Observations on the Corrosion of Zirconium Alloys Containing Copper and Molybdenum PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages : 20
Book Description
A program to study zirconium-base alloys containing 1.0 wt% to 2.0 wt% copper with 1.5 wt% to 2.5 wt% molybdenum for possible use in natural uranium fueled power reactors is being conducted. As part of this program, a series of alloys was prepared for corrosion testing in steam at 400C (750F) and 1500 psi. Additions of 0.25 wt% tin and 0.25 wt% iron were made to some Zr-Cu-Mo alloys and the corrosion behaviour of these alloys after heat treating at 750C (1380F) and 850C (1560F) was studied.
Author: Publisher: ISBN: Category : Languages : en Pages : 20
Book Description
A program to study zirconium-base alloys containing 1.0 wt% to 2.0 wt% copper with 1.5 wt% to 2.5 wt% molybdenum for possible use in natural uranium fueled power reactors is being conducted. As part of this program, a series of alloys was prepared for corrosion testing in steam at 400C (750F) and 1500 psi. Additions of 0.25 wt% tin and 0.25 wt% iron were made to some Zr-Cu-Mo alloys and the corrosion behaviour of these alloys after heat treating at 750C (1380F) and 850C (1560F) was studied.
Author: H. M. Skelly Publisher: Queen's Printer ISBN: Category : Metals Languages : en Pages : 40
Book Description
Investigation to determine the transformation reaction of a Zr-1.0% Cu-1.5% Mo alloy quenched from the beta phase and aged at 500C (930F) and to observe any anomalies in its corrosion behaviour during transformation when tested in steam at 400C (750F) and 1500 psi. The corrosion behaviour of a second alloy, Zr-0.5% Cu-0.5% Mo was also examined. Micro-examinations were made of the corrosion film during transformation and an electron-probe microanalyser was used to investigate the composition of the intermetallic phases.
Author: Publisher: ISBN: Category : Languages : en Pages : 7
Book Description
At the present time, zircaloy-2 is considered to be the most attractive material available for use as fuel sheathing and pressure tubing in water-cooled natural uranium nuclear reactors. However, to keep up with reactor design, considerable work is being done to develop zirconium alloys with greater strength than zircaloy-2 and with as good or better corrosion resistance. This report describes the effect of additions of 0.062 wt % Pd and 0.106 wt % Au on the corrosion resistance of zircaloy-2 in steam at 400C (750F) and 1500 psi.
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Author: Sam Kass
Author: H. M. Skelly
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Author: Boris Grigorevich Parfenov
Author: C. F. Dixon
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