TY - JOUR
T1 - Characterization of microstructure, local deformation and microchemistry in Alloy 690 heat-affected zone and stress corrosion cracking in high temperature water
AU - Lu, Zhanpeng
AU - Chen, Junjie
AU - Shoji, Tetsuo
AU - Takeda, Yoichi
AU - Yamazaki, Seiya
N1 - Funding Information:
This work has been partly supported by PEAC-E and POLIM programs. Z.P. Lu acknowledges the support of the Ph.D. Programs Foundation of Ministry of Education of China No. 20123108110021 and the International Cooperative Project sponsored by Science and Technology Commission of Shanghai Municipality No. 13520721200 .
Publisher Copyright:
© 2015 Elsevier B.V.
PY - 2015/6/29
Y1 - 2015/6/29
N2 - With increasing the distance from the weld fusion line in an Alloy 690 heat-affected zone, micro-hardness decreases, kernel average misorientation decreases and the fraction of Σ3 boundaries increases. Chromium depletion at grain boundaries in the Alloy 690 heat-affected zone is less significant than that in an Alloy 600 heat-affected zone. Alloy 690 heat-affected zone exhibits much higher IGSCC resistance than Alloy 600 heat-affected zone in simulated pressurized water reactor primary water. Heavily cold worked Alloy 690 exhibits localized intergranular stress corrosion cracking. The effects of metallurgical and mechanical properties on stress corrosion cracking in Alloy 690 are discussed.
AB - With increasing the distance from the weld fusion line in an Alloy 690 heat-affected zone, micro-hardness decreases, kernel average misorientation decreases and the fraction of Σ3 boundaries increases. Chromium depletion at grain boundaries in the Alloy 690 heat-affected zone is less significant than that in an Alloy 600 heat-affected zone. Alloy 690 heat-affected zone exhibits much higher IGSCC resistance than Alloy 600 heat-affected zone in simulated pressurized water reactor primary water. Heavily cold worked Alloy 690 exhibits localized intergranular stress corrosion cracking. The effects of metallurgical and mechanical properties on stress corrosion cracking in Alloy 690 are discussed.
KW - Heat-affected zone
KW - High temperature water
KW - Nickel-base alloy
KW - Pressurized water reactor
KW - Stress corrosion cracking
KW - Welding
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U2 - 10.1016/j.jnucmat.2015.06.025
DO - 10.1016/j.jnucmat.2015.06.025
M3 - Article
AN - SCOPUS:84933514872
SN - 0022-3115
VL - 465
SP - 471
EP - 481
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -