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KEYWORD_EN:Accelerated thermal aging CSPE 8 result(s) found
 
1. ASSESSMENT OF WALL-THINNING IN CARBON STEEL PIPE BY USING LASER-GENERATED GUIDED WAVE

Kim, Do-Youn;Cho, Youn-Ho;Lee, Joon-Hyun;
Nuclear Engineering and Technology, vol. 42, iss. 5, 2010, pp. 546-551
 
2. A REVIEW OF CANDU FEEDER WALL THINNING

Chung, Han-Sub;
Nuclear Engineering and Technology, vol. 42, iss. 5, 2010, pp. 568-575
 
3. CFD APPLICATION TO THE REGULATORY ASSESSMENT OF FAC-CAUSED CANDU FEEDER PIPE WALL THINNING ISSUE

Kang, Dong-Gu;Jo, Jong-Chull;
Nuclear Engineering and Technology, vol. 40, iss. 1, 2008, pp. 37-48
 
4. 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, vol. 37, iss. 4, 2005, pp. 375-384
 
5. Piping Failure Frequency Analysis for the Main Feedwater System in Domestic Nuclear Power Plants

Choi Sun Yeong;Choi Young Hwan;
Nuclear Engineering and Technology, vol. 36, iss. 1, 2004, pp. 112-120
 
6. Flow-Accelerated Corrosion Behavior of SA106 Gr.C Steel in Alkaline Solution Characterized by Rotating Cylinder Electrode

Kim, Jun-Hwan;Kim, In-Sup;
Nuclear Engineering and Technology, vol. 32, iss. 6, 2000, pp. 595-604
 
7. Evaluation of Piping Integrity in Thinned Main Feedwater Pipes

Park, Young-Hwan;Kang, Suk-Chull;
Nuclear Engineering and Technology, vol. 32, iss. 1, 2000, pp. 67-76
 
8. 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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