Irradiation growth of zirconium alloys at 573 k in NRU.
Author : M. A. Miller
Publisher :
Page : 0 pages
File Size : 36,78 MB
Release : 1995
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Author : M. A. Miller
Publisher :
Page : 0 pages
File Size : 36,78 MB
Release : 1995
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Author : M. A. Miller
Publisher :
Page : 0 pages
File Size : 12,80 MB
Release : 1996
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Author : M. A. Miller
Publisher :
Page : 0 pages
File Size : 34,50 MB
Release : 1996
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Author : Atomic Energy of Canada Limited
Publisher :
Page : pages
File Size : 33,92 MB
Release : 1984
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Author : Atomic Energy of Canada Limited
Publisher : Chalk River, Ont. : Chalk River Nuclear Laboratories
Page : 46 pages
File Size : 10,74 MB
Release : 1980
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Author : RB. Adamson
Publisher :
Page : 23 pages
File Size : 20,3 MB
Release : 1984
Category : Alloys
ISBN :
Irradiation growth behavior of zirconium, Zircaloy-2 and Zircaloy-4,Zr-2.5Nb, and Zr-3.5Sn-0.8Mo-0.8Nb (EXCEL) was studied on specimens irradiated in the Experimental Breeder Reactor II (EBR-II) to fluences of 1.2 to 16.9 x 1025 neutrons (n).m-2 (E > 1 MeV) in the temperature range 644 to 725 K. In Zircaloy, growth and growth rate were observed to increase continuously with fluence up to 16.9 x 1025 n.m-2 with no indication of saturation in either recrystallized or cold-worked materials. Positive growth strains of 1.5% and negative strains of approximately 2% to 2.5% were observed in both recrystallized and cold-worked Zircaloy. The formation of both a-type loops and c component dislocations is recrystallized Zircaloy under irradiation appears to be the basis in this material for growth strains similar in magnitude to those in cold-worked Zircaloy. Alloy additions to zirconium can increase growth by as much as an order of magnitude for a given texture at the higher irradiation temperatures and fluences. A sharp change to increasing growth rate with temperature occurs in Zircaloy at ~670 K, with a similar trend indicated for the other alloys. Although growth in all these alloys is a strong function of crystallographic texture, an exact (1-3f) type of dependence is not always apparent. In Zr-2.5Nb the dependence of growth on texture appears to be masked by the precipitation of betaniobium, with a transition to a well-defined texture dependence being a function of fluence and temperature. Significant differences in growth behavior were observed in nominally similar Zircaloys, apparently due to minor microstructural or chemical differences.
Author : JY. Ren
Publisher :
Page : 8 pages
File Size : 28,52 MB
Release : 1994
Category : Irradiation
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Experimental investigation of irradiation growth on annealed Zircaloy-4 and 20% to 50% cold-worked Zr-2.5wt%Nb specimens with stress relief has been carried out. The specimens are irradiated in a heavy water reactor at 610 K to 4.2 x 1024 n/m2 (E > 1.0 MeV). The growth strains increase linearly with fluence. The saturation of growth is not observed for all specimens. The difference of growth behavior between two kinds of Zircaloy-4 tube may be associated with the content of minor alloying elements and impurities that influence the microstructure evolution under irradiation.
Author : R. P. Tucker
Publisher :
Page : 0 pages
File Size : 16,24 MB
Release : 1984
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Author : M. Griffiths
Publisher :
Page : 20 pages
File Size : 10,22 MB
Release : 1989
Category : Anisotropic diffusion
ISBN :
Sponge zirconium and Zr-2.5 wt% Nb, Zircaloy, or Excel alloys all exhibit accelerated irradiation growth compared with high-purity crystal-bar zirconium for irradiation temperatures between 550 to 710 K and fluences between 0.1 to 10 x 1025 n • m-2 (E > 1 MeV). There is generally an incubation period or fluence before the onset of accelerated or "breakaway" growth, which is dependent on the particular material being irradiated, its metallurgical condition before irradiation, and the irradiation temperature.
Author : D. G. Franklin
Publisher : ASTM International
Page : 866 pages
File Size : 22,25 MB
Release : 1984
Category : Science
ISBN : 9780803102705