Published November 2016 | Version v1
Journal article

Mechanism of corrosion of 9Cr and 12Cr ferritic/martensitic steels under oxygen-saturated sodium

  • 1. Advanced Fuel Development Division, Korea Atomic Energy Research Institute (KAERI), 111 Daedeok-Daero 989beon-gil, Yuseong-Gu, Daejeon 34057 (Korea, Republic of)
  • 2. Department of Nuclear Engineering, School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST), 50 UNIST-gil, Eonyang-Eup, Ulju-Gun, Ulsan 44919 (Korea, Republic of)

Description

Highlights: • Ferritic/martensitic steels (Gr.92 and HT9) were exposed to oxygen-saturated Na. • Tests were carried out at 650 °C and 550 °C for 300 h. • Na-Cr-O compound formed in the matrix of Gr. 92 and HT9 samples. • Gr. 92 has a higher corrosion rate than HT9 in oxygen-saturated Na. • In oxygen-saturation Na, corrosion is very rapid than the reported values. - Abstract: Liquid sodium corrosion poses a major problem with liquid-sodium-cooled fast reactors. Ferritic/martensitic steels are used as cladding materials and structural materials in these reactors. Gr.92 and HT9 steels were exposed to oxygen-saturated sodium at 650 °C and 550 °C for 300 h, and a Na-Cr-O compound formed in the matrix of specimens. Gr.92 showed a higher corrosion rate than HT9. The corrosion rate of Ferritic/Martensitic Steels (FMS) in oxygen-saturated sodium was also modelled in this study. The empirical model was compared with the short-term experimental data. The results show that the empirical model had close value to the short-term experimental model.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.corsci.2016.09.001

Additional details

Identifiers

DOI
10.1016/j.corsci.2016.09.001;
PII
S0010-938X(16)30685-0;

Publishing Information

Journal Title
Corrosion Science
Journal Volume
112
Journal Page Range
p. 611-624
ISSN
0010-938X
CODEN
CRRSAA

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.