Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

Ki-Deuk Min; Seokmin Hong; Dae-Whan Kim; Bong-Sang Lee; Seon-Jin Kim

doi:10.1016/j.net.2017.01.019

Nuclear Engineering and Technology (Jun 2017)

Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

Ki-Deuk Min,
Seokmin Hong,
Dae-Whan Kim,
Bong-Sang Lee,
Seon-Jin Kim

Affiliations

Ki-Deuk Min: Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division, 989-111, Daedeok-daero, Daejeon 34057, Republic of Korea
Seokmin Hong: Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division, 989-111, Daedeok-daero, Daejeon 34057, Republic of Korea
Dae-Whan Kim: Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division, 989-111, Daedeok-daero, Daejeon 34057, Republic of Korea
Bong-Sang Lee: Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division, 989-111, Daedeok-daero, Daejeon 34057, Republic of Korea
Seon-Jin Kim: Hanyang University, Division of materials science and engineering, 222, Wangsimni-ro, Seoul 04763, Republic of Korea

DOI: https://doi.org/10.1016/j.net.2017.01.019
Journal volume & issue: Vol. 49, no. 4
pp. 752 – 759

Abstract

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The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evaluated under the operating conditions of a pressurized water reactor (PWR). These two materials showed different fatigue crack growth rates (FCGRs) according to the changes in dissolved oxygen content and frequency. Under the simulated PWR conditions for normal operation, the FCGR of S347N was lower than that of S347 and insensitive to the changes in PWR water conditions. The higher yield strength and better corrosion resistance of the nitrogen-alloyed Type 347 stainless steel might be a main cause of slower FCGR and more stable properties against changes in environmental conditions.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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