articleTop 10% cited
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
Journal of Nuclear Materials · 2000 · Vol. 276(1-3) · pp. 123–142
F.А. Garner✉(Pacific Northwest National Laboratory)M.B. Toloczko(Washington State University)Bulent H. Sencer(New Mexico Institute of Mining and Technology)
Fusion materials and technologiesNuclear Materials and PropertiesHigh Temperature Alloys and CreepSwellingCreepMaterials scienceAusteniteVoid (composites)MartensiteMetallurgyComposite materialMicrostructure
Citations
553
FWCI
3.99
field-weighted impact
References
54
Percentile
94%
vs. same field & year
Citations per year
Cited by
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
Journal of Nuclear Materials · 2013 · 561 citations
Ferritic/martensitic steels for next-generation reactors
Journal of Nuclear Materials · 2007 · 864 citations
Materials challenges in nuclear energy
Acta Materialia · 2013 · 2,477 citations
Citation Network
How this paper connects to the literature. Drag to explore, click any node to open that paper.
