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

JC Brachet, I Idarraga-Trujillo, M Le Flem… - Journal of Nuclear …, 2019 - Elsevier
Coatings with thicknesses between a few microns and∼ 10 μm deposited on a Zircaloy-4
substrate have been studied with the objective to provide a significant reduction in the …

Mechanical and high-temperature corrosion properties of AlTiCrNiTa high entropy alloy coating prepared by magnetron sputtering for accident-tolerant fuel cladding

S Zhao, C Liu, J Yang, W Zhang, L He, R Zhang… - Surface and Coatings …, 2021 - Elsevier
A high-entropy alloy (HEA) AlTiCrNiTa coating with near-equal molar ratio was prepared on
the base of zircaloy-4 substrates using radio frequency (RF) magnetron sputtering (MS) …

Oxidation behavior of FeCrAl coated Zry-4 under high temperature steam environment

X Han, Y Wang, S Peng, H Zhang - Corrosion Science, 2019 - Elsevier
FeCrAl alloys have exhibited excellent oxidation resistance in high temperature steam
environment. However, over the past few years, thin film FeCrAl on zircaloy substrate can …

Improved oxidation resistance of Cr/FeCrAl coating on Zr alloy in high-temperature steam environment

X Yang, B Luan, L Chen, J Wu, P Zhu, H Zhou… - Surface and Coatings …, 2023 - Elsevier
A new bi-layer Cr/FeCrAl coating was successfully fabricated on the Zr-4 plates through
multi-arc ion plating in order to take advantage of the two materials of FeCrAl and Cr. The …

Under-deposit corrosion of Ni-based alloy 825 and Fe-Ni based alloy 800 in supercritical water oxidation environment

J Yang, S Wang, Y Li, D Xu - Corrosion Science, 2020 - Elsevier
The under-deposit corrosion behavior of Alloy 800 and Alloy 825 in oxidizing supercritical
water (SCW) containing KCl or NaCl were investigated. A novel-designed reactor was used …

Corrosion of the bonding at FeCrAl/Zr alloy interfaces in steam

D Jin, N Ni, Y Guo, Z Zou, X Wang, F Guo… - Journal of Nuclear …, 2018 - Elsevier
The interfacial bonding at protective coatings and Zr alloy substrates could have a significant
effect on the corrosion behaviors of the coatings. In this work, FeCrAl-Zr couples were …

Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment

R Schoell, J Kabel, S Lam, A Sharma, J Michler… - Journal of Nuclear …, 2022 - Elsevier
The simulated boiling water condition corrosion properties of multilayer and combinatorial
physical vapor deposition metal coatings (Zr, Cr, and/or Ti) deposited on a SiC f-SiC …

Effect of interface undulation on the high temperature oxidation behaviors of grit-blasted and coated zircaloy in pressurized water

D Jin, J Jiang, Z Di, C Zhang, M Xiong, F Yang, S Wei - Corrosion Science, 2021 - Elsevier
Abstract Effect of interface undulation on the high-temperature oxidation behaviors of grit-
blasted and coated zircaloys in pressurized water was investigated. The grit-blasted and the …

[PDF][PDF] Metallic and ceramic coatings for enhanced accident tolerant fuel cladding

C Tang, M Stüber, HJ Seifert… - Comprehensive Nuclear …, 2020 - scholar.archive.org
Zirconium-based alloy fuel claddings applied in current water-cooled nuclear reactors
possess multiple desirable attributes during steady-state normal operation. However, the …

Effects of the Laser Micromelting Process Parameters on the Preparation of Micron-Sized FeCrAl Coatings on Zr Alloy Surfaces

G Song, W Wei, B Liu, B Shuai, G Liu, K Xue, Y Chen - Materials, 2023 - mdpi.com
Laser micromelting (LMM) technology allows for the remelting of pre-positioned coatings on
the surface of a specimen to form a metallurgical bond with the substrate material …