首页|Correlating oxidation resistance to stress corrosion cracking of 309L and 308L stainless steel claddings in simulated PWR primary water

Correlating oxidation resistance to stress corrosion cracking of 309L and 308L stainless steel claddings in simulated PWR primary water

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  • NSTL
  • Elsevier
Stress corrosion cracking (SCC) growth behaviors of 309L and 308L stainless steel claddings in simulated pressurized water reactor primary water at 325 ? and 350 ? were investigated by compact tension specimens and correlated to the oxide film properties in terms of microstructure. SCC growth rates of 308L were much lower than those of 309L. 309L showed typical intergranular SCC characteristics. The high SCC resistance of 308L was related to the low oxidation rate and crack tip retardation due to the presence of highly networked ferrites. The lower Cr content, as well as less and sparsely distributed delta-ferrite phases in 309L than in 308L, led to more severe local oxidation penetration beneath the metal/inner oxide interface and more porous inner oxide, therefore, contributed to its enhanced SCC growth in 309L. The SCC growth rate results by compact tension specimens are consistent with those by slow strain rate tests. (C)& nbsp;2022 Published by Elsevier B.V.

Stainless steel claddingsPressurized water reactorHigh-temperature waterStress corrosion crackingCrack growth rateOxide filmMETAL WELD JOINTLOW-ALLOY STEELDISSIMILAR METALFUSION BOUNDARYOXIDE-FILMSTEMPERATUREBEHAVIORMICROSTRUCTURESUSCEPTIBILITYINITIATION

Zheng, Hui、Zhong, Zhimin、Shoji, Tetsuo、Cui, Tongming、Xu, Xinhe、Pan, Deng、Lu, Zhanpeng、Ma, Jiarong、Yang, Shuangliang

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State Nucl Power Plant Serv Co

Tohoku Univ

Shanghai Univ

2022

10.1016/j.jnucmat.2022.153509

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN：0022-3115
年,卷(期)：2022.561
  • 5
  • 56