Irradiation effects on corrosion of zirconium alloy claddings-Reference-Cited by-同舟云学术

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Irradiation effects on corrosion of zirconium alloy claddings

Published:1997-09 Issue: Volume:248 Page:268-274
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Lefebvre Florence,Lemaignan Clément

Publisher

Elsevier BV

Subject

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

Reference37 articles.

1. Technique and method for upgrading corrosion performance though Fragema fuel experience feedback;Morel,1994

2. Corrosion of Zirconium in nuclear power plants,1993

3. Precipitate growth kinetics in Zircaloy-4

4. Corrosion optimized Zircaloy for BWR fuel elements;Garzarolli,1994

Cited by 31 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. Corrosion Resistance of Traditional and Advanced Fuel Rod Cladding Materials for Water-Cooled Reactors;Progress in Physics of Metals;2024-06

2. Atomistic simulations of the interaction of edge dislocations with β-Nb precipitates in Zr-Nb alloys;Journal of Physics D: Applied Physics;2024-05-03

3. Development of a Zr-Nb-H-O reactive force field for molecular dynamics simulations of in-reactor corrosion;Computational Materials Science;2024-05

4. Peculiarities of interaction between oxygen and solute/vacancy in commercial-type zirconium-based alloys: A first-principles study;Materials Today Communications;2024-03

5. Effects of He and Ni ion irradiation on the ZrO2/Cr composite coating on Zr1Nb alloy;Journal of Alloys and Compounds;2024-01

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