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

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

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 tube...

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Main Authors: Tae Hyun Lee, Kyung Ha Ryu, Hong Deok Kim, Il Soon Hwang, Ji Hyun Kim, Min Ho Lee, Sungyeol Choi
Format: Article
Language:English
Published: Elsevier 2019-08-01
Series:Nuclear Engineering and Technology
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573319300154
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spelling doaj-b5436ba18e624ea2b0d100f1afc2f97a2020-11-24T21:52:49ZengElsevierNuclear Engineering and Technology1738-57332019-08-0151513811389Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubingTae Hyun Lee0Kyung Ha Ryu1Hong Deok Kim2Il Soon Hwang3Ji Hyun Kim4Min Ho Lee5Sungyeol Choi6Korea Institute of Machinery and Materials, 156 Gajeongbuk-ro, Yuseong, Daejeon, 34103, South KoreaKorea Institute of Machinery and Materials, 156 Gajeongbuk-ro, Yuseong, Daejeon, 34103, South KoreaCentral Research Institute of Korea Hydro & Nuclear Power, 1312-70 Yusengdae-ro, Yuseong, Daejeon, 34101, South KoreaDepartment of Nuclear Engineering, Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul, 08826, South KoreaDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, South KoreaDepartment of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, South KoreaDepartment of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, South Korea; Corresponding author.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 600http://www.sciencedirect.com/science/article/pii/S1738573319300154
collection DOAJ
language English
format Article
sources DOAJ
author Tae Hyun Lee
Kyung Ha Ryu
Hong Deok Kim
Il Soon Hwang
Ji Hyun Kim
Min Ho Lee
Sungyeol Choi
spellingShingle Tae Hyun Lee
Kyung Ha Ryu
Hong Deok Kim
Il Soon Hwang
Ji Hyun Kim
Min Ho Lee
Sungyeol Choi
Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
Nuclear Engineering and Technology
author_facet Tae Hyun Lee
Kyung Ha Ryu
Hong Deok Kim
Il Soon Hwang
Ji Hyun Kim
Min Ho Lee
Sungyeol Choi
author_sort Tae Hyun Lee
title Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
title_short Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
title_full Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
title_fullStr Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
title_full_unstemmed Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing
title_sort effect of oxide film on ect detectability of surface igscc in laboratory-degraded alloy 600 steam generator tubing
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2019-08-01
description 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
url http://www.sciencedirect.com/science/article/pii/S1738573319300154
work_keys_str_mv AT taehyunlee effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
AT kyungharyu effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
AT hongdeokkim effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
AT ilsoonhwang effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
AT jihyunkim effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
AT minholee effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
AT sungyeolchoi effectofoxidefilmonectdetectabilityofsurfaceigsccinlaboratorydegradedalloy600steamgeneratortubing
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