Journal ArticleDOI
Irradiation growth of zirconium single crystals
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TLDR
In this paper, the growth of zirconium single crystals has been studied during neutron irradiation at 353 K and 553 K at fluences up to 2× 10 25 n/m 2.About:
This article is published in Journal of Nuclear Materials.The article was published on 1981-10-01. It has received 44 citations till now. The article focuses on the topics: Zirconium & Vacancy defect.read more
Citations
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Journal ArticleDOI
A review of microstructure evolution in zirconium alloys during irradiation
TL;DR: In this article, anisotropic interstitial diffusion has been observed in ZrSn and ZrNb alloys at temperatures between about 573 and 873 K, at least for fluences up to 7 × 10 25 n m −2.
Journal ArticleDOI
Point defect diffusion in α-Zr
TL;DR: In this article, a review of defects in α-Zr is concerned with atomic and vacancy diffusion and with solute effects on radiation damage, both in a general context and in terms of problems and features more specifically associated with αZr, including the anisotropic crystal structure, the limited temperature interval of α-phase stability, imposed by the α-β (hcp-bcc) transformation, and the tendency for Zr to have high residual impurity levels.
Journal ArticleDOI
Mechanisms of irradiation growth of alpha-zirconium alloys
TL;DR: In this article, the authors apply new theoretical concepts to assist in understanding growth, e.g., the potential role of anisotropic diffusion in segregating point defects to different sinks and "negative" growth caused by the relaxation of intergranular constrains.
Book ChapterDOI
Radiation Effects in Zirconium Alloys
F. Onimus,J.L. Béchade +1 more
TL;DR: In this article, the effects of neutron irradiation on zirconium alloys are described, describing damage creation and point-defect evolution leading to loops formation and secondary-phase evolution under irradiation.
Journal ArticleDOI
Irradiation creep and growth of zirconium alloys: A critical review
TL;DR: A review of the evolution in measurement methodologies (either from controlled experiments in materials test reactors or gauging of power reactor components) is described together with the results gleaned from such measurements.
References
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Journal ArticleDOI
Single-Crystal Elastic Moduli and the hcp → bcc Transformation in Ti, Zr, and Hf
E. S. Fisher,C. J. Renken +1 more
Journal ArticleDOI
Self-interstitial atoms in metals
TL;DR: The present state of knowledge and understanding of the properties of self-interstitial atoms (SIAs) in metals is reviewed in this paper, with a discussion of the structure of SIAs and those properties which relate to structure such as relaxation volumes, elastic polarizabilities, defect vibrations, geometry of jump processes, and elastic interactions.
Journal ArticleDOI
Plastic deformation of zirconium single crystals
A Akhtar,A Teghtsoonian +1 more
TL;DR: In this paper, the deformation modes operative at various crystal orientations and the effect of purity, temperature, orientation and strain rate, on the work hardening parameters have been investigated.
Journal ArticleDOI
Characterization of neutron irradiation damage in zirconium alloys — an international “round-robin” experiment
D.O. Northwood,R.W. Gilbert,L.E. Bahen,P.M. Kelly,R.G. Blake,A. Jostsons,P.K. Madden,D. Faulkner,W.L Bell,R.B. Adamson +9 more
TL;DR: In this paper, an international round-robin experiment was conducted to study the nature of the damage structure in neutron irradiated zirconium and zircaloy-2 using transmission electron microscopy.
Journal ArticleDOI
The nature of dislocation loops in neutron irradiated zirconium
TL;DR: In this article, the nature of the damage structure in neutron-irradiated zirconium has been studied using transmission electron microscopy using a 3⊂11 2 0〉 Burgers vector.