Review on chromium coated zirconium alloy accident tolerant fuel cladding

J Yang, M Steinbrück, C Tang, M Große, J Liu… - Journal of Alloys and …, 2022 - Elsevier
Abstract The Fukushima-Daiichi accident revealed that the zirconium fuel claddings have
the significant safety risk of hydrogen detonation due to the strong oxidation and hydrogen …

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

KA Terrani - Journal of Nuclear Materials, 2018 - Elsevier
The motivation for transitioning away from zirconium-based fuel cladding in light water
reactors to significantly more oxidation-resistant materials, thereby enhancing safety …

High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

JC Brachet, E Rouesne, J Ribis, T Guilbert, S Urvoy… - Corrosion …, 2020 - Elsevier
The oxidation of chromium-coated zirconium-based alloys is studied under steam at
temperatures ranging from 800° C up to 1500° C and for oxidation times ranging from a few …

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 …

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

C Tang, M Stueber, HJ Seifert, M Steinbrueck - Corrosion reviews, 2017 - degruyter.com
Chongchong Tang received his Master's degree in metallurgical engineering from the
Northeastern University, China, in 2014. He is currently a PhD student in the IAM-AWP of the …

Current status of materials development of nuclear fuel cladding tubes for light water reactors

Z Duan, H Yang, Y Satoh, K Murakami, S Kano… - … Engineering and Design, 2017 - Elsevier
Abstract Zirconium-based (Zr-based) alloys have been widely used as materials for the key
components in light water reactors (LWRs), such as fuel claddings which suffer from …

Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure

EB Kashkarov, DV Sidelev, MS Syrtanov, C Tang… - Corrosion …, 2020 - Elsevier
Cr coatings with the thickness of 4.5–9.0 μm and dense/columnar microstructure were
deposited onto Zr alloy by cooled or hot target magnetron sputtering. Steam oxidation tests …

Recent advances in protective coatings for accident tolerant Zr-based fuel claddings

E Kashkarov, B Afornu, D Sidelev, M Krinitcyn… - Coatings, 2021 - mdpi.com
Zirconium-based alloys have served the nuclear industry for several decades due to their
acceptable properties for nuclear cores of light water reactors (LWRs). However, severe …

AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding

J Bischoff, C Delafoy, C Vauglin, P Barberis… - Nuclear Engineering …, 2018 - Elsevier
Abstract AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced
accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated …

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 …