The microstructure of(CrFe)_7C_3 has been studied with scanning tunneling microscopy.It shows that a carbide consists of colonies which are full of stacking faults. The stacking faults in one colony are parallel while...The microstructure of(CrFe)_7C_3 has been studied with scanning tunneling microscopy.It shows that a carbide consists of colonies which are full of stacking faults. The stacking faults in one colony are parallel while those in different colonies lie at angle with each other.展开更多
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 gener...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 4500 C.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 asα-ferrite matrix,(Fe,Cr)_(7)C_(3),and(Ti,W)C precipitates were evaluated.Theα-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 inα-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.展开更多
文摘The microstructure of(CrFe)_7C_3 has been studied with scanning tunneling microscopy.It shows that a carbide consists of colonies which are full of stacking faults. The stacking faults in one colony are parallel while those in different colonies lie at angle with each other.
基金supported financially by the Office of Nuclear Energy of Department of Energy(No.#DE-NE0008264)supported by DOE as a part of Rapid Turnaround Experiments(RTE)award of Nuclear Science User Facilities(NSUF)。
文摘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 4500 C.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 asα-ferrite matrix,(Fe,Cr)_(7)C_(3),and(Ti,W)C precipitates were evaluated.Theα-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 inα-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.
