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

Jong Sung Kim; Ji Soo Kim; Jun Young Jeon; Yun Jae Kim

doi:10.1016/j.net.2016.03.003

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

Jong Sung Kim, Ji Soo Kim, Jun Young Jeon, Yun Jae Kim

Research output: Contribution to journal › Article › peer-review

4 Citations (Scopus)

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.

Original language	English
Pages (from-to)	1036-1046
Number of pages	11
Journal	Nuclear Engineering and Technology
Volume	48
Issue number	4
DOIs	https://doi.org/10.1016/j.net.2016.03.003
Publication status	Published - 2016 Aug 1
Externally published	Yes

Keywords

Alloy 600
Primary Water Stress Corrosion Cracking (PWSCC)
SCC Growth Simulation
Steam Generator Tube
Stress Triaxiality

ASJC Scopus subject areas

Nuclear Energy and Engineering

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10.1016/j.net.2016.03.003

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title = "PWSCC Growth Assessment Model Considering Stress Triaxiality Factor for Primary Alloy 600 Components",

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.",

keywords = "Alloy 600, Primary Water Stress Corrosion Cracking (PWSCC), SCC Growth Simulation, Steam Generator Tube, Stress Triaxiality",

author = "Kim, {Jong Sung} and Kim, {Ji Soo} and Jeon, {Jun Young} and Kim, {Yun Jae}",

note = "Funding Information: This work was supported by the Nuclear Energy Technology Innovation Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government Ministry of Trade, Industry and Energy (No. 2012T100100443 ). This work was supported by the Nuclear Power Core Technology Development Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) , granted financial resource from the Ministry of Trade, Industry & Energy, Republic of Korea (No. 20131520000140 ). Publisher Copyright: {\textcopyright} 2016",

year = "2016",

month = aug,

day = "1",

doi = "10.1016/j.net.2016.03.003",

language = "English",

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pages = "1036--1046",

journal = "Nuclear Engineering and Technology",

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AU - Kim, Jong Sung

AU - Kim, Ji Soo

AU - Jeon, Jun Young

AU - Kim, Yun Jae

N1 - Funding Information: This work was supported by the Nuclear Energy Technology Innovation Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government Ministry of Trade, Industry and Energy (No. 2012T100100443 ). This work was supported by the Nuclear Power Core Technology Development Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) , granted financial resource from the Ministry of Trade, Industry & Energy, Republic of Korea (No. 20131520000140 ). Publisher Copyright: © 2016

PY - 2016/8/1

Y1 - 2016/8/1

N2 - 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.

AB - 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.

KW - Alloy 600

KW - Primary Water Stress Corrosion Cracking (PWSCC)

KW - SCC Growth Simulation

KW - Steam Generator Tube

KW - Stress Triaxiality

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

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ASJC Scopus subject areas

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