RADIATION-INDUCED DISLOCATION AND GROWTH BEHAVIOR OF ZIRCONIUM AND ZIRCONIUM ALLOYS – A REVIEW
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel cladding and guide tubes because they have excellent corrosion- and radiation-resistant properties.
SANG IL CHOI, JI HYUN KIM
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Production of (Sm,Zr)(Fe,Co)3 magnets
This study was aimed at the improvement of SmFe3-based alloys prepared by means of melt-spinning. A systematic study was carried out on (Sm1-xZrx)(Fe0.75Co0.25)3 (x = 0–0.4) alloys melt-spun at a wheel speed of 50 m/s and annealed at 773–1173 K.
Tetsuji Saito
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Overheating threshold and its effect on time–temperature-transformation diagrams of zirconium based bulk metallic glasses [PDF]
A pronounced effect of overheating is observed on the crystallization behavior for the three zirconium-based bulk metallic glasses: Zr41.2Ti13.8Cu12.5Ni10Be22.5, Zr57Cu15.4Ni12.6Al10Nb5, and Zr52.5Cu17.9Ni14.6Al10Ti5.
Johnson, W. L. +4 more
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Research progress on corrosion and protection of zirconium alloys [PDF]
Zirconium alloys are widely used as structural materials in civil power reactors, nuclear-powered aircraft carriers, nuclear submarines and space vehicles as well as medical materials due to their excellent nuclear properties and biocompatibility ...
Zishuai HU +5 more
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Numerical modelling of dynamics of free boundary of hydride formation
One of the most important requirements for the reactor's active zone materials (made of zirconium alloys) is low hydrogen absorptivity since hydrogen embrittlement may cause zirconium cladding damage.
Yury Zaika +2 more
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Influence of Zirconium Percentage on Microhardness and Corrosion Resistance of Ti50 Ni50-xZrx Shape Memory Alloys [PDF]
To obtain high temperature shape memory alloys of the lower cost Ni-Ti-X system, elements such as Hf and Zr are introduced to modify the thermal and mechanical properties of these alloys. This work studied the production and characterization of Ti50 Ni50-
Alana Pereira Ramos +3 more
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Production of Zirconium-Niobium Alloys for Nuclear Reactors Fuel Rods via SHS Process
This article presents the results of studies of the self-propagating high-temperature synthesis (SHS) for obtaining zirconium alloys with niobium by the method of calcium-thermal reduction of nuclear-grade zirconium tetrafluoride in the presence of ...
Anatoly Mukhachev +2 more
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Ab-initio calculations for structural properties of Zr-Nb alloys [PDF]
Ab-initio calculations for the structural properties of Zr-Nb alloys at different values of the niobium concentration are done at zero temperature. Different cases for Zr-Nb alloys with unit cells having BCC and HCP structures are considered.
Kharchenko, Dmitrii O. +1 more
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Boundary-value problem with free boundary: zirconium alloy hydrogenation
One of the most important requirements for the reactor’s active zone materials (made of zirconium alloys) is low hydrogen absorptivity since hydrogen embrittlement may cause zirconium cladding damage.
Yury Zaika, Natalia Rodchenkova
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Investigations of Zr(IV) in LiF-CaF2: stability with oxide ions and electroreduction pathway on inert and reactive electrodes [PDF]
In this work, a detailed electrochemical study of the molten LiF-CaF2-ZrF4 system is provided in the 810-920°C temperature range, allowing the determination of the reduction potential, the diffusion coefficient and the reduction mechanism of dissolved Zr(
Cassayre, Laurent +4 more
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