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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.


Papers
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Journal ArticleDOI
TL;DR: In this article, a model for describing hydrogen absorption by Zr alloys during high temperature oxidation in steam was developed, based on the detailed experimental results of recent tests on the kinetics of hydrogen absorption of Zr-1Nb cladding during steam oxidation in the temperature range from 900 to 1200°C.

25 citations

Patent
28 Aug 1989
TL;DR: In this paper, the authors proposed an alloy comprising, by weight percent, 0.5-2.0 niobium and 0.7-1.5 tin, and up to 220 ppm C, and the balance essentially zirconium.
Abstract: This is an alloy comprising, by weight percent, 0.5-2.0 niobium, 0.7-1.5 tin, 0.07-0.14 iron, and 0.03-0.14 of at least one of nickel and chromium, and at least 0.12 total of iron, nickel and chromium, and up to 220 ppm C, and the balance essentially zirconium. Preferably, the alloy contains 0.03-0.08 chromium, and 0.03-0.08 nickel. The alloy is also preferably subjected intermediate recrystallization anneals at a temperature of about 1200°-1300° F., and to a beta quench two steps prior to final size.

25 citations

Journal ArticleDOI
TL;DR: A review of the applications of Zircaloy creep and growth to LWR fuel designs is given in this article, along with an analysis of the impact of in-reactor creep on fuel rod and fuel assembly performance, and comments on potential improvements.

25 citations

Patent
08 Jul 1988
TL;DR: A nuclear reactor fuel assembly includes a fuel rod containing nuclear fuel in a cladding tube formed of an iron-containing zirconium alloy as mentioned in this paper, which has an oxygen content of from 1 to 1.6% by weight and contains alloy components of from 0 to 1% of niobium, 0 to 8% of tin, and at least two metals from the group consisting of iron, chromium and vanadium having from 2 to 4% of oxygen content.
Abstract: A nuclear reactor fuel assembly includes a fuel rod containing nuclear fuel in a cladding tube formed of an iron-containing zirconium alloy A fuel assembly skeleton to which the fuel rod is attached has a structural part formed of the iron-containing zirconium alloy The iron-containing zirconium alloy has an oxygen content of from 01 to 016% by weight and contains alloy components of from 0 to 1% by weight of niobium, 0 to 08% by weight of tin, at least two metals from the group consisting of iron, chromium and vanadium having from 02 to 08% by weight of iron, 0 to 04% by weight of chromium and 0 to 03% by weight of vanadium, a total percent by weight of iron, chromium and vanadium of from 025 to 1% by weight, and a total percent by weight for niobium and tin in the range from 0 to 1% by weight

25 citations

Patent
10 Jun 1988
TL;DR: A stabilized alpha metal matrix provides an improved ductility after irradation without loss of corrosion resistance in a "Zircaloy" alloy modified with measurable amounts of up to 0.6 percent by weight of niobium or 0.1 percent of molybdenum.
Abstract: A stabilized alpha metal matrix provides an improved ductility after irradation without loss of corrosion resistance in a "Zircaloy" alloy modified with measurable amounts of up to 0.6 percent by weight of niobium or 0.1 percent by weight of molybdenum. Tin is present in the Zircaloy in the range of 1.2 to 1.70 percent by weight and the oxygen level is in the range of from 1000 to 1600 ppm. Iron and chromium alloying element levels are those of typical Zircaloys. The average intermetallic precipitates' particle sizes are in the range of from 1200 to 1800 angstroms, thereby providing optimum corrosion resistance of the improved alloy in both boiling water and pressurized water reactors.

25 citations


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