Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

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The corrosion behaviour of as-welded and thermally aged ER316L in simulated pressurised water reactor (PWR) primary water was studied. Significant spinodal decomposition without G-phase was observed after thermal ageing. Thermal ageing does not change the duplex oxide film formation mechanism on ER316L. Slightly higher Fe and Ni concentrations are in the external oxide particles of thermally aged ER316L. More Ni enrichment is in ferrite of as-welded ER316L beneath the ferrite/inner oxide layer interface. Oxide films of thermally aged ER316L show higher point defect densities and lower EIS resistances.
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Issue Date
2020-08
Language
English
Article Type
Article
Citation

CORROSION SCIENCE, v.172, pp.108730

ISSN
0010-938X
DOI
10.1016/j.corsci.2020.108730
URI
http://hdl.handle.net/10203/281956
Appears in Collection
NE-Journal Papers(저널논문)
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