journal article·2014-05

Corrosion behavior of austenitic steels in liquid lead bismuth containing 10−6wt% and 10−8wt% oxygen at 400–500°C

A. Heinzel, A. Weisenburger, G. Müller

Journal of Nuclear Materials· Volume 448· Issue 1-3
Publisher page

Abstract

Abstract Three austenitic steels (316L, DIN 1.4970 tube and rod material) were tested up to 5000 h at temperatures between 400 and 500 °C in PbBi containing 10 −8 wt% oxygen and at 450 °C and 500 °C in PbBi with 10 −6 wt% oxygen. Protective scales grown on the surface up to 450 °C consist mainly of Cr rich oxides. However, after 5000 h at 500 °C dissolution attack occurred. At 10 −6 wt% and 450 °C the thin Cr rich oxide scale is interrupted by areas with a thicker duplex-layered oxide of magnetite and spinel. At the higher temperature of 500 °C the whole surface is covered by the duplex-layered oxide scale.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear materials and radiation effects · Fusion materials and technologies

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