J. Mater. Sci. Technol. ›› 2020, Vol. 40: 1-14.DOI: 10.1016/j.jmst.2019.08.035

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Microstructure and stress corrosion cracking of a SA508-309L/308L-316L dissimilar metal weld joint in primary pressurized water reactor environment

Lijin Dongab, Cheng Maa, Qunjia Penga*(), En-Hou Hana, Wei Kea   

  1. a Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, China
    b School of Materials and Engineering, Southwest Petroleum University, Chengdu, 610500, China
  • Received:2019-06-21 Revised:2019-08-07 Accepted:2019-08-20 Published:2020-03-01 Online:2020-04-01
  • Contact: Peng Qunjia

Abstract:

Stress corrosion cracking (SCC) of an SA508-309 L/308 L-316 L dissimilar metal weld joint in primary pressurized water reactor environment was investigated by the interrupted slow strain rate tension tests following a microstructure characterization. The 308 L weld metal shows a higher content of δ ferrite than the 309 L weld metal. In addition, no obvious Cr-depletion but carbides precipitation at γ/δ phase boundaries was observed in both 308 L and 309 L weld metals. The slow strain rate tension tests showed that the SCC susceptibility of the base and weld metals of the dissimilar metal weld joint follows the order of SA508 < 308 L weld metal < the heat affected zone of 316 L base metal < 309 L weld metal. The higher SCC susceptibility of 309 L weld metal than that of 308 L weld metal is likely due to the lower content of δ ferrite. In addition, a preferential SCC initiation in the 309 L weld metal adjacent to 308 L weld metal is attributed to few carbides in this region.

Key words: Dissimilar metal weld joint, Stress corrosion cracking, Microstructure, Primary pressurized water reactor, environment