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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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Journal ArticleDOI
TL;DR: In this paper, a 3D fuel performance code BISON is implemented in order to calculate the hydrogen distribution for arbitrary geometries, such as a nuclear fuel rod, and is now available for BISON users.

57 citations

Journal ArticleDOI
TL;DR: In this article, a model explaining the uniform and nodular corrosion and hydriding behavior in BWRs is presented, where three materials with different second phase particle (SPP) distributions have been characterised in the unirradiated and irradiated conditions.

57 citations

Journal ArticleDOI
TL;DR: In this article, the effect of matrix yield strength on precipitation of hydride phases in zirconium alloys was studied and the results indicated that yield stress has a pronounced effect on hydrides phase stability.

57 citations

Journal ArticleDOI
TL;DR: In this article, chemical interactions between UO2 fuel and Zircaloy-4 cladding under isothermal and transient temperature conditions up to the melting point of Zry (Zry) are described.

56 citations

Journal ArticleDOI
C.J. Rosa1
TL;DR: In this paper, the authors present a review of the kinetics and phenomena associated with the oxidation of pure zirconium metal by oxygen gas, and the obtained results can be used for investigating more complex oxidation kinetics, e.g., oxidation of titanium.
Abstract: Perhaps, with the exception of copper and nickel, zirconium has undergone the most extensive oxidation studies within the last decade or so. The vast interest in the oxidation behavior of zirconium stems mainly from two reasons. Firstly, zirconium alloys are of primary importance in nuclear reactor technology. Due to their low cross section for thermal neutrons and because of their relatively good corrosion resistance against water and steam, these alloys may be considered as favourable materials for many structural components, e.g., cladding tubes for water-cooled nuclear reactors. Consequently, investigations into the oxidation behavior of zirconium are necessary if the more intricate corrosion characteristics of zirconium alloys are to be better understood. Secondly, the zirconium-oxygen system is rather simple when compared with many other metal-oxygen systems. Because of this simplicity, zirconium is amenable to fundamental studies of the oxidation mechanism(s) and the obtained results can be of paramount importance in investigating more complex oxidation kinetics, e.g., oxidation of titanium. The present review is primarily concerned with the kinetics and phenomena associated with the oxidation of “pure” zirconium metal by oxygen gas.

56 citations


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Performance
Metrics
No. of papers in the topic in previous years
YearPapers
202395
2022215
2021137
2020164
2019194
2018219