article Open AccessTop 1% cited
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
Journal of Nuclear Materials · 2015 · Vol. 465 · pp. 746–755
Kevin G. Field✉(Oak Ridge National Laboratory)Xunxiang Hu(Oak Ridge National Laboratory)Kenneth C. Littrell(Oak Ridge National Laboratory)Yukinori Yamamoto(Oak Ridge National Laboratory)L.L. Snead(Oak Ridge National Laboratory)
Nuclear Materials and PropertiesFusion materials and technologiesNuclear reactor physics and engineeringIrradiationMaterials scienceAlloyChromiumHardening (computing)NeutronZirconium alloyUltimate tensile strengthPrecipitationMetallurgy
Funding
- Office of Nuclear Energy
- Basic Energy Sciences
- Oak Ridge National Laboratory
Citations
314
FWCI
13.15
field-weighted impact
References
75
Percentile
99%
vs. same field & year
Citations per year
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References
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Journal of Nuclear Materials · 2015 · 497 citations
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