Proposal to irradiate zircaloy-2 fuel specimens in an NRU fast neutron facility PDF Download
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Author: K. P. Steward
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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: 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: C. D. Williams
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Category :
Languages : en
Pages : 0
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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.
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Languages : en
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Microstructural evolution in Zircaloy-2 and -4 spent-fuel cladding specimens after approx. 3 years of irradiation in commercial power reactors has been investigated by TEM and HVEM. Two kinds of precipitates induced by the fast-neutron irradiation in the reactors have been identified, i.e., Zr3O and cubic-ZrO2 particles approximately 2 to 10 nm in size. By means of a weak-beam dark-field ''2-1/2D-microscopy'' technique, the bulk nature of the precipitates and the surficial nature of artifact oxide and hydride phases could be discerned. The Zr(Fe/sub x/, Cr/sub 1-x/)2 and Zr2(Fe/sub x/, Ni/sub 1-x/) intermetallic precipitates normally present in the as-fabricated material virtually dissolved in the spent-fuel cladding specimens after a fast-neutron fluence of approx. 4 x 1021 ncm−2 in the power reactors. The observed radiation-induced phase transformations are compared with predictions based on the currently available understanding of the alloy characteristics. 29 refs.
Author: C. L. Whitmarsh
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Category : Nuclear reactors
Languages : en
Pages : 74
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Author: Arden Lee Bement (Jr.)
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Category : Metallurgy
Languages : en
Pages : 214
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