Hydrogen Redistribution in Zircaloy-2 Under Thermal and Mechanical Stress Gradients
Author : J. M. Markowitz
Publisher :
Page : 26 pages
File Size : 28,19 MB
Release : 1959
Category : Zircaloy-2
ISBN :
Author : J. M. Markowitz
Publisher :
Page : 26 pages
File Size : 28,19 MB
Release : 1959
Category : Zircaloy-2
ISBN :
Author :
Publisher :
Page : pages
File Size : 48,84 MB
Release : 1959
Category :
ISBN :
Past and current work on the study of the movement of dissolved hydrogen in Zircaloy-2 under the influence of thermal and mechanical stress and two-phase activity gradients is reviewed, and the findings are discussed. A program of future work ia presented. (auth).
Author : Myra S. Feldman
Publisher :
Page : 156 pages
File Size : 10,88 MB
Release : 1963
Category : Zircaloy-2
ISBN :
Author : J. M. Markowitz
Publisher :
Page : 42 pages
File Size : 41,74 MB
Release : 1958
Category : Hydrogen
ISBN :
Author : A. W. Sommer
Publisher :
Page : 44 pages
File Size : 21,86 MB
Release : 1960
Category : Hydrogen
ISBN :
Author :
Publisher :
Page : pages
File Size : 19,89 MB
Release : 1958
Category :
ISBN :
By using experimental data, the quantities determimng the extent of dissolved H redistribution under a thermal gradient in Zircaloy were calculated. It is concluded that the phenomenon of hydride precipitation by means of thermaI gradient diffusion of dissolved H in Zircaloy fuel plates and cladding places much more severe restrictions on the allowable pre-operation H content of such elements than was hitherto suspected. The specific effects of operating conditions on H content of plates and cladding are presented in detail. (M.H.R.).
Author :
Publisher :
Page : 1296 pages
File Size : 38,83 MB
Release : 1974
Category : Nuclear energy
ISBN :
Author : E. Hillner
Publisher :
Page : 48 pages
File Size : 12,25 MB
Release : 1964
Category : Hydrogen
ISBN :
Author : PH. Kreyns
Publisher :
Page : 38 pages
File Size : 17,15 MB
Release : 2000
Category : Hydrogen
ISBN :
Zircaloy-4, which is used widely as a core structural material in pressurized water reactors (PWRs), picks up hydrogen during service. Hydrogen solubility in Zircaloy-4 is low and zirconium hydride phases precipitate after the Zircaloy-4 lattice becomes supersaturated with hydrogen. These hydrides embrittle the Zircaloy-4, degrading its mechanical performance as a structural material. Because hydrogen can move rapidly through the Zircaloy-4 lattice, the potential exists for large concentrations of hydride to accumulate in local regions of a Zircaloy component remote from its point of entry into the component. Much has been reported in the literature regarding the long-range migration of hydrogen through Zircaloy under concentration gradients and temperature gradients. Relatively little has been reported, however, regarding the long-range migration of hydrogen under stress gradients. This paper presents experimental results regarding the long-range migration of hydrogen through Zircaloy in response to both tensile and compressive stress gradients. The importance of this driving force for hydrogen migration relative to concentration and thermal gradients is discussed.
Author :
Publisher :
Page : 918 pages
File Size : 45,89 MB
Release : 1972
Category : Nuclear energy
ISBN :