Topic
Zirconium alloy
About: Zirconium alloy is a research topic. Over the lifetime, 6548 publications have been published within this topic receiving 78954 citations. The topic is also known as: zircaloy.
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26 citations
TL;DR: In this article, several novel dispersion fuel compositions with a high uranium content fuel (U9Mo, U5Zr5Nb, U 3 Si) and a zirconium alloy matrix with low melting point (1063-1133 K) have been developed at A.A. Bochvar Institute using a capillary impregnation fabrication method.
26 citations
Patent•
26 Sep 1985TL;DR: In this paper, a combination reduction-distillation vessel is used to produce high quality zirconium or hafnium sponge for nuclear fuel rods, which can be used to line the inner surface of Zircaloy tubing.
Abstract: This is a process for producing high quality zirconium or hafnium sponge. It is especially useful for producing the very high purity zirconium which may be used to line the inner surface zirconium of Zircaloy tubing for nuclear fuel rods. The process uses a combination reduction-distillation vessel which is directly fed with zirconium or hafnium tetrachloride from a molten salt sublimer. A precharge of magnesium chloride is used to prevent reduction of metal outside the inner liner, and thereby facilitate removal of the inner liner after reduction and distillation. The agitator for the molten salt sublimer preferably utilizes a molten metal seal around the agitator shaft.
26 citations
TL;DR: In this article, the mechanism of corrosion and hydriding of zirconium alloys was discussed in relation to the mechanisms of accelerated oxidation of massive ZIRCONIUM hydride.
26 citations
TL;DR: In this article, a dislocation-loop interaction is simulated in the same geometrical, stress and dislocation mobility conditions, and it is shown that the interaction leads to the formation of an helicoidal turn expanding along the dislocation before being blocked below the sample surface.
26 citations