The effect of fabrication variables on the mechanical properties of zirconium alloy fuel cladding PDF Download
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Author: B. A. Cheadle
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Languages : en
Pages : 0
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Author: B. A. Cheadle
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Category :
Languages : en
Pages : 0
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Author: D. G. Hardy
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Category :
Languages : en
Pages : 0
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Author:
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Category : Nuclear energy
Languages : en
Pages : 640
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Author:
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Category : Aeronautics
Languages : en
Pages : 832
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Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
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Category : Nuclear engineering
Languages : en
Pages : 1244
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Author:
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Category :
Languages : en
Pages : 22
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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.
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Category : Energy development
Languages : en
Pages : 720
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Category : Metallurgy
Languages : en
Pages : 1390
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Author: United States. Congress. House. Committee on Appropriations
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Category : Public works
Languages : en
Pages : 520
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Author: United States. Congress. House. Committee on Appropriations
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Category : Finance, Public
Languages : en
Pages : 1888
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