Proposal to irradiate zircaloy-2 appendage specimens in an NRU fast neutron facility PDF Download
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Author: K. P. Steward
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ISBN:
Category :
Languages : en
Pages : 0
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Author: K. P. Steward
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author:
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Category :
Languages : en
Pages : 0
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Author: C. D. Williams
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Category :
Languages : en
Pages : 0
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Author: R. S. Roberts
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Category :
Languages : en
Pages : 0
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Author: K. P. Steward
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Category :
Languages : en
Pages : 0
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Author: R. S. Roberts
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Category :
Languages : en
Pages : 0
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Author: Arden Lee Bement (Jr.)
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Category : Metallurgy
Languages : en
Pages : 214
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Author: M. Griffiths
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Category :
Languages : en
Pages : 0
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Author: HM. Chung
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Category : Brittle failure
Languages : en
Pages : 24
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Microstructural evolution in Zircaloy-2 and -4 spent-fuel cladding specimens after three years of irradiation in commercial power reactors has been investigated by transmission and high-voltage electron microscopies. Two kinds of precipitates induced by the fastneutron irradiation in the reactors have been identified, that is, Zr3O and cubic-ZrO2 particles approximately 2 to 10 nm in size. By means of specimen tilting and dark-field stereomicroscopy, the bulk nature of the cubic-ZrO2 particles has been shown. The Zr(Fex,Cr1-x)2 and Zr2(Fex,Ni1-x) intermetallic precipitates normally present in the as-fabricated material virtually dissolved in the spent-fuel cladding specimens after a fast-neutron fluence of ~4 x 1021 n/cm2 in the power reactors. The observed radiation-induced phase transformations are discussed in relation with the currently available understanding of the alloy characteristics.
Author: A. L. Bement
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ISBN:
Category : Zirconium-tin alloys
Languages : en
Pages : 416
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