Abstract
This work focuses on irradiation behaviors of a novel silicon carbide and carbon coated nanostructured ferritic alloy (SiC-C@NFA) composite for potential applications as a cladding and structural material for next generation nuclear reactors.The SiC-C@NFA samples were irradiated with 1 MeV Kr ions up to 10 dpa at 300 and 450 ℃.Microstructures and defect evolution were studied in-situ at the IVEM-Tandem facility at Argonne National Laboratory.The effects of ion irradiation on various phases such as α-ferrite matrix,(Fe,Cr)7C3,and (Ti,W)C precipitates were evaluated.The α-ferrite matrix showed a continuous increase in dislocation density along with spatial ordering of dislocation loops (or loop strings) at ＞5 dpa.The size of the dislocation loops at 450 ℃ was larger than that at 300 ℃.The nucleation and growth of new (Ti,W)C precipitates in α-ferrite grains were enhanced with the ion dose at 450 ℃.This study provides new insight into the irradiation resistance of the SiC-C@NFA system.
基金项目
Office of Nuclear Energy of Department of Energy(DE-NE0008264)
in-situ ion irradiation experiments at Argonne National Laboratory were supported by DOE as a part of Rapid Turnaround Exper()
NETL
NSTL
维普
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