The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water
Author : Stanley Kass
Publisher :
Page : 34 pages
File Size : 46,25 MB
Release : 1958
Category : Nuclear fuels
ISBN :
The Corrosion Properties of Zirconium-base Fuel Alloys
Author : Sam Kass
Publisher :
Page : 42 pages
File Size : 29,96 MB
Release : 1956
Category : Nuclear fuels
ISBN :
Book Description
Corrosion of Zirconium Alloys in 900° Steam
Author : J. Paul Pemsler
Publisher :
Page : 26 pages
File Size : 13,78 MB
Release : 1958
Category : Steam
ISBN :
Book Description
Nuclear Science Abstracts
Author :
Publisher :
Page : 948 pages
File Size : 38,78 MB
Release : 1970
Category : Nuclear energy
ISBN :
Book Description
Specific Zirconium Alloy Design Program Quarterly Progress Report
Author :
Publisher :
Page : 128 pages
File Size : 43,61 MB
Release : 1962-02
Category : Nuclear reactors
ISBN :
Book Description
Oxidation of Zirconium and Zirconium Alloys
Author :
Publisher :
Page : 48 pages
File Size : 16,47 MB
Release : 1959
Category : Oxidation
ISBN :
Book Description
The oxidation rate was found to be relatively insensitive to various types of surface preparations in the temperature range 400 to 700 deg C. No dependence of reaction rate on oxygen pressure was observed. The cubic rate law also was obeyed by foil specimens at 700 deg C; however, the rate constants were slightly larger than values obtained from parallelepiped samples.
Zirconium in the Nuclear Industry
Author : Gerry D. Moan
Publisher : ASTM International
Page : 891 pages
File Size : 21,40 MB
Release : 2002
Category : Nuclear fuel claddings
ISBN : 0803128959
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Zirconium in the Nuclear Industry: Tenth International Symposium
Author : A. M. Garde
Publisher : ASTM International
Page : 805 pages
File Size : 40,22 MB
Release : 1994
Category : Nuclear fuel claddings
ISBN : 0803120117
Book Description
Zirconium in the Nuclear Industry
Author : George P. Sabol
Publisher : ASTM International
Page : 907 pages
File Size : 45,64 MB
Release : 1996
Category : Nuclear fuel claddings
ISBN : 0803124066
Book Description
Development and Properties of Uranium-base Alloys Corrosion Resistant in High Temperature Water
Author : I. Cohen
Publisher :
Page : 322 pages
File Size : 39,6 MB
Release : 1955
Category : Uranium alloys
ISBN :
Book Description
The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed.
