Review of manufacturing technologies for coated accident tolerant fuel cladding

J Ko, JW Kim, HW Min, Y Kim, YS Yoon - Journal of Nuclear Materials, 2022 - Elsevier
This article reviewed the near-term development status of accident tolerant fuel (ATF)
cladding to increase the safety of nuclear power generation. The key to near-term …

Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

G Jiang, D Xu, P Feng, S Guo, J Yang, Y Li - Journal of Alloys and …, 2021 - Elsevier
The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …

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 …

High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments

H Yeom, B Maier, G Johnson, T Dabney… - Journal of Nuclear …, 2019 - Elsevier
Oxidation kinetics and microstructural evolution of cold sprayed Cr coatings on Zircaloy-4 at
1130–1310° C in flowing steam at atmospheric pressure have been studied. The study is …

High-temperature oxidation of Zr1Nb zirconium alloy with protective Cr/Mo coating

MS Syrtanov, EB Kashkarov, AV Abdulmenova… - Surface and Coatings …, 2022 - Elsevier
The oxidation and interdiffusion behavior of Cr-and Cr/Mo-coated Zr single bond 1Nb
zirconium alloy were investigated. A single-layer Cr (8 um) and multilayer Cr (8 μm)/Mo (3 …

Investigations of oxidation behavior and establishment of life-cycle model during the steam oxidation of Cr-coated Zry-4 at 1200° C

Y Meng, C Chen, S Zeng, C Zhu, X Zhou, X Han - Corrosion Science, 2024 - Elsevier
The isothermal steam oxidation behaviors of Cr-coated and non-coated Zry-4 cladding at
1200° C have been investigated systematically. The oxidation of Cr coating is divided into …

Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding

B Maier, H Yeom, G Johnson, T Dabney… - Journal of Nuclear …, 2019 - Elsevier
The development of a cold spray process for the deposition of chromium (Cr) coatings on
zirconium-alloys is presented with the goal of improving the accident tolerance of light water …

Cr-coated Zr-4 alloy prepared by electroplating and its in situ He+ irradiation behavior

M Huang, Y Li, G Ran, Z Yang, P Wang - Journal of Nuclear Materials, 2020 - Elsevier
With the aim of improving the oxidation resistance of zirconium alloy claddings in light water
reactors and enhancing the deposition efficiency and economics of surface coating …

Investigation of oxidation behaviors of coated Zircaloy as accident-tolerant fuel with CrAlN and CrAlSiN coatings in high-temperature steam

J Liu, Z Cui, D Ma, J Lu, Y Cui, C Li, W Liu, Z Hao… - Corrosion …, 2020 - Elsevier
CrAlN and CrAlSiN coatings were deposited on Zircaloy samples by multi-arc ion plating
(MAIP) and the microstructure, hardness, and oxidation resistance of the two types of …

Recent advances and prospects in design of hydrogen permeation barrier materials for energy applications—a review

ECE Rönnebro, RL Oelrich, RO Gates - Molecules, 2022 - mdpi.com
The hydrogen infrastructure involves hydrogen production, storage and delivery for
utilization with clean energy applications. Hydrogen ingress into structural materials can be …