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Zirconium alloys in nuclear technology.

A. Scaroni
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The article was published on 1972-01-01 and is currently open access. It has received 28 citations till now. The article focuses on the topics: Zirconium alloy & Corrosion.

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Instituto de Pesquisas Energéticas e Nucleares

TL;DR: The activities that have been executed in Animal House Facilities of IPEN, including the refurbishment project and the adaptation of the facilities are described.
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Oxidation behavior and microstructure evolution of alumina-forming austenitic & high entropy alloys in steam environment at 1200 °C

TL;DR: In this article, the growth of oxide scale is discussed based on the oxygen partial pressure of metal oxides and dissociation oxygen pressure of the steam at 1200 °C, and it is shown that adding yttrium to AFA or niobium to HEA shows no evidence of scale exfoliation.
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Point defect effects on tensile strength of α−zirconium studied by molecular dynamics simulations

TL;DR: In this paper, the tensile strength of α − Zr is studied by molecular dynamics simulations. And the authors show that the yield stresses and corresponding yield strains decrease with the increase of the defect concentration for the three types of point defects studied.
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Hot Deformation Behaviour and Microstructural Evaluation of Zr-1Nb Alloy

TL;DR: In this article, hot compression tests were performed to understand the deformation behavior of Zr-1Nb alloy in the temperature range of 700-1050°C, which envelopes α-phase, (α+β) phase, and β-phase.
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Revealing the effect of local stresses on twin growth mechanisms in titanium using synchrotron X-ray diffraction

TL;DR: In this paper, the effects of local stresses on twin thickening using in-situ synchrotron experiments with differential aperture X-ray microscopy were revealed using 3D stress fields with a spatial resolution of 0.5 μ m.