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PWSCC Growth Assessment Model Considering Stress Triaxiality Factor for Primary Alloy 600 Components

Authors
Kim, Jong-SungKim, Ji-SooJeon, Jun-YoungKim, Yun-Jae
Issue Date
8월-2016
Publisher
KOREAN NUCLEAR SOC
Keywords
Alloy 600; Primary Water Stress Corrosion Cracking (PWSCC); SCC Growth Simulation; Steam Generator Tube; Stress Triaxiality
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.4, pp.1036 - 1046
Indexed
SCIE
SCOPUS
KCI
Journal Title
NUCLEAR ENGINEERING AND TECHNOLOGY
Volume
48
Number
4
Start Page
1036
End Page
1046
URI
https://scholar.korea.ac.kr/handle/2021.sw.korea/87953
DOI
10.1016/j.net.2016.03.003
ISSN
1738-5733
Abstract
We propose a primary water stress corrosion cracking (PWSCC) initiation model of Alloy 600 that considers the stress triaxiality factor to apply to finite element analysis. We investigated the correlation between stress triaxiality effects and PWSCC growth behavior in cold-worked Alloy 600 stream generator tubes, and identified an additional stress triaxiality factor that can be added to Garud's PWSCC initiation model. By applying the proposed PWSCC initiation model considering the stress triaxiality factor, PWSCC growth simulations based on the macroscopic phenomenological damage mechanics approach were carried out on the PWSCC growth tests of various cold-worked Alloy 600 steam generator tubes and compact tension specimens. As a result, PWSCC growth behavior results from the finite element prediction are in good agreement with the experimental results. Copyright (C) 2016, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society.
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공과대학 (기계공학부)
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