A comparative study of hydride-induced embrittlement of Zircaloy-4 fuel cladding tubes in the longitudinal and hoop directions
Author:
Affiliation:
1. Graduate School of Engineering, Tohoku University, Sendai, Japan
2. School of Engineering, The University of Tokyo, Tokai-mura, Japan
3. Nuclear Development Co., Tokai, Japan
4. Institute for Materials Research, Tohoku University, Sendai, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2017.1287603
Reference39 articles.
1. Electron microscope observations on the precipitation of zirconium hydride in zirconium
2. Microstructural criteria for abrupt ductile-to-brittle transition induced by δ-hydrides in zirconium alloys
3. Hydrogen in Zircaloy: Mechanism and its impacts
4. Crystallography of Zirconium Hydrides in Recrystallized Zircaloy-2 Fuel Cladding by Electron Backscatter Diffraction
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1. A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes;Journal of Nuclear Materials;2023-02
2. Influence of temperature and hydrogen content on the transverse mechanical properties of Zircaloy-4 fuel cladding;Progress in Nuclear Energy;2022-11
3. Expansion deformation behavior of zirconium alloy claddings with different hydrogen concentrations;Journal of Nuclear Materials;2021-10
4. In-situ tensile deformation of Zircaloy-4 sheets with different hydrogen contents at RT and 300 °C;Materials Science and Engineering: A;2021-04
5. Surface orientation dependence of irradiation-induced hardening in a polycrystalline zirconium alloy;Scripta Materialia;2019-03
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