articleTop 1% cited
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
Journal of Nuclear Materials · 2013 · Vol. 440(1-3) · pp. 420–427
Bruce A. Pint✉(Oak Ridge National Laboratory)Kurt A. Terrani(Oak Ridge National Laboratory)Michael P. Brady(Oak Ridge National Laboratory)Ting Cheng(Oak Ridge National Laboratory)James R. Keiser(Oak Ridge National Laboratory)
Nuclear Materials and PropertiesHigh-Temperature Coating BehaviorsFusion materials and technologiesMaterials scienceCladding (metalworking)MetallurgyAlloyHydrogenMetalAusteniteBar (unit)Atmospheric temperature rangeMicrostructure
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482
FWCI
12.41
field-weighted impact
References
33
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References
Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials
Journal of Nuclear Materials · 1993 · 326 citations
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
Journal of Nuclear Materials · 2005 · 552 citations
Structural materials challenges for advanced reactor systems
Journal of Nuclear Materials · 2008 · 676 citations
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