articleTop 10% cited
Ferritic/martensitic steels for next-generation reactors
Journal of Nuclear Materials · 2007 · Vol. 371(1-3) · pp. 37–52
R.L. Klueh✉(Oak Ridge National Laboratory)Andrew Nelson(Oak Ridge National Laboratory)
Fusion materials and technologiesNuclear Materials and PropertiesNuclear reactor physics and engineeringNuclear engineeringCladding (metalworking)Fusion powerMaterials scienceWork (physics)MetallurgyMechanical engineeringEngineeringNuclear physicsPlasma
Funding
- U.S. Department of Energy
Citations
864
FWCI
8.51
field-weighted impact
References
50
Percentile
99%
vs. same field & year
Citations per year
Cited by
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
Journal of Nuclear Materials · 2015 · 497 citations
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
Journal of Nuclear Materials · 2013 · 561 citations
References
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
Journal of Nuclear Materials · 2000 · 553 citations
Citation Network
How this paper connects to the literature. Drag to explore, click any node to open that paper.