A key problem in development of heavy liquid metal cooled nuclear energy and transmutation reactors is the corrosion of structural and fuel cladding materials in contact with the liquid metal. Lead and lead bismuth attack unprotected steel surfaces by dissolution of the metallic components into the liquid metal. It is common understanding that oxide scales on the surface provide the best protection against dissolution attack. However, at temperatures above 500°C austenitic steels suffer from severe dissolution attack, while martensitic steels form thick oxide scales, which hinder heat transfer from the fuel pins and which may break off and eventually lead to a blocking of the coolant channel. Above 500°C steels have to be protected by stable, thin oxide scales. A well understood measure is alloying of stable oxide formers into the surface. Al has shown its ability to form such oxide scales. In the range of 4–10 wt% Al on the surface a stable thin alumina scale is formed by Al diffusion to the surface and selective oxidation. The alumina scale grows only very slowly and prevents migration of oxygen into the steel as well as migration of steel components onto the surface. A number of corrosion experiments showed the good protective behaviour of Al scales in LBE with 10−6 wt% oxygen up to 650°C and for exposure times up to 10000 h. Alloying Al into the surface was done by diffusion processes and also by pulsed electron beam (GESA) melting of a thin surface layer on which Al or an Al containing alloy was precipitated before. This presentation gives an overview on investigations of the steel behaviour in HLM environment carried out to explore their suitability for systems with Pb/LBE coolants. Results of experiments with static and flowing LBE are discussed. The behaviour of steels examined and their respective application ranges are described. Part of the presentation deals with protective barrier development on the steel surface by alloying of Al and its effect on the corrosion resistance. Furthermore the influence of parameters like stresses in the cladding wall, creep behaviour, different flow velocities of the LBE and changing temperatures and oxygen concentrations in LBE is discussed.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Corrosion, Corrosion Barrier Development and Mechanical Properties of Steels Foreseen as Structural Materials in Liquid Lead Alloy Cooled Nuclear Systems Available to Purchase
Alfons Weisenburger,
Alfons Weisenburger
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Georg Mu¨ller,
Georg Mu¨ller
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Annette Heinzel,
Annette Heinzel
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Adrian Jianu,
Adrian Jianu
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Heinrich Muscher,
Heinrich Muscher
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Martin Kieser
Martin Kieser
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
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Alfons Weisenburger
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Georg Mu¨ller
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Annette Heinzel
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Adrian Jianu
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Heinrich Muscher
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Martin Kieser
Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen, Germany
Paper No:
ICONE17-75773, pp. 681-686; 6 pages
Published Online:
February 25, 2010
Citation
Weisenburger, A, Mu¨ller, G, Heinzel, A, Jianu, A, Muscher, H, & Kieser, M. "Corrosion, Corrosion Barrier Development and Mechanical Properties of Steels Foreseen as Structural Materials in Liquid Lead Alloy Cooled Nuclear Systems." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 681-686. ASME. https://doi.org/10.1115/ICONE17-75773
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