In the 1950s, the 9-12Cr steels with low Carbon (max 0.1%) have been developed for their high creep-rupture strength combined with good oxidation and corrosion resistance at elevated temperatures and were successfully used in several industries (e.g.: petroleum, aerospace, electrical power plants engineering,…). In the 1980s, ferritic-martensitic steels have been further developed and used for fast breeder reactor core components, because of their superior resistance to irradiation damage, appropriate strength properties and acceptable cost. In recent years, martensitic steels with 9 – 12 wt % Cr have been considered to be very promising candidates for internal structures of fusion reactors or high temperature reactors, because of their resistance to swelling and their good mechanical properties like impact, tensile and creep resistance. In the present work, radiation effects on the microstructure and mechanical properties of Fe and Fe-Cr single crystals and Fe-Cr model alloys, used as a model materials for ferritic-martensitic steels was studied. The objective was to define the microstructure and the mechanical properties of model alloys before and after neutron irradiation to different doses, in order to find out how they compare with steels, as real structural materials.
|Place of Publication||Gent, Belgium|
|State||Published - 16 Nov 2007|