The objective of the GETMAT project was the investigation, both in the theoretical and experimental domains, of selected material properties that are cross-cutting among the various Generation IV and Transmutation reactor designs. Since the design requirements of the innovative reactors are beyond those for the LWR currently in operation, the selection of the properties to be investigated has been performed by identifying relevant conditions of key components as cores and primary systems. In fact, high temperature, high irradiation doses, corrosive environments as well as high thermal and mechanical loads are features that pose challenges on all materials foreseen for these components.

Taking into account this framework and the goals defined by the Generation IV and the waste transmutation approaches as e.g. sustainability in terms of optimisation of use of resources and waste minimisation, high safety standards, economic viability and efficiency, it turned out that innovative materials might be a better choice with respect to conventional nuclear grade steels for the design of the core components and the primary system.

Therefore, ODS alloys and 9-12 Cr Ferritic/Martensitic (F/M) steels have been selected as reference for the GETMAT project. In particular, even if ODS alloys are known since several decades, data for nuclear applications are quite scarce. The scientific results produced within the GETMAT project on 9Cr, 12Cr and 14Cr ODS alloys fabricated via the powder metallurgy route as well as the results obtained on the 9-12Cr F/M steels through an important PIE program, contribute considerably to a better understanding of the behaviour of these classes of materials for nuclear application.

Moreover, the results have been found to be highly relevant for the identification of further R&D activities defined within the EERA Joint Program for Nuclear Materials (JPNM) and the related projects MATTER and MatISSE supported by the EURATOM FP7. In concordance with the experimental investigation on F/M steels and Ferritic / F/M ODS alloys the theoretical program was devoted to the study of Fe and Fe-Cr alloys. Emphasis has been put on first principle modelling studies and experiments to identify and validate physical models and mechanisms that explain irradiation hardening and embrittlement of these alloys.