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Published in 2019 at "Materials Chemistry and Physics"
DOI: 10.1016/j.matchemphys.2018.10.029
Abstract: Abstract 304 stainless steel (SS) was exposed to 325 °C water condition to simulate the operation condition of nuclear power reactor. The microstructural characteristics and corrosion behaviors of exposed 304 SS was investigated. Result shows that…
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Keywords:
oxide film;
stainless steel;
304 stainless;
mechanism oxide ... See more keywords