Effects of hydride rim on the ductility of Zircaloy-4 cladding-Reference-Cited by-同舟云学术

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Effects of hydride rim on the ductility of Zircaloy-4 cladding

Published:2019-09 Issue: Volume:523 Page:383-390
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Ju-Seong,Kim Ho-A,Kang So-Young,Kim Yong-Soo

Funder

Korea Institute of Energy Technology Evaluation and Planning (KETEP) and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea

Publisher

Elsevier BV

Subject

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

Reference35 articles.

1. Hydrogen Absorption by Zircaloy-2 and Some Other Alloys during Corrosion in Steam

2. Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4

3. Hydrogen in zircaloy-2: Its distribution and heat of transport

4. A Numerical Calculation of the Redistribution of an Interstitial Solute in a Thermal Gradient

Cited by 9 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. Effects of intergranular hydride precipitation on the mechanical behavior of bicrystalline zirconium: A molecular dynamics-based study;Mechanics of Materials;2024-11

2. 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

3. Effects of Hydrogenation on the Corrosion Behavior of Zircaloy-4;Materials;2024-02-28

4. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes;Journal of Nuclear Materials;2023-12

5. A Representative Volume Element Model for Investigating the Hydride Inclusion Effect on Ductility of Zry-Based Nuclear Fuel Cladding;Arabian Journal for Science and Engineering;2023-09-07

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