Stress and temperature-dependent hydride reorientation of Zircaloy-4 cladding and its effect on the ductility degradation
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/00223131.2014.978829
Reference29 articles.
1. Control of hydride orientation in zircaloy
2. Influence of fabrication history on stress-oriented hydrides in zircaloy tubing
3. Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions
4. Dry Storage Demonstration for High-Burnup Spent Nuclear Fuel-Feasibility Study
5. A creep rupture criterion for Zircaloy-4 fuel cladding under internal pressure
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1. The influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4;Journal of Nuclear Materials;2024-11
2. Methodology for numerical evaluation of fracture resistance under pinch loading of spent nuclear fuel cladding containing reoriented hydrides;Nuclear Engineering and Technology;2024-06
3. Micro-mechanisms of the ductile-to-brittle transition in hydrogenated zirconium alloys: A review and a comparison analysis of experimental data and theoretical approaches;Engineering Failure Analysis;2024-05
4. Hydride-Induced Responses in the Mechanical Behavior of Zircaloy-4 Sheets;Metals;2024-02-01
5. The Influence of Hydrogen on the Creep Behavior of Zircaloy-4 Cladding in Low Burnup Regime;2024
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