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Evaluation of corrosion and oxidation behaviors of TiAlCrN coatings for nuclear fuel cladding

https://doi.org/10.1016/j.surfcoat.2018.11.083
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38/38 checkable references clean · checked 2026-07-23

Every reference with a DOI in the deposited reference list resolved to a known work in Crossref or DataCite at the dated check, and none carried a retraction, withdrawal, or removal notice.

2 without a DOI — not checked. A reference deposited without a DOI is never matched by title or guessed at; it stays outside the checked set, and this line discloses that.

The 38 checked references that resolve
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Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction
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Phenomenology of BWR fuel assembly degradation
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Zircaloy-4 and M5® high temperature oxidation and nitriding in air
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Reaction in air and in nitrogen of pre-oxidised Zircaloy-4 and M5™ claddings
resolves10.1016/j.surfcoat.2018.04.037
Preparation, structure, and properties of an AlCrMoNbZr high-entropy alloy coating for accident-tolerant fuel cladding
resolves10.1016/j.surfcoat.2018.04.029
Improved oxidation resistance of zirconium at high-temperature steam by magnetron sputtered Cr-Al-Si ternary coatings
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Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis
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Influence of chemical composition of zirconium alloy E110 on embrittlement under LOCA conditions – Part 1: Oxidation kinetics and macrocharacteristics of structure and fracture
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A study of the breakaway oxidation behavior of zirconium cladding materials
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The air oxidation of yttrium ion implanted zircaloy-4 at 500°C
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Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure
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High temperature steam oxidation of Al3Ti-based alloys for the oxidation-resistant surface layer on Zr fuel claddings
resolves10.1016/j.surfcoat.2010.12.017
Deposition, characterization and performance evaluation of ceramic coatings on metallic substrates for supercritical water-cooled reactors
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Influence of Cr addition on microstructure and mechanical properties of Zr-based alloys corresponding to Zr–C–Cr system
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Atomic-scale interface structure of a Cr-coated Zircaloy-4 material
resolves10.1016/j.surfcoat.2015.09.022
High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings
resolves10.1016/j.jnucmat.2015.06.030
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating
resolves10.1016/j.net.2017.12.004
AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding
resolves10.1016/j.surfcoat.2013.08.010
Effect of CrN addition on the structure, mechanical and thermal properties of Ti-Al-N coating
resolves10.1016/j.surfcoat.2017.01.053
Influence of Cr additions on the structure and oxidation resistance of multilayered TiAlCrN films
resolves10.1016/S0257-8972(05)80016-7
Microstructural investigation of droplets in arc-evaporated TiN films
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Oxidation kinetics of sputtered Cr–N hard coatings
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Annealing induced oxidation and transformation of Zr thin film prepared by ion beam sputtering deposition
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The microstructure and microtexture of zirconium oxide films studied by transmission electron backscatter diffraction and automated crystal orientation mapping with transmission electron microscopy
resolves10.1016/j.jnucmat.2017.03.010
Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding
resolves10.1016/j.jnucmat.2018.03.037
Phase stability of zirconium oxide films during focused ion beam milling
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Effects of Ti alloying of AlCrN coatings on thermal stability and oxidation resistance
resolves10.1016/j.surfcoat.2017.05.053
Thermal stability and oxidation resistance of sputtered Ti Al Cr N hard coatings
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Deformation of zircaloy-4 cladding during a LOCA transient up to 1200 C
resolves10.1016/j.surfcoat.2007.11.037
A study of the oxidation behavior of CrN and CrAlN thin films in air using DSC and TGA analyses
The 2 references without a DOI — listed, not checked
no DOI — not checkedOn-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRS fuel
no DOI — not checkedAssessment at CEA of coated nuclear fuel cladding for LWRs with increasing margins in LOCA and beyond LOCA conditions
What this badge says. CiteStamped means the CHECKABLE references of this work were clean at the dated check: each resolved to a known work in a public registry, and none carried a retraction notice at that time. It says nothing about the quality, findings, or importance of the work itself, and nothing about references deposited without a DOI.

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