Effect of Temperature and Pressure on Steam Testing of Zirconium Alloys PDF Download
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Author: D. S. Kneppel
Publisher:
ISBN:
Category : Aerosols
Languages : en
Pages : 48
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Book Description
Author: D. S. Kneppel
Publisher:
ISBN:
Category : Aerosols
Languages : en
Pages : 48
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Book Description
Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 26
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Author: Stanley Kass
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 28
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Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 106
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Book Description
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102705
Category : Science
Languages : en
Pages : 866
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Book Description
Author: A. A. Kiselev
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 48
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Book Description
Author: A. B. Johnson
Publisher:
ISBN:
Category : Catastrophic corrosion
Languages : en
Pages : 15
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Book Description
A nuclear fuel-failure phenomenon prompted a study of the corrosion properties of the Zircaloy-2 fuel cladding. The principal studies were conducted at 400, 450, 475, and 500 C in steam at 1700 psig. Materials tested were: five lots of Zircaloy-2; one lot of Ozhennite (Zr-0.2Sn-0.1Fe-0.1Ni-0.1Nb); and one lot of crystal bar zirconium. As-fabricated (rolled or extruded) Zircaloy-2 underwent a rapid approach to failure in tests at 475 and 500 C. The attack involved nucleation of nodular oxide which spread across the surface, finally resulting in an accelerated, relatively uniform attack. Ozhennite was resistant to the attack. Heat treatments (? and ? anneals) delayed the catastrophic attack on Zircaloy-2 but not on crystal bar zirconium.
Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 28
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Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 680
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