Current Status and Investigation of International Co-operative Research Program-PINC(Program for the Inspection of Nickel Alloy Components)
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Kim, Kyung-Cho
(Korea Institute of Nuclear Safety)
Kang, Sung-Sik (Korea Institute of Nuclear Safety) Song, Kyung-Ho (Korea Institute of Nuclear Safety) Chung, Koo-Kap (Korea Institute of Nuclear Safety) Chung, Hae-Dong (Korea Institute of Nuclear Safety) |
1 | Bamford, W. and Hall, J., '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, (2003) |
2 | V. N. Shah, A. G. Ware and A. M. Porter, '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, (1994) |
3 | A. Jenssen, K. Norrgard, C. Jansson, J. Lagerstom, G. Embring and P. Efsing, '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, (2002) |
4 | L. E. Thomas, J. S. Vetrano, S. M. Bruemmer, P. Efsing, B. Forssgren, G. Embring and K. Gott, 'High-resolution analytical electron microscopy characterization of environtally assiasted cracks in alloy 182 weldments,' Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Waster Reactros, ANS, (2003) |
5 | NRC Information Notice 2004-11: Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle, United States Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, (2006) |
6 | D. Buisine, F. Cattant, J. Champredonde, C. Pichon, C. Benhamou, A. Gelpi and M. Vaindirlis, 'Stress corrosion cracking in the vessel closure head penetrations of French PWRs,' Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (1993) |
7 | C. Amzallag, J. M. Boursier, C. Pages and C. Gimond, 'Stress corrosion life experience of 182 and 82 welds in French PWRs,' in Proceedings Fontevraud International Symposium Number 5, (2002) |
8 | NRC Information Notice 2000-17: 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, (2000) |
9 | 최성남, 김형남, 유현주, 조현준, 황원걸, '배관용접부 초음파검사 시스템 개발', 비파괴검사학회지, 제28권, 제4호, pp. 331-337, (2008) |
10 | USNRC Website http://www.nrc.gov/reactors/operating/opsexperience/pressureboundary-integrity/weld-issues/index.html, 'Reactor Coolant System Weld Issues' |
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