Authors & Affiliations

Weisenburger A., Müller G., DelGiacco M., Fetzer R., Heinzel A., Jianu A.
Karlsruhe Institute of Technology, Institute for Pulsed power and Microwave Technology Karlsruhe, Germany

Abstract

Studies were carried out on corrosion behavior of Fe-Cr-Al-base model alloys during their exposure to oxygen-containing lead in the temperature range 400-600°C. A map of the alumina stability domain for this temperature range was drawn in Fe-Cr-Al ternary diagrams and the type of alumina polymorph, formed at different temperatures, was determined. Fretting enhanced corrosion of selected fuel clad materials like 15-15Ti, T91 and aluminum surface alloyed steel is discussed and fretting rates of materials in liquid lead as function of temperature, load and amplitude are given.

Keywords
innovative nuclear reactors, structural materials, lead coolant, corrosion, surface aluminizing, fretting

Article Text (PDF)

References

UDC 621.039.53

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 1, 1:3