articleTop 10% cited
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating
Journal of Nuclear Materials · 2015 · Vol. 465 · pp. 531–539
Hyung‐Il Kim✉(Korea Atomic Energy Research Institute)Il-Hyun Kim(Korea Atomic Energy Research Institute)Yang‐Il Jung(Korea Atomic Energy Research Institute)Dong-Jun Park(Korea Atomic Energy Research Institute)Jeong-Yong Park(Korea Atomic Energy Research Institute)Yang-Hyun Koo(Korea Atomic Energy Research Institute)
Nuclear Materials and PropertiesNuclear reactor physics and engineeringFusion materials and technologiesMaterials scienceCoatingCladding (metalworking)Layer (electronics)Composite materialZirconium alloyAdhesionInert gasOxideInert
Funding
- National Research Foundation of Korea
Citations
339
FWCI
5.74
field-weighted impact
References
8
Percentile
97%
vs. same field & year
Citations per year
Cited by
Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
Journal of Nuclear Materials · 2019 · 371 citations
Accident tolerant fuel cladding development: Promise, status, and challenges
Journal of Nuclear Materials · 2018 · 899 citations
References
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
Journal of Nuclear Materials · 2013 · 482 citations
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