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V. Fidleris

Researcher at Atomic Energy of Canada Limited

Publications -  6
Citations -  157

V. Fidleris is an academic researcher from Atomic Energy of Canada Limited. The author has contributed to research in topics: Creep & Zirconium alloy. The author has an hindex of 5, co-authored 6 publications receiving 154 citations.

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Uniaxial in-reactor creep of zirconium alloys.

TL;DR: In this paper, the experimental results of 24 uniaxial in-reactor creep tests on various zirconium alloys, covering a range of stresses from 7 to 42 kg/mm2 and temperatures between 200 and 400 °C.
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Dislocation loop generation and irradiation growth in a zirconium single crystal

TL;DR: In this article, a zirconium single crystal was irradiated at 473-523 K and its growth measured by transmission electron microscopy (TEM) at various fluences by TEM, and an explanation for the measured growth was given in terms of defects that are too small to be seen in the electron microscope, i.e. point defects or very small defect clusters.
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In-reactor creep of zirconium-2.5 wt% niobium at 570 K

TL;DR: In this article, the effect of fast neutron flux at 570 K on the creep rate of specimens of zirconium-2.5 wt% niobium alloy taken from tubes in various metallurgical conditions, using both constant load tensile creep machines and bent-beam stress relaxation.
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IRRADIATION CREEP IN Zr SINGLE CRYSTALS

TL;DR: In this article, a single crystal of crystal bar Zr was irradiated, unstressed, at 570 K in a fast (> 1 MeV) neutron flux of 5.5 × 10 16 n/m 2 -s.
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The creep strength of quenched and aged Zr-2.5 wt% Nb alloy

TL;DR: In this paper, the creep at 573 and 723 K of quenched and aged Zr-2.5 wt% Nb alloy was studied as a function of (i) solution temperature in the range 1073 to 1273 K, (ii) oxygen concentration of 170 to 1150 ppm, and (iii) aging at 673 or 773 K.