scholarly journals Effects of hydride precipitation on the mechanical property of cold worked zirconium alloys in fully recrystallized condition

2020 ◽  
Vol 52 (2) ◽  
pp. 352-359 ◽  
Author(s):  
Hoon Lee ◽  
Kyung-min Kim ◽  
Ju-Seong Kim ◽  
Yong-Soo Kim
2008 ◽  
Vol 110 (1) ◽  
pp. 56-60 ◽  
Author(s):  
Yanzhang Liu ◽  
Qian Peng ◽  
Wenjin Zhao ◽  
Hongman Jiang

2015 ◽  
Vol 466 ◽  
pp. 12-20 ◽  
Author(s):  
Jacob Bair ◽  
Mohsen Asle Zaeem ◽  
Michael Tonks

2014 ◽  
Vol 47 (1) ◽  
pp. 303-315 ◽  
Author(s):  
Zhiyang Wang ◽  
Ulf Garbe ◽  
Huijun Li ◽  
Yanbo Wang ◽  
Andrew J. Studer ◽  
...  

This work presents a detailed microstructure and texture study of various hydrided Zircaloy-4 materials by neutron diffraction and microscopy. The results show that the precipitated δ-ZrH1.66generally follows the δ(111)//α(0001) and δ[1{\overline 1}0]//α[11{\overline 2}0] orientation relationship with the α-Zr matrix. The δ-hydride displays a weak texture that is determined by the texture of the α-Zr matrix, and this dependence essentially originates from the observed orientation correlation between α-Zr and δ-hydride. Neutron diffraction line profile analysis and high-resolution transmission electron microscopy observations reveal a significant number of dislocations present in the δ-hydride, with an estimated average density one order of magnitude higher than that in the α-Zr matrix, which contributes to the accommodation of the substantial misfit strains associated with hydride precipitation in the α-Zr matrix. The present observations provide an insight into the behaviour of δ-hydride precipitation in zirconium alloys and may help with understanding the induced embrittling effect of hydrides.


1983 ◽  
Vol 31 (9) ◽  
pp. 1381-1391 ◽  
Author(s):  
V. Perovic ◽  
G.C. Weatherly ◽  
C.J. Simpson

2015 ◽  
Vol 2015.23 (0) ◽  
pp. 111-112
Author(s):  
Shin Numaga ◽  
Shigeru Kuramoto ◽  
Junya Kobayashi

2007 ◽  
Vol 539-543 ◽  
pp. 3377-3382 ◽  
Author(s):  
Indrajit Charit ◽  
K. Linga Murty

Zirconium (Zr) alloys are best known for their use in nuclear reactor applications. A hexagonally close-packed structure with a low c/a ratio and very limited slip systems leads to strong textures in these alloys during fabrication processes. These alloys are used in cladding applications for encapsulating fuel pellets, and undergo various stress conditions in-service. Hence, it is necessary to understand the creep properties of Zr alloys to predict the life of reactor claddings. Due to the unique texture, the creep deformation of these alloys is anisotropic in nature. The texture of Zircaloys was determined by X-ray diffraction experiments, and expressed in terms of pole figures and crystalline orientation distribution functions. Biaxial creep testing of thin walled tubing was used to study the creep anisotropy. Creep loci evaluation based on the experimental data and model predictions are compared. It is found that the models can predict the creep loci for recrystallized alloy very well. However, they fail to explain the behavior of the cold worked alloys. When stress enhancements due to the grain boundary sliding are taken into account, the predicted creep loci correlated well with that constructed from the experimental data.


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