Oxide growth and oxygen transport in proton irradiated Zircaloy-4 oxide layers-Reference-Cited by-同舟云学术

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Oxide growth and oxygen transport in proton irradiated Zircaloy-4 oxide layers

Published:2021-09 Issue: Volume:190 Page:109655
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Jones Christopher^ORCID,Gass Mhairi,Preuss Michael^ORCID,Moore Katie L.

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference36 articles.

1. Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants;IAEA,1998

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

3. Corrosion of zirconium alloys;Allen,2012

4. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys;Cox;J. Nucl. Mater.,2005

5. Corrosion of Zirconium Alloys in Nuclear Power Plants;Nechaev,1993

Cited by 3 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. Secondary ion mass spectrometry;Nature Reviews Methods Primers;2024-05-09

2. Insights into the interfacial speciation of Ni in the corrosion layer of high burnup Zircaloy-2 cladding: A combined XRD, XAS, and LFDFT study;Corrosion Science;2023-05

3. Dynamic implantation – an improved approach for a large area SIMS measurement;Journal of Analytical Atomic Spectrometry;2023

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