Patent
Zirconium alloy fuel cladding resistant to PCI crack propagation
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TLDR
In this article, a tubular water reactor fuel cladding has an outer cylindrical layer composed of a conventional zirconium base alloy, and a second inner layer is composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin, approximately 0.5 to 1.4 wt.Abstract:
This invention relates to a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer layer is a second, inner layer composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin; about 0.05 to 0.2 wt. % iron; about 0.05 to 0.4 wt. % niobium; about 0.03 to 0.1 wt. % of either chromium or nickel, alone or in combination with each other; while keeping the sum of the iron chromium and nickel contents below 0.25 wt. %; 300 to 1200 ppm oxygen; and the balance essentially zirconium. The inner layer is characterized by excellent resistance to PCI crack propagation, excellent aqueous corrosion resistance and a fully recrystallized microstructure.read more
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Zirconium-based alloy and method for making a component for a nuclear fuel assembly with same
TL;DR: In this article, a zirconium alloy for nuclear reactor components was proposed, which contained 0.02 to 1 % iron, 0.8 to 2.3 % niobium, less than 2000 ppm of tin, more than 100 ppm of carbon, from 5 to 35 ppm of sulphur and less than 0.25 % of chromium and/or vanadium.
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Zirconium alloy with superior ductility
Anand M. Garde,Satya R. Pati +1 more
TL;DR: A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance under neutron irradiation environment in a zirconium alloy containing tin in a range of 8 to 12 percent, iron in a ranges of 2 to 5 percent, and typically 035 percent, chromium in a ranging of 0.25 to 0.30 percent, niobium in range of from a measurable amount up to 06 percent, Niobium, silicon, and oxygen were added as an alloying element to reduce hydrogen absorption by the alloy and to reduce variations in the corrosion resistance with
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Corrosion resistant cladding for nuclear fuel rods
TL;DR: In this article, a nuclear fuel element for use in the core of a nuclear reactor is disclosed having an improved corrosion resistant cladding, which is comprised of zirconium alloys containing in weight percent 0.5 to 2.
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Alloys based on zirconium having proportional amount of tin, iron, chromium and oxygen
TL;DR: A zirconium alloy containing on weight basis, 0.4-1.5% of niobium, not higher than 0.6% chromium, wherein the sum of weight proportions of tin, iron and chromium is in the range from 0.9 to 1.95 as mentioned in this paper.
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Zirlo material for light water reactor applications
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.
References
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Nuclear fuel element
TL;DR: In this paper, a nuclear fuel element for use in the core of a nuclear reactor is disclosed and has an improved composite cladding comprised of a moderate purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconsium alloy tube.
Patent
Fuel rod for a nuclear reactor fuel assembly
TL;DR: In this article, a fuel rod for a nuclear reactor fuel assembly includes a cladding tube having an outer surface and a given total wall thickness, which is formed of a first zirconium alloy which may have alloy components of from 1.2 to 2% by weight of tin, 0.18 to 0.38% by value of chromium, and a total percent by weight for the components of iron, chromium and nickel in a range of from 0.28-0.37%
Patent
Zirconium alloy fuel cladding resistant to PCI crack propagation
TL;DR: In this paper, the zirconium base alloys have been designed to minimize the adverse effects of pellet-clad interaction, when they are used as a liner bonded to the inside surface of water reactor nuclear fuel cladding.
Patent
Fuel rod for a nuclear reactor
TL;DR: A fuel rod for a nuclear reactor comprises a cladding tube of a zirconium-based alloy, on the internal surface of which there is arranged a layer of ZIRconium containing 0.1-1 per cent by weight tin this article.