article Open AccessTop 1% cited
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
Journal of Nuclear Materials · 2015 · Vol. 467 · pp. 703–716
Yukinori Yamamoto✉(Oak Ridge National Laboratory)Bruce A. Pint(Oak Ridge National Laboratory)Kurt A. Terrani(Oak Ridge National Laboratory)Kevin G. Field(Oak Ridge National Laboratory)Ying Yang(Oak Ridge National Laboratory)L.L. Snead(Oak Ridge National Laboratory)
Nuclear Materials and PropertiesFusion materials and technologiesNuclear reactor physics and engineeringMaterials scienceCladding (metalworking)MetallurgyAlloyZirconiumLight-water reactorMicrostructureMolybdenumZirconium alloyAluminium
Funding
- U.S. Department of Energy
- Battelle
- UT-Battelle
- Office of Nuclear Energy
- Nuclear Fuel Cycle and Supply Chain
- Basic Energy Sciences
- Oak Ridge National Laboratory
Citations
497
FWCI
15.67
field-weighted impact
References
41
Percentile
100%
vs. same field & year
Citations per year
Cited by
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References
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
Journal of Nuclear Materials · 2015 · 314 citations
Ferritic/martensitic steels for next-generation reactors
Journal of Nuclear Materials · 2007 · 864 citations
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
Journal of Nuclear Materials · 2013 · 561 citations
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
Journal of Nuclear Materials · 2013 · 482 citations
Accident tolerant fuels for LWRs: A perspective
Journal of Nuclear Materials · 2013 · 1,030 citations
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