TENSILE PROPERTIES AND STRUCTURAL ANALYSIS OF MARTENSITIC LOW-ACTIVATION ALLOYS AFTER NEUTRON IRRADIATION

摘要

Within the framework of the European Fusion Technology Program, a series of ferritic/rnmartensitic developmental alloys have been investigated after irradiation in thernHFR (Petten, Netherlands) up to an accumulated dose of 2.4 dpa. Six alloys fromrnForschungszentrum Karlsruhe (OPTIFER-Type) were compared with the internationallyrninvestigated IEA alloy F82H mod. a 8%Cr2WVTa material. These new 8-rn10%CrWVTa alloys are optimized towards long-term activation. Tensile propertiesrnwere determined. The highest strength was observed in the range of 250 and 350 ℃rnas radiation hardening. Neutron irradiation induced precipitates, dislocation loops andrnHe bubbles or small voids have been revealed by transmission electron microscopicsrnanalysis.