articleTop 1% cited
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
Journal of Nuclear Materials · 2013 · Vol. 448(1-3) · pp. 420–435
Kurt A. Terrani✉(Oak Ridge National Laboratory)S.J. Zinkle(Oak Ridge National Laboratory)Lance L. Snead(Oak Ridge National Laboratory)
Nuclear Materials and PropertiesFusion materials and technologiesNuclear reactor physics and engineeringCladding (metalworking)Materials scienceAlloyZirconium alloyZirconiumAusteniteNuclear fuelMetallurgyLight-water reactorNuclear engineering
Citations
561
FWCI
13.94
field-weighted impact
References
112
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99%
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Citations per year
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References
Ferritic/martensitic steels for next-generation reactors
Journal of Nuclear Materials · 2007 · 864 citations
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
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The evolution of mechanical property change in irradiated austenitic stainless steels
Journal of Nuclear Materials · 1993 · 453 citations
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel
Journal of Nuclear Materials · 1993 · 380 citations
Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals
Journal of Nuclear Materials · 1999 · 375 citations
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