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Evaluation of Primary Water Stress Corrosion Cracking Resistance of Three Heats of Alloy 600 in 400 °C Hydrogenated Steam Condition

1
Central Research Institute, Korea Hydro and Nuclear Co., Ltd., 70, 1312-gil, Yuseong-daero, Yuseong-gu, Daejeon 34101, Korea
2
Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 34141, Korea
*
Author to whom correspondence should be addressed.
Metals 2018, 8(2), 130; https://doi.org/10.3390/met8020130
Received: 6 December 2017 / Revised: 30 January 2018 / Accepted: 5 February 2018 / Published: 12 February 2018
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Abstract

For Alloy 600, primary water stress corrosion cracking (PWSCC) is one of the key material degradation mechanisms in pressurized water reactors (PWRs). To identify the governing factors of PWSCC resistance, a systematic investigation into the role of each factor was performed. A PWSCC initiation test was performed for 3 heats of Alloy 600 in the 400 °C hydrogenated steam condition. Based on the test results, the effects of known factors like chemical composition, mechanical strength, grain boundary carbide coverage, grain boundary character, and surface cold work on PWSCC resistance were discussed. In addition, surface oxide morphology and penetrative oxide depth was compared. From this study, grain boundary character was considered to be the most dominant factor affecting the PWSCC resistance. View Full-Text
Keywords: Alloy 600; primary water stress corrosion cracking; hydrogenated steam; grain boundary character Alloy 600; primary water stress corrosion cracking; hydrogenated steam; grain boundary character
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Yun, E.; Chung, H.; Jang, C. Evaluation of Primary Water Stress Corrosion Cracking Resistance of Three Heats of Alloy 600 in 400 °C Hydrogenated Steam Condition. Metals 2018, 8, 130.

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