Effect of radial hydrides on the axial and hoop mechanical properties of Zircaloy-4 cladding
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference18 articles.
1. Hydride embrittlement in ZIRCALOY-4 plate: Part I. Influence of microstructure on the hydride embrittlement in ZIRCALOY-4 at 20 °C and 350 °C
2. Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part III. Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C
3. Control of hydride orientation in zircaloy
4. The stress orientation of hydride in zirconium alloys
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1. Annealing cracking in Zr and a Zr-alloy with low hydrogen concentration;Journal of Materials Science & Technology;2024-05
2. Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings;Journal of Nuclear Materials;2024-01
3. Numerical analysis of multi-field coupling behaviors of delayed hydride cracking for thin plate-type Zr-2.5Nb specimens;Engineering Fracture Mechanics;2024-01
4. Characterization of Hydride Precipitation and Reorientation in Zircaloy-4 at Different Metallurgical States;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01
5. Understanding the mechanical integrity of Zircaloy cladding with various radial and circumferential hydride morphologies via image analysis;Journal of Nuclear Materials;2023-10
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