TECHNIQUES FOR INTERGRANULAR CRACK FORMATION AND ASSESSMENT IN ALLOY 600 BASE AND ALLOY 182 WELD METALS |
LEE, TAE HYUN
(Korea Institute of Machinery & Materials (KIMM))
HWANG, IL SOON (Department of Nuclear Engineering, Seoul National University) KIM, HONG DEOK (Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd.) KIM, JI HYUN (School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) |
1 | D.R. Diercks, W.J. Shack, J. Muscara, Overview of steam generator tube degradation and integrity issues, Nuclear Engineering and Design 194 (1999) 19-30. DOI |
2 | D. Straub, M.H. Faber, Modeling dependency in inspection performance, in: 9th International Conference on Applications of Statistics and Probability in Civil Engineering, vol. 2, 2003, pp. 1123e1130. San Francisco, USA. |
3 | J.R. Rudlin, L.C. Wolstenholme, Development of statistical probability of detection models using actual trial inspection data, British Journal of Non-Destructive Testing 34 (1992) 583-589. |
4 | P.G. Heasler, Piping Inspection Round Robin, NUREG/CR-5068, U.S. Nuclear Regulatory Commission, Washington, DC, 1994. |
5 | R. Clark, W.D. Dover, L.J. Bond, The effect of crack closure on the reliability of NDT predictions of crack size, NDT International 20 (1987) 269-275. |
6 | I. Virkkunen, M. Kemppainen, J.E. Pitkanen, Effect of Crack Opening on UT Response, in: 9th European Conference on NDT, Berlin, Germany, Th.4.4.2, 2006. |
7 | H. Yoneyama, Comparison of echo heights between fatigue crack and EDM notch, Journal of High Pressure Institute of Japan 41 (2003) 115-122. |
8 | F.L. Becker, C. Latiolais, Experience with inspection qualifications for austenitic piping, Nuclear Engineering and Design 195 (2000) 227-232. DOI |
9 | Z. Chen, L. Janousek, N. Yusa, K. Miya, A nondestructive strategy for the distinction of natural fatigue and stress corrosion cracks based on signals from eddy current testing, Journal of Pressure Vessel Technology 129 (2007) 719-728. DOI |
10 | M. Kemppainen, I. Virkkunen, J. Pitkanen, K. Hukkanen, H. Hanninen, Production of realistic artificial flaw in inconel 600 safe-end, in: Proceedings of the Conference on Vessel Penetration Inspection, Crack Growth and Repair, Washington D.C., Gaithersburg, USA, 2003, pp. 181e196. NUREG/CP-0191. |
11 | M. Kemppainen, I. Virkkunen, J. Pitkanen, K. Hukkanen, H. Hanninen, Advanced flaw production method for inservice inspection qualification mock-ups, Nuclear Engineering and Design 224 (2003) 105-117. DOI |
12 | T. Kubo, N. Saito, H. Sakamoto, S. Tanaka, Evaluation of sensitization of Ni-base weld metal by the EPR method, in: 10th International Conference on Environment Degradation of Materials in Nuclear Power Systems Water Reactors, Lake Tahoe, Nevada, USA, on CD-ROM, 2001. |
13 | T.H. Lee, I.S. Hwang, H.S. Chung, J.Y. Pak, A new technique for intergranular crack formation in alloy 600 steam generator tubing, Journal of Pressure Vessel Technology 130 (2008) 011403. DOI |
14 | R.G. Ballinger, I.S. Hwang, Characterization of Microstructure and IGSCC of Alloy 600 Steam Generator Tubing, EPRI TR-101983, Electric Power Research Institute, Palo Alto, CA, 1993. |
15 | W.T. Tsai, C.L. Yu, J.I. Lee, Effect of heat treatment on the sensitization of Alloy 182 weld, Scripta Materialia 53 (2005) 505-509. DOI |
16 | D.R. Diercks, W.J. Shack, J. Muscara, Steam Generator Tube Integrity Program, Annual Report, NUREG/CR-6511, vol. 4, U.S. Nuclear Regulatory Commission, Washington, DC, 1999. ANL-98/15. |
17 | I.S. Hwang, S.U. Kwon, J.H. Kim, S.G. Lee, An intraspecimen method for the statistical characterization of stress corrosion crack initiation behavior, Corrosion 57 (2001) 787-793. DOI |
18 | J. Wale, Crack Characterisation for In-service Inspection PlanningdAn Update, SKI Report 2006:24, Swedish Nuclear Power Inspectorate, Stockholm, Sweden, 2006. |
19 | J.A. Ogilvy, Model for the ultrasonic inspection of rough defects, Ultrasonics 27 (1989) 69-79. DOI |