Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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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)
  • Received : 2019.01.06
  • Accepted : 2019.03.07
  • Published : 2019.06.25
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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.

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References

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