Corrosion behavior of 316 stainless steel for advanced high‐temperature water‐cooled nuclear plant

Corrosion occurs widely in the supercritical water system materials under high temperature and pressure. To select reliable candidate materials, corrosion behavior of many alloys was investigated. This study focused on investigating the corrosion behavior of 316 stainless steel (316 SS) in supercrit...

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Bibliographic Details
Published in:Surface and interface analysis 2022-07, Vol.54 (7), p.767-774
Main Authors: Yi, Guo‐Ming, Cheng, Yan‐Hai, Ren, Lu, Yang, Jinyong, Wang, Qingqing, Li, Xingsheng
Format: Article
Language:English
Subjects:
316 SS
Austenitic stainless steels
Corrosion mechanisms
High temperature
high‐temperature oxidation
Iron
Materials selection
Oxidation
Photoelectrons
Pitting (corrosion)
Reaction kinetics
Scale (corrosion)
Spectroscopy
supercritical water
Weight measurement
XPS
XRD
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Summary:Corrosion occurs widely in the supercritical water system materials under high temperature and pressure. To select reliable candidate materials, corrosion behavior of many alloys was investigated. This study focused on investigating the corrosion behavior of 316 stainless steel (316 SS) in supercritical water (798 K/24 MPa). After exposed to SCW for 200 h, the oxidation kinetics, surface morphology, and diffusion of elements were investigated by weight measurement, scanning electron microscopy (SEM), X‐ray diffraction (XRD), energy‐dispersive spectroscopy (EDS), and X‐ray photoelectron spectroscopy (XPS). The surface of 316 SS showed isolated and discontinued oxide scales. The oxide scale was determined to be a monolayer layer, and the main composition was determined to be Fe–Cr‐rich spinel with a few amounts of magnetite attached to the surface. A few pores due to pitting corrosion were found on the surface, and the oxidation mechanism was also investigated.
ISSN:0142-2421
1096-9918
DOI:10.1002/sia.7089