The present status of the small specimen test technique (SSTT) and the engineering design of the post irradiation examination (PIE) facility in the International Fusion Materials Irradiation Facility (IFMIF) were evaluated and summarized as parts of the IFMIF/engineering validation and engineering design activity (EVEDA). SSTT is very important to obtain data mainly for the design of fusion demonstration (DEMO) reactors using the high flux test module (HFTM) of IFMIF. The analysis of brittle-ductile transition behaviors of reduced-activation ferritic/martensitic (RAFM) steels is very important for evaluating the structural integrity of RAFM steels used in the fusion DEMO reactors, and it is necessary to develop new analyses combined with random inhomogeneity analysis and the modified master curve method. Further developed analysis and test equipment developing for small specimen tests are necessary in the establishment of SSTT.
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