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KEYWORD_EN:Inspection car 10 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. DEVELOPMENT OF AN AMPHIBIOUS ROBOT FOR VISUAL INSPECTION OF APR1400 NPP IRWST STRAINER ASSEMBLY

Jang, You Hyun;Kim, Jong Seog;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 439-446
 
3. ON-POWER DETECTION OF PIPE WALL-THINNED DEFECTS USING IR THERMOGRAPHY IN NPPS

Kim, Ju Hyun;Yoo, Kwae Hwan;Na, Man Gyun;Kim, Jin Weon;Kim, Kyeong Suk;
Nuclear Engineering and Technology, vol. 46, iss. 2, 2014, pp. 225-234
 
4. VISUALIZATION OF INTERNAL DEFECTS IN PLATE-TYPE NUCLEAR FUEL BY USING NONCONTACT OPTICAL INTERFEROMETRY

PARK SEUNG-KYU ; PARK NAK-GYU ; BAIK SUNG-HOON ; KANG YOUNG-JUNE
Nuclear Engineering and Technology, vol. 45, iss. 3, 2013, pp. 361-366
 
5. A FEASIBILITY STUDY ON THE ADVANCED PERFORMANCE INDICATOR CONCEPT FOR IMPROVING KINS SAFETY PERFORMANCE INDICATORS (SPI)

Lee, Yong-Suk;Cho, Nam-Chul;Chung, Dae-Wook;
Nuclear Engineering and Technology, vol. 43, iss. 2, 2011, pp. 105-132
 
6. MEASUREMENT OF NUCLEAR FUEL ROD DEFORMATION USING AN IMAGE PROCESSING TECHNIQUE

Cho, Jai-Wan;Choi, Young-Soo;Jeong, Kyung-Min;Shin, Jung-Cheol;
Nuclear Engineering and Technology, vol. 43, iss. 2, 2011, pp. 133-140
 
7. DEVELOPMENT OF A STEAM GENERATOR TUBE INSPECTION ROBOT WITH A SUPPORTING LEG

Shin, Ho-Cheol;Jeong, Kyung-Min;Jung, Seung-Ho;Kim, Seung-Ho;
Nuclear Engineering and Technology, vol. 41, iss. 1, 2009, pp. 125-134
 
8. FRENCH PROGRAM TOWARDS AN INNOVATIVE SODIUM COOLED FAST REACTOR

Martin, Ph.;Anzieu, P.;Rouault, J.;Serpantie, J.P.;Verwaerde, D.;
Nuclear Engineering and Technology, vol. 39, iss. 4, 2007, pp. 237-248
 
9. Nonlinear Flexural Analysis of PSC Test Beams in CANDU Nuclear Power Plants

Bae, In-Hwan;Choi, In-Kil;Seo, Jeong-Moon;
Nuclear Engineering and Technology, vol. 32, iss. 2, 2000, pp. 180-190
 
10. Demonstration of EPRI CHECWORKS Code to Predict FAC Wear of Secondary System Pipings of a Nuclear Power Plant

Lee, Sung-Ho;Seong Jegarl;Chung, Han-Sub;
Nuclear Engineering and Technology, vol. 31, iss. 4, 1999, pp. 375-384
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