| Abstract Scope |
Oxide dispersion strengthened (ODS) ferritic steels show promising high temperature strength, creep resistance, and radiation tolerance, but the effects of irradiation on dispersoid stability are not fully understood. This uncertainty is compounded by the effects of joining techniques (e.g., fusion welding) that may alter, agglomerate, or redistribute nanoscale oxide particles. To minimize these effects, a solid state capacitive discharge resistance welding technique was used to seal small diameter, thin walled cladding tubes of ODS alloy 14YWT to like caps. Material from the resulting joints was irradiated with 1 MeV H<sup>+</sup> and 4 MeV Fe<sup>2+</sup> at various dose-temperature conditions (1-50 dpa, 350-450 ºC). Microstructural and chemical evolution (e.g., oxide particle stability, radiation-induced segregation) were characterized using electron microscopy (S/TEM, EDS, EELS), while the sensitivity of these effects to the welding parameters was considered. |