材料科学
包层(金属加工)
辐照
原子探针
降水
合金
冶金
小角中子散射
相(物质)
中子
成核
微观结构
中子散射
核物理学
化学
物理
气象学
有机化学
作者
Samuel A. Briggs,Philip D. Edmondson,Kenneth C. Littrell,Yukinori Yamamoto,Richard J. Howard,Charles R. Daily,Kurt A. Terrani,Kumar Sridharan,Kevin G. Field
标识
DOI:10.1016/j.actamat.2017.02.077
摘要
FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding applications in light water reactors owing to their superior high-temperature oxidation and corrosion resistance compared to the Zr-based alloys currently employed. However, their performance could be limited by precipitation of a Cr-rich α ′ phase that tends to embrittle high-Cr ferritic Fe-based alloys. In this study, four FeCrAl model alloys with 10–18 at.% Cr and 5.8–9.3 at.% Al were neutron-irradiated to nominal damage doses up to 7.0 displacements per atom at a target temperature of 320 °C. Small angle neutron scattering techniques were coupled with atom probe tomography to assess the composition and morphology of the resulting α ′ precipitates. It was demonstrated that Al additions partially destabilize the α ′ phase, generally resulting in precipitates with lower Cr contents when compared with binary Fe-Cr systems. The precipitate morphology evolution with dose exhibited a transient coarsening regime akin to previously observed behavior in aged Fe-Cr alloys. Similar behavior to predictions of the LSW/UOKV models suggests that α ′ precipitation in irradiated FeCrAl is a diffusion-limited process with coarsening mechanisms similar to those in thermally aged high-Cr ferritic alloys.
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