Transformation Reaction and Corrosion Behaviour of Two Zirconium-copper-molybdenum Alloys PDF Download
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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: 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 : 25
Book Description
The low thermal neutron-capture cross section of zirconium, coupled with good mechanical properties and corrosion resistance, have made this metal of practical interest in nuclear engineering. The work presented in this paper was part of a study of zirconium-copper-molybdenum alloys. The investigation studied the transformation reactions occurring during ageing of solution heat-treated alloys and determined the effect of heat treatment on their corrosion behaviour in steam.
Author: Publisher: ISBN: Category : Languages : en Pages : 22
Book Description
At the present time, zircaloy is generally considered to be the most attractive material available for water-cooled power reactor fuel cladding and core components such as pressure tubes, but projected power reactor designs already require a better material having improved mechanical properties and corrosion resistance at the higher operating temperatures contemplated. As part of the Canadian program directed toward natural uranium fuelled power reactor development, a study of zirconium-based alloys containing between 1 and 2 wt% copper, combined with from 1.5 to 2.5 wt% molybdenum was made. In this investigation, the effects of solution and ageing heat treatments were examined in metallographic structure and resulting room temperature mechanical properties. An assessment of hot working fabrication characteristics was also made.
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
Author: H. M. Skelly
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Author: Robert Graham Walmsley
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