Citing Korean DOI Journals According to CrossRef’s Cited-by Linking and a Local Journal Citation Database

Seo Tae-Sul ; Jung Eun-Gyeong ; Kim Hwanmin
Journal of Information Science Theory and Practice, vol. 1, iss. 2, 2013, pp. 58-68
 
5. RELATIONSHIP BETWEEN RADIATION INDUCTED YIELD STRENGTH INCREMENT AND CHARPY TRANSITION TEMPERATURE SHIFT IN REACTOR PRESSURE VESSEL STEELS OF KOREAN NUCLEAR POWER PLANTS

Lee, Gyeong-Geun;Lee, Yong-Bok;Kwon, Jun-Hyun;
Nuclear Engineering and Technology, vol. 44, iss. 5, 2012, pp. 543-550
 
6. INVESTIGATION ON MATERIAL DEGRADATION OF ALLOY 617 IN HIGH TEMPERATURE IMPURE HELIUM COOLANT

Kim, Dong-Jin;Lee, Gyeong-Geun;Jeong, Su-Jin;Kim, Woo-Gon;Park, Ji-Yeon;
Nuclear Engineering and Technology, vol. 43, iss. 5, 2011, pp. 429-436
 
7. 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
 
8. WOLSONG LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE DISPOSAL CENTER: PROGRESS AND CHALLENGES

Park, Jin-Beak;Jung, Hae-Ryong;Lee, Eun-Young;Kim, Chang-Lak;Kim, Geon-Young;Kim, Kyung-Su;Koh, Yong-Kwon;Park, Kyung-Woo;Cheong, Jae-Hak;Jeong, Chan-Woo;Choi, Jong-Soo;Kim, Kyung-Deok;
Nuclear Engineering and Technology, vol. 41, iss. 4, 2009, pp. 477-492
 
9. MULTISCALE MODELING OF RADIATION EFFECTS ON MATERIALS: PRESSURE VESSEL EMBRITTLEMENT

Kwon, Jun-Hyun;Lee, Gyeong-Geun;Shin, Chan-Sun;
Nuclear Engineering and Technology, vol. 41, iss. 1, 2009, pp. 11-20
 
10. VERIFICATION OF PLC PROGRAMS WRITTEN IN FBD WITH VIS

Yoo, Jun-Beom;Cha, Sung-Deok;Jee, Eun-Kyung;
Nuclear Engineering and Technology, vol. 41, iss. 1, 2009, pp. 79-90