Scinovex
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. GarnerM.B. ToloczkoBulent H. Sencer
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.