MECHANICAL PROPERTIES OF NEUTRON-IRRADIATED LOWER ACTIVATED Fe-Cr-Mn ALLOYS

概要

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Fe-Cr-Mn steels have been proposed as materials for structural components of the fusion reactor because of their lower radio-activity in comparison with SUS 316 austenitic stainless steels. Therefore, it is required to characterize the material with respect to its mechanical properties and microstructural changes during neutron irradiation for the doses and temperatures relevant for first wall condition. For these objectives, a series of Fe-Cr-Mn-(Al) steels with different compositions have been examined in tensile tests and by electron microscopy after neutron irradiation up to 8 x 10^<23> n/m^2 at 473 K. The 0.2% proof stress, ultimate tensile stress and total elongation were compared before and after irradiation. The results indicate that both Fe-10%Cr-(20-25)%Mn-3%Al and Fe-10%Cr-30%Mn steels show most radiation-resistant.low activationradiation hardeningdefect clusteralloying elementfusion reactor
東北大学の論文
1994-09-16