In situ crack growth studies of hydrided Zircaloy-4 on a single-edge notched tensile specimen
Author:
Publisher
Elsevier BV
Subject
Condensed Matter Physics,General Materials Science,Mechanics of Materials,Metals and Alloys,Mechanical Engineering
Reference18 articles.
1. IAEA, Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors, IAEA-TECDOC-1410, Vienna, 2004.
2. Effect of Hydrogen on Behavior of Materials;Dutton,1976
3. Comments on the stability of zirconium hydride phases in Zircaloy
4. Strain evolution of zirconium hydride embedded in a Zircaloy-2 matrix
5. Evidence of stress-induced hydrogen ordering in zirconium hydrides
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1. Microscopic stress and crystallographic orientation of hydrides precipitated in Zr-1Nb-0.01Cu cladding tube investigated by high-energy X-ray diffraction and EBSD;Journal of Nuclear Materials;2020-12
2. Engineering Materials Research at ESRF;Synchrotron Radiation News;2017-05-04
3. Influence of grain size on fatigue crack propagation and acoustic emission features in commercial-purity zirconium;Materials Science and Engineering: A;2015-06
4. The role of chemical free energy and elastic strain in the nucleation of zirconium hydride;Journal of Nuclear Materials;2013-10
5. Hydride reorientation in Zr2.5Nb studied by synchrotron X-ray diffraction;Acta Materialia;2012-12
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