2Effects of composition and microstructure on oxidation and stress corrosion cracking susceptibility of stainless steel claddings in hydrogenated PWR primary water

JOURNAL OF NUCLEAR MATERIALS

卷:553

Article

Cui, Tongming^1,2  Xu, Xinhe^1,2  Ma, Jiarong^1,2  Lu, Zhanpeng^1,2  Tang, Yuanjie^1,2  Zhang, Kun^1,2  Yang, Shuangliang³  Zhong, Zhiming³  Lozano-Perez, Sergio⁴  Shoji, Tetsuo⁵ 

[1] Shanghai Univ, Sch Mat Sci & Engn, Inst Mat, Shanghai 200072, Peoples R China

[2] Shanghai Univ, State Key Lab Adv Special Steels, Shanghai 200072, Peoples R China

[3] State Nucl Power Plant Serv Co, 888 Tianlin Rd, Shanghai 200233, Peoples R China

[4] Univ Oxford, Dept Mat, Parks Rd, Oxford OX1 3PH, England

[5] Tohoku Univ, New Ind Creat Hatchery Ctr, Sendai, Miyagi 9808579, Japan

关键词: Pressurized water reactor;    Stainless steel cladding;    Oxidation;    Stress corrosion cracking;    Ferrite;   

DOI  :  10.1016/j.jnucmat.2021.153057

来源: Elsevier

【 摘 要 】

Oxidation resistance and stress corrosion cracking (SCC) susceptibility of A508III-309 L/308 L stainless steel (SS) claddings were investigated in simulated pressurized water reactor (PWR) primary water following a microstructure characterization. Preferential oxidation of slip bands was observed in 309 L SS. The oxidation resistance of 309 L SS was found to be lower than that of 308 L SS due to the higher Crand ferrite-content in 308 L SS than in 309 L SS after cladding. There was no indication of SCC for low alloy steel (LAS) after slow strain rate tensile (SSRT) tests. The presence of type-I and type-II boundaries, composition dilution and less delta-ferrite content synergistically contributed to increasing the SCC susceptibility of 309 L SS cladding. The effect of chemical composition and microstructure on SCC performance of the SS claddings was discussed. (C) 2021 Published by Elsevier B.V.

【 授权许可】

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