Corrosion behaviour of 12Cr-ODS steel in molten lead

•The corrosion of 12Cr-ODS steel was tested in static and flowing liquid lead.•The formation of external oxides and inner diffusion were observed.•In flowing Pb there was removal of the surface oxides and damage.•Oxide scale constitution depending on oxygen concentration.•The morphology of oxides wa...

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Bibliographic Details
Published in:	Nuclear engineering and design Vol. 280; pp. 69 - 75
Main Authors:	Di Gabriele, Fosca, Amore, Stefano, Scaiola, Celeste, Arato, Elisabetta, Giuranno, Donatella, Novakovic, Rada, Ricci, Enrica
Format:	Journal Article
Language:	English
Published:	Elsevier B.V 01-12-2014
Subjects:	Austenitic stainless steels Contact Corrosion tests Dispersion hardening alloys Ferritic stainless steels Heat resistant steels Lead (metal) Martensitic stainless steels Nuclear reactor components Structural materials Structural steels
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Summary:	•The corrosion of 12Cr-ODS steel was tested in static and flowing liquid lead.•The formation of external oxides and inner diffusion were observed.•In flowing Pb there was removal of the surface oxides and damage.•Oxide scale constitution depending on oxygen concentration.•The morphology of oxides was strongly dependent on the extrusion direction. Oxide dispersion-strengthened (ODS) steels are being studied as potential materials for future Generation IV concepts of Nuclear Fast Reactors. In particular, the use of heavy liquid metals (HLM), lead and lead bismuth eutectic alloy, is foreseen as coolant and target. However, most of the structural materials used traditionally, suffer severe damage when in contact with HLMs. Structural materials such as the austenitic 316L and the ferritic–martensitic T91 steels have been considered for operation at temperature lower than 823K. On the other hand, for operations at elevated temperature and under severe neutron exposure environment, the ODS steels are taken into account and currently studied. In the frame of the FP7-GETMAT (Generation IV and Transmutation Materials) project, ODS steels containing 12wt% Cr were tested in different conditions and environments, comparing experimental techniques and results. This paper reports the results of the study on the behaviour of the 12Cr-ODS steel in contact with molten lead at the temperature of 923K. The corrosion tests were performed both in a static cell (CorAL) and in flowing conditions, in a natural convection loop (COLONRI II), in Pb, for an exposure time up to 2000h. The microstructure analysis of the specimens was done before and after the corrosion tests. The results of the corrosion experiments in both experimental facilities are described and the characteristics of the oxides developed on the 12Cr-ODS steel are discussed.
Bibliography:	ObjectType-Article-1 SourceType-Scholarly Journals-1 ObjectType-Feature-2 content type line 23
ISSN:	0029-5493 1872-759X
DOI:	10.1016/j.nucengdes.2014.09.030