Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding

Accident tolerant fuels for LWRs: A perspective

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Accident tolerant fuel cladding development: Promise, status, and challenges

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Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings

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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

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Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating

Hyung‐Il Kim, Il-Hyun Kim, Yang‐Il Jung et al. · Journal of Nuclear Materials · 2015 · 340 citations

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