Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion-Reference-Cited by-同舟云学术

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Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion

Published:2021-09 Issue: Volume:190 Page:109652
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Yu Zefeng,Bachhav Mukesh,Teng Fei,He Lingfeng,Couet Adrien^ORCID

Funder

Idaho National Laboratory

U.S. Department of Energy

National Research Council Canada

Office of Nuclear Energy

Laboratory Directed Research and Development

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference65 articles.

1. Corrosion of zirconium alloys used for nuclear fuel cladding;Motta;Annu. Rev. Mater. Res.,2015

2. Investigations of the fresh-core cycle-length and the average fuel depletion analysis of the NuScale core;Sadegh-Noedoost;Ann. Nucl. Energy,2020

3. Effect Of Aging And Irradiation On The Corrosion Of Zr-2. 5 Wt% Nb;Urbanic;Corrosion,1975

4. Effect of Proton Pre-irradiation on Corrosion of Zr-0.5Nb Model Alloys With Different Nb Distributions;Yu,2020

5. Effect of neutron and ion irradiation on the metal matrix and oxide corrosion layer on Zr-1.0Nb cladding alloys;Hu;Acta Mater.,2019

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Observations of solute redistribution obtained using atom probe tomography examinations of bulk Zircaloy neutron irradiated at nominally 410°C;Journal of Nuclear Materials;2024-04

2. The role of secondary phase precipitates in zircaloy corrosion: From point defects to local percolation;Corrosion Science;2024-04

3. STEM/EDS and APT study on the microstructure and microchemistry of neutron irradiated ZIRLOTM;Journal of Nuclear Materials;2023-01

4. Nanoscale chemistry of Zircaloy-2 exposed to three and nine annual cycles of boiling water reactor operation — an atom probe tomography study;Journal of Nuclear Materials;2022-04

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