http://www.youngbrigades.com/phd-schola ... ience.htmlReduced-activation ferritic-martensitic (RAFM) material is currently considered as one of the candidates for the structural components of the future fusion reactors. Ferritic martensitic steels show limited swelling and susceptibility to helium effects, attractive mechanical properties and can be made with low-activation chemical compositions, which allow recycling of the waste from fusion power plants in 100 years time. The main unresolved issues for RAFM steels are incomplete understanding of the effect of irradiation and irradiation temperature on defect structures and the consequent changes in mechanical properties. In the present project, two variants of the most promising RAFM-material will be thoroughly studied on their defect structure and its thermal stability, Two sets of experiments will be performed: one on samples that have been irradiation in the nuclear reactor in Petten, and one set of laboratory-irradiated samples.
The main aim of the project is to establish a relationship between the observed changes in the mechanical properties and the irradiation-induced defect structures. The irradiation-induced defects have been introduced in the material by neutrons, with involvement of (n,?)-reactions, and by ion implantation. The project will be focusing on the characterization of the defect structures which are formed as result of clustering and coalescence of the primary point defects: helium-vacancy clusters, helium-filled bubbles, interstitial loops, etc. Such defects, ranging from point defects to a few nanometres in size, can serve as pinning centres for dislocations, segregate at grain boundaries, leading to radiation embrittlement, swelling and other changes in material properties.
Steel For Fusion
Steel For Fusion
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