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 …

Additive manufacturing of ceramic materials for energy applications: Road map and opportunities

CL Cramer, E Ionescu, M Graczyk-Zajac… - Journal of the European …, 2022 - Elsevier
Among engineering materials, ceramics are indispensable in energy applications such as
batteries, capacitors, solar cells, smart glass, fuel cells and electrolyzers, nuclear power …

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 …

[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 …

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 …

Materials for future nuclear energy systems

GS Was, D Petti, S Ukai, S Zinkle - Journal of Nuclear Materials, 2019 - Elsevier
Materials for future nuclear energy systems must operate under more extreme conditions
than those in current Gen II or Gen III systems. These conditions include higher temperature …

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

Y Yamamoto, BA Pint, KA Terrani, KG Field… - Journal of Nuclear …, 2015 - Elsevier
Abstract Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated
for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys …

Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200° C

J Liu, M Steinbrück, M Große, U Stegmaier, C Tang… - Corrosion …, 2022 - Elsevier
The isothermal oxidation behavior of the Cr-coated Zircaloy-4 at 1200° C in steam is
comprehensively investigated. Oxidation kinetics transition is observed when outward …

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 …

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 …