Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment
作者： Lijin Dong , Qunjia Peng , He Xue , En-Hou Han , Wei Ke
DOI: 10.1016/J.CORSCI.2017.12.011
关键词:
摘要: Abstract Correlation of microstructure and stress corrosion cracking (SCC) initiation behaviour the fusion boundary (FB) region in a SA508 Cl. 3-Alloy 52M weld joint primary pressurized water reactor environment was investigated. Cr-depletion at grain strength mismatch FB are two causes for SCC region. The partially mixed zone between dilution (DZ) Alloy 3 has retardation effect on initiation. This is attributed to decrease alleviation strain concentration adjacent DZ.
sci-hub.se 参考文章(56)
Yaolei Han, Jinna Mei, Qunjia Peng, En-Hou Han, Wei Ke, Effect of electropolishing on corrosion of Alloy 600 in high temperature water Corrosion Science. ,vol. 98, pp. 72- 80 ,(2015) , 10.1016/J.CORSCI.2015.05.026
E.I. Galindo-Nava, P.E.J. Rivera-Díaz-del-Castillo, A model for the microstructure behaviour and strength evolution in lath martensite Acta Materialia. ,vol. 98, pp. 81- 93 ,(2015) , 10.1016/J.ACTAMAT.2015.07.018
E.I. Galindo-Nava, P.E.J. Rivera-Díaz-del-Castillo, Understanding the factors controlling the hardness in martensitic steels Scripta Materialia. ,vol. 110, pp. 96- 100 ,(2016) , 10.1016/J.SCRIPTAMAT.2015.08.010
George A. Young, Robert A. Etien, Micah J. Hackett, Julie D. Tucker, Thomas E. Capobianco, Physical Metallurgy, Weldability, and in-Service Performance of Nickel-Chromium Filler Metals Used in Nuclear Power Systems edmn. pp. 2431- 2441 ,(2011) , 10.1007/978-3-319-48760-1_147
M. B. Toloczko, M. J. Olszta, S. M. Bruemmer, Stress Corrosion Crack Growth of Alloy 52M in Simulated PWR Primary Water 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. pp. 225- 243 ,(2011) , 10.1007/978-3-319-48760-1_14
Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack, Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment edmn. pp. 245- 266 ,(2011) , 10.1007/978-3-319-48760-1_15
Steven A. Attanasio, David S. Morton, Measurement of the Nickel/Nickel Oxide Transition in Ni-Cr-Fe Alloys and Updated Data and Correlations to Quantify the Effect of Aqueous Hydrogen on Primary Water SCC Other Information: PBD: 16 Jun 2003. ,(2003) , 10.2172/821507
Peter L. Andresen, SCC of High CR Alloys in BWR Environments Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. pp. 267- 300 ,(2011) , 10.1007/978-3-319-48760-1_16
Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack, SCC Behavior of Alloy 152 Weld in a PWR Environment Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. pp. 179- 196 ,(2011) , 10.1007/978-3-319-48760-1_12
Peter L. Andresen, Martin M. Morra, Kawaljit Ahluwalia, SCC of Alloy 690 and its Weld Metals Corrosion. pp. 161- 178 ,(2011) , 10.1007/978-3-319-48760-1_11