Preliminary PINC(Program for the Inspection of Nickel Alloy Components) RRT(Round Robin Test) - Pressurizer Dissimilar Metal Weld - |
Kim, Kyung-Cho
(Mechanical and Material Engineering Department, Korea Institute of Nuclear Safety)
Kang, Sung-Sik (Mechanical and Material Engineering Department, Korea Institute of Nuclear Safety) Shin, Ho-Sang (Mechanical and Material Engineering Department, Korea Institute of Nuclear Safety) Chung, Ku-Kab (Mechanical and Material Engineering Department, Korea Institute of Nuclear Safety) Song, Myung-Ho (Mechanical and Material Engineering Department, Korea Institute of Nuclear Safety) Chung, Hae-Dong (Mechanical and Material Engineering Department, Korea Institute of Nuclear Safety) |
1 | NRC Information Notice 2004-11 (2006) Cracking III Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle, United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation |
2 | Jenssen, A. et al. (2002) Structural Assessment of Defected Nozzle to Safe-End Welds in Ringhals 3 and 4, Proceedings of Fontevraud V International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, SFEN, pp. 43-54 |
3 | Bamford, W. and Hall, J. (2003) A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends, 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors |
4 | Buisine, D. et al. (1993) Stress Corrosion Cracking in the Vesses Closure Head Penetrations of French PWRs, Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors |
5 | NRC Information Notice 2000-17 (2000) Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. SUMMER, United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation |
6 | Shah, V. N. et al. (1994) Assessment of Pressurized Water Reactor Control Rod Drive Mechanism Nozzle Cracking, prepared for U.S. Nuclear Regulatory Commission, Safety Programs Division, NUREG/CR-6245, EGG-2715 |
7 | Amzallag, C. et al. (2002) Stress Corrosion Life Experience of 182 and 82 Welds in French PWRs, Proceedings Fontevraud International Symposium Number 5 |
8 | USNRC Website http://www.nrc.govlreactors/operating/ops-experience/pressure-boundary-integrity/ weld-issues/lindex.html, Reactor Coolant System Weld Issues |
9 | Thomas, L. E. et al. (2003) High-Resolution Analytical Electron Microscopy Characterization of Environmentally Assiasted Cracks in Alloy 182 Weldments, Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Waster Reactros, ANS |