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- Kim, Ji Hyun
- UNIST Nuclear Innovative Materials Lab.
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Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
- Author(s)
- Lee, Tae Hyun, Ryu, Kyung Ha, Kim, Hong Deok, Hwang, Il Soon, Kim, Ji Hyun, Lee, Min Ho, Choi, Sungyeol
- Issued Date
- 2019-08
- Citation
- NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.5, pp.1381 - 1389
- 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 ELT's detection capabilities for SCC in laboratory-degraded SG tubing in high temperature and high pressure aqueous environment.
- Publisher
- KOREAN NUCLEAR SOC
- ISSN
- 1738-5733
- Keyword (Author)
- Stress corrosion cracking, Eddy current tests, Steam generators, PWR, Alloy 600
- Keyword
- CORROSION, POTENTIALS, PH
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