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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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Book ChapterDOI
BF Kammenzind1, BM Berquist1, R Bajaj1, PH Kreyns1, DG Franklin1 
01 Nov 1998
TL;DR: In this article, the long range migration of hydrogen through Zircaloy in response to both tensile and compressive stress gradients is discussed. And the importance of this driving force for hydrogen migration relative to concentration and thermal gradients are discussed.
Abstract: Zircaloy-4, which is used widely as a core structural material in pressurized water reactors (PWRs), picks up hydrogen during service. Hydrogen solubility in Zircaloy-4 is low and zirconium hydride phases precipitate after the Zircaloy-4 lattice becomes supersaturated with hydrogen. These hydrides embrittle the Zircaloy-4, degrading its mechanical performance as a structural material. Because hydrogen can move rapidly through the Zircaloy-4 lattice, the potential exists for large concentrations of hydride to accumulate in local regions of a Zircaloy component remote from its point of entry into the component. Much has been reported in the literature regarding the long range migration of hydrogen through Zircaloy under concentration gradients and temperature gradients. Relatively little has been reported, however, regarding the long range migration of hydrogen under stress gradients. This paper presents experimental results regarding the long range migration of hydrogen through Zircaloy in response to both tensile and compressive stress gradients. The importance of this driving force for hydrogen migration relative to concentration and thermal gradients is discussed.

31 citations

Patent
10 Jul 1981
TL;DR: In this article, a cladding tube is provided which has at the same time good corrosion properties and mechanical properties by performing the β-quenching prior to a cold rolling, after which an intermediate annealing is performed at a temperature of 500°-610° C.
Abstract: In the manufacture of cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors by extrusion of the zirconium-based alloy and cold rollings of the extruded product with annealings, intermediate annealings, between the cold rollings and a β-quenching prior to the last cold rolling, a cladding tube is provided which has at the same time good corrosion properties and mechanical properties by performing the β-quenching prior to a cold rolling, after which an intermediate annealing is performed at a temperature of 500°-610° C

31 citations

Journal ArticleDOI
TL;DR: In this paper, the authors apply concepts from semiconductor defect physics and catalysis to develop materials engineering strategies for thwarting hydrogen uptake in ZrO${}_{2}$ film on a Zr alloy, a model system that is important for materials in nuclear reactors.
Abstract: Hydrogen embrittlement of metallic alloys is critical to the aging and failure of components in power plants and infrastructure. Embrittlement begins with hydrogen penetrating the protective oxide film that naturally grows on a surface in air. The authors apply concepts from semiconductor defect physics and catalysis to develop materials engineering strategies for thwarting hydrogen uptake. For ZrO${}_{2}$ film on a Zr alloy, a model system that is important for materials in nuclear reactors, they demonstrate that one can use doping to tune the chemical potential of electrons in ZrO${}_{2}$ either to minimize the solubility of hydrogen, or to facilitate its evolution as H${}_{2}$ gas from the surface.

31 citations

Journal ArticleDOI
TL;DR: Amorphous Co33Zr67 alloy, prepared by rapid solidification of its components (Co, Zr) in an argon atmosphere, was investigated in view of its possible application as electrocatalytic material for the hydrogen evolution reaction (her) as mentioned in this paper.
Abstract: Amorphous Co33Zr67 alloy, prepared by rapid solidification of its components (Co, Zr) in an argon atmosphere, was investigated in view of its possible application as electrocatalytic material for the hydrogen evolution reaction (her) Electrocatalytic efficiency was evaluated on the basis of electrochemical and impedance measurements carried out in deaerated 1 M NaOH solution The results were compared with polycrystalline Co and Zr metals The Tafel slope, bc and the value of exchange current density, j0 confirmed rather good electrocatalytic properties of Co; on the contrary, pure Zr exhibited very poor activity for the her which was influenced by the presence of a ZrO2 surface layer due to high affinity of Zr for oxygen Improved electrocatalytic performances were obtained after the as quenched Co33Zr67 samples were chemically pretreated in HF solution The true kinetic parameters of these electrodes for the hydrogen evolution reaction resembled that of Co, but the stability and activity in the highest state exceeded those of pure polycrystalline Co electrode Experimental results of hydrogen evolution kinetics on the Co33Zr67 alloy were discussed using known electronic structure of Co–Zr amorphous alloys, ionicity difference between Co and Zr, as well as the free energy of adsorption and the bond strength of hydrogen adsorbed on Co

31 citations

ReportDOI
01 Aug 2015
TL;DR: In this paper, alternative materials with reduced oxidation kinetics as compared to zirconium alloys are sought to enable enhanced accident-tolerant fuels and cores in light water nuclear power plants.
Abstract: Fuels and core structures in current light water reactors (LWR’s) are vulnerable to catastrophic failure in severe accidents as unfortunately evidenced by the March 2011 Fukushima Dai-ichi Nuclear Power Plant Accident. This vulnerability is attributed primarily to the rapid oxidation kinetics of zirconium alloys in a water vapor environment at very high temperatures. Zr alloys are the primary material in LWR cores except for the fuel itself. Therefore, alternative materials with reduced oxidation kinetics as compared to zirconium alloys are sought to enable enhanced accident-tolerant fuels and cores.

31 citations


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