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 …
reactors to significantly more oxidation-resistant materials, thereby enhancing safety …
Current status of materials development of nuclear fuel cladding tubes for light water reactors
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 …
components in light water reactors (LWRs), such as fuel claddings which suffer from …
[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 …
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 …
substrate have been studied with the objective to provide a significant reduction in the …
Recent advances in protective coatings for accident tolerant Zr-based fuel claddings
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 …
acceptable properties for nuclear cores of light water reactors (LWRs). However, severe …
Review of manufacturing technologies for coated accident tolerant fuel cladding
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 …
cladding to increase the safety of nuclear power generation. The key to near-term …
Microstructure, corrosion resistance and oxidation behavior of Cr-coatings on Zircaloy-4 prepared by vacuum arc plasma deposition
T Wei, R Zhang, H Yang, H Liu, S Qiu, Y Wang, P Du… - Corrosion …, 2019 - Elsevier
Cr-coated Zircaloy-4 samples are prepared by vacuum arc plasma deposition and their
microstructure, corrosion resistance and oxidation behavior are investigated. The as …
microstructure, corrosion resistance and oxidation behavior are investigated. The as …
Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding
In an attempt to develop an accident-tolerant fuel (ATF) that can delay the deleterious
consequences of loss-of-coolant-accidents (LOCA), multilayer coatings were deposited onto …
consequences of loss-of-coolant-accidents (LOCA), multilayer coatings were deposited onto …
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 …
zirconium alloy were investigated. A single-layer Cr (8 um) and multilayer Cr (8 μm)/Mo (3 …
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 …
reactors and enhancing the deposition efficiency and economics of surface coating …