Mechanical Properties of Irradiated Zirconium, Zircaloy, and Aluminum PDF Download
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Author: Richard E. Schreiber
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 112
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Author: Richard E. Schreiber
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 112
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Author: J. Baicry
Publisher:
ISBN:
Category : Anisotropy
Languages : en
Pages : 19
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Book Description
Irradiation tests conducted for the Advanced Fuel Assembly (AFA) grid development allowed the measurement of the mechanical characteristics, growth, and relaxation of the following materials: stress-relieved, ?-annealed, and ?-quenched Zircaloy-4, and ?-annealed Zr-3Sn-1Mo. The mechanical characteristics of the zirconium alloys approached a limit value as early as 5 x 1024 n m-2, except for the ?-quenched Zircaloy-4 for which the limit value was reached later at about 5 x 1025 n m-2. Uniform elongation at 588 K showed a minimum at about 5 x 1024 n m-2; beyond this fluence, stress-relieved Zircaloy-4 presented the most marked tendency to increase. Longitudinal direction growth of annealed Zircaloy-4 and longitudinal and transverse direction growth of stress-relieved Zircaloy-4 may be expressed by the formula ? = A(?t)n where n = 0.67 (stress-relieved Zircaloy-4) and n = 0.4 (annealed Zircaloy-4). It is doubtful that the growth is associated with a density change. The stress-relaxation of the zirconium base materials is nearly complete for 4 x 1025 n m-2, with the exception of Zr-1Nb which has an intermediate behavior between those of Zircaloy-4 and Inconel 718.
Author: Eugene V. T. Murphy
Publisher: Pinawa, Man. : Materials and Component Development Branch, Whiteshell Nuclear Research Establishment
ISBN:
Category :
Languages : en
Pages : 19
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Author: Spencer H. Bush
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 128
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Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
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Author: Frederic R. Shober
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
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The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Author: A. E. Bibb
Publisher:
ISBN:
Category :
Languages : en
Pages : 38
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Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102705
Category : Science
Languages : en
Pages : 866
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Author: R. K. Wagner
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 44
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