Microstructural influence on uniform corrosion of Zircaloy nuclear fuel claddings-Reference-Cited by-同舟云学术

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Microstructural influence on uniform corrosion of Zircaloy nuclear fuel claddings

Published:1993-04 Issue:2 Volume:200 Page:207-217
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wadman Boel,Andrén Hans-Olof,Nyström Anna-Lena,Rudling Peter,Pettersson Håkan

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference22 articles.

1. Proc. on Fundamental Aspects of Corrosion of Zirconium Base Alloys in Water Reactor Environments;Andersson,1990

2. Proc. Int. Topical Meeting on LWR Fuel Performance;Massih,1991

3. Proc. Int. Symp. on Improvements in Water Reactor Fuel Technology and Utilization;Andersson,1987

Cited by 15 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. Improvement and prediction technology of the water-side corrosion of zirconium alloy: the developmental tendency;Journal of Physics: Conference Series;2024-08-01

2. The gradual disappearance of yield plateau in Zr–Sn–Nb–Fe–Mo alloy by the trace addition of Cr and V;Materials Science and Engineering: A;2019-07

3. Atom probe microscopy characterization of as quenched Zr–0.8wt% Fe and Zr–0.15wt% Cr binary alloys;Materials Letters;2013-01

4. How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys;Acta Materialia;2012-12

5. Methods of quantitative matrix analysis of Zircaloy-2;Ultramicroscopy;2011-05

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