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http://dx.doi.org/10.1016/j.net.2019.03.005

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing  

Lee, Tae Hyun (Korea Institute of Machinery and Materials)
Ryu, Kyung Ha (Korea Institute of Machinery and Materials)
Kim, Hong Deok (Central Research Institute of Korea Hydro & Nuclear Power)
Hwang, Il Soon (Department of Nuclear Engineering, Seoul National University)
Kim, Ji Hyun (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology)
Lee, Min Ho (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
Choi, Sungyeol (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
Publication Information
Nuclear Engineering and Technology / v.51, no.5, 2019 , pp. 1381-1389 More about this Journal
Abstract
Stress corrosion cracking (SCC) widely found in both primary and secondary sides of steam generator (SG) tubing in pressurized water reactors (PWR) has become an important safety issue. Using eddy-current tests (ECTs), non-destructive evaluations are performed for the integrity management of SG tubes against intergranular SCC. To enhance the reliability of ECT, this study investigates the effects of oxide films on ECT's detection capabilities for SCC in laboratory-degraded SG tubing in high temperature and high pressure aqueous environment.
Keywords
Stress corrosion cracking; Eddy current tests; Steam generators; PWR; Alloy 600;
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  • Reference
1 M. Kemppainen, I. Virkkunen, J. Pitkanen, R. Paussu, H. Hanninen, Nucl. Eng. Des. 224 (2003) 105.   DOI
2 J. Wale, Crack characterisation for in-service inspection planning-an update (No. SKI-R-06-24), Swedish Nuclear Power Inspectorate, 2006.
3 I.S. Hwang, Embitterment Mechanisms of Nickel-Base Alloys in Water, Ph.D. Thesis, MIT, Massachusetts, 1987.
4 T.H. Lee, I.S. Hwang, H.S. Chung, J.Y. Park, J. Press. Vessel Technol. 130 (2008) 1.
5 ASTM, Standard Test Method for Measurement of Fracture Toughness (E1820-01), American Society for Testing and Materials, Annual Book of ASTM Standards, West Conshohocken, PA, 2001.
6 I.S. Hwang, S.U. Kwon, S.G. Lee, J.H. Kim, Corrosion 57 (2001) 787.   DOI
7 S.H. Oh, In-situ EIS of Oxide Film Formed on Nickel-Plated Alloy 600, M.S. Thesis, Seoul National University, Seoul, 2002.
8 D.R. Diercks, S. Bakhtiari, K.E. Kasza, D.S. Kupperman, S. Majumdar, J.Y. Park, W.J. Shack, Steam Generator Tube Integrity Program: Annual Report (NUREG/CR-6511), U.S. Nuclear Regulatory Commission, Washington, D.C., 1999.
9 L.W. Niedrach, J. Electrochem. Soc. 129 (1982) 1445.   DOI
10 L.W. Niedrach, W.H. Stoddard, Corrosion 41 (1985) 45.   DOI
11 D.M. Himmelblau, J. Chem. Eng. Data 5 (1960) 10.   DOI
12 M.E. Orazem, B. Tribollet, Electrochemical Impedance Spectroscopy, Wiley-Interscience, New York, 2008.
13 P. Combrade, P.M. Scott, M. Foucault, E. Andrieu, P. Marcus, Oxidation of Ni base alloys in PWR water: oxide layers and associated damage to the base metal, in: 12th International Conference on Environmental Degradation of Materials in Nuclear Power System, Salt Lake City, Utah, August 14-18, 2005.
14 M. Linder, T. Hocker, L. Holzer, O. Pecho, K.A. Friedrich, T. Morawietz, R. Hiesgen, R. Kontic, B. Iwanschitz, A. Mai, J.A. Schuler, Solid State Ionics 283 (2015).
15 EPRI, Steam Generator Eddy Current Data Analysis Performance Demonstration, Electric Power Research Institute, Palo Alto, 1995.