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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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Mechanism of corrosion of 9Cr and 12Cr ferritic/martensitic steels under oxygen-saturated sodium

Author(s)
Shin, Sang HunLee, JeonghyeonKim, Jun HwanKim, Ji Hyun
Issued Date
2016-11
DOI
10.1016/j.corsci.2016.09.001
URI
https://scholarworks.unist.ac.kr/handle/201301/20584
Fulltext
http://www.sciencedirect.com/science/article/pii/S0010938X16306850
Citation
CORROSION SCIENCE, v.112, pp.611 - 624
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.
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
ISSN
0010-938X
Keyword (Author)
SteelAlloySEMWeight lossHigh temperature corrosion
Keyword
AUSTENITIC STAINLESS-STEELBI EUTECTIC ALLOY650 DEGREES-CLIQUID-SODIUMSUPERCRITICAL WATEROXIDATION MECHANISMFE-9CR-1MO STEELFERRITIC STEELSHIGH-TEMPERATUREFAST-REACTORS

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