Browse > Article

Current Status and Investigation of International Co-operative Research Program-PINC(Program for the Inspection of Nickel Alloy Components)  

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)
Publication Information
Abstract
After several PWSCCs were found in Bugey(France), Ringhals(Sweden), Tihange(Belgium), Oconee, Arkansas, Crystal Fever, Davis-Basse, VC Summer(U.S.A.), Thuruga(Japan), USNRC and PNNL started the research on PWSCC, that is, PINC project. The aim of this project is to fabricate and obtain representative NDE mock-ups with flaws to simulate tight PWSCC cracks, to identify and quantitatively assess NDE methods for accurately detecting, sizing and characterizing tight cracks such as PWSCC, to document the range of locations and crack morphologies associated with PWSCC and observed responses and to incorporate findings from other ongoing PWSCC research programs, as appropriate. By participating in PINC project, Korean morphology technique about PWSCC and NDE technique have improved and become similar lever with other advanced country. Therefore, the evaluation technique of integrity for nickel alloy component has been improved by cooperation with university, research institute and industries.
Keywords
BMI(Bottom Mounted Instrumentation); DMW(Dissimilar Metal Weld); PINC(Program for the Inspection of Nickel Alloy Components); PWSCC(Primarily Water Stress Corrosion Crack);
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
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'