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Interdiffusion In Zircaloy 2 Clad U 2 W O Zr Fuel Materials And Its Effect Upon Corrosion Behavior
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Book Synopsis Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior by : A. L. Geary
Download or read book Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior written by A. L. Geary and published by . This book was released on 1960 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Diffusion Annealing as a Means of Improving Corrosion Resistance of Zircaloy-2 Clad, Uranium-2 W/o Zirconium Rods by : R. G. Jenkins
Download or read book Diffusion Annealing as a Means of Improving Corrosion Resistance of Zircaloy-2 Clad, Uranium-2 W/o Zirconium Rods written by R. G. Jenkins and published by . This book was released on 1960 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis CORROSION BEHAVIOR OF DEFECTED FUEL ELEMENTS WITH U-2 W/o Zr CORE CLAD WITH ZIRCALOY-2 by :
Download or read book CORROSION BEHAVIOR OF DEFECTED FUEL ELEMENTS WITH U-2 W/o Zr CORE CLAD WITH ZIRCALOY-2 written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The aqueous corrosion behavior of defected fuel elements having a U-2 wt. % Zr core with Zircaloy-2 cladding has been studied. A standard diffusion heat treatment for 7 hours at 880 C, followed by moderately rapid cooling, was established to overcome the effect of subtle defects in 15-mil Zircaloy cladding. The development of this heat treatment was carried out primarily with small rod specimens, which were also used to obtain data on aurxiliary effects of thw diffusion heat treatment. The heat treatment has been applied to full diameter tubes. One of these tubes was tested with subtle defects and various sections have been observed following the insertion of gross defects. These observations have shown a difference in the rate of hydrogen evolution as a result of heat treatment. In addition, the heat treatment changes the nature of failure in both full diameter tube sections and small rods. The presence of 2 wt. % Zr in the core reduces the corrosion rate considerably. Comparative quantitative data are presented for uranium alloys with various zirconium contents up to 15 wt. %. (auth).
Book Synopsis The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water by : Stanley Kass
Download or read book The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water written by Stanley Kass and published by . This book was released on 1958 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Silicon, Nitrogen, and Oxygen on the Corrosion and Hydrogen Absorption Performance of Zircaloy-2 by : S. Kass
Download or read book Effects of Silicon, Nitrogen, and Oxygen on the Corrosion and Hydrogen Absorption Performance of Zircaloy-2 written by S. Kass and published by . This book was released on 1963 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Corrosion of Zircaloy-2 in Steam Containing Fluoride-ion Additions by : R. S. Young
Download or read book Corrosion of Zircaloy-2 in Steam Containing Fluoride-ion Additions written by R. S. Young and published by . This book was released on 1963 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effect of Impurity Levels on Zircaloy 2 Microstructure, Mechanical Properties, and Corrosion Rates by : H. Kato
Download or read book Effect of Impurity Levels on Zircaloy 2 Microstructure, Mechanical Properties, and Corrosion Rates written by H. Kato and published by . This book was released on 1964 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Corrosion Properties of Zirconium-base Fuel Alloys by : Sam Kass
Download or read book The Corrosion Properties of Zirconium-base Fuel Alloys written by Sam Kass and published by . This book was released on 1956 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Corrosion of Zirconium Alloys written by and published by . This book was released on 1964 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Visual Study of the Corrosion of Defected Zircaloy-2-clad Fuel Specimens by Hot Water by : Elmer F. Stephan
Download or read book A Visual Study of the Corrosion of Defected Zircaloy-2-clad Fuel Specimens by Hot Water written by Elmer F. Stephan and published by . This book was released on 1959 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Summary of the Work Associated with the Solution and Understanding of Stringer-type Corrosion in Zircaloy-2 and -3 by : J. G. Goodwin
Download or read book A Summary of the Work Associated with the Solution and Understanding of Stringer-type Corrosion in Zircaloy-2 and -3 written by J. G. Goodwin and published by . This book was released on 1959 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Recovery and Recrystallization of Zirconium and Its Alloys by : Spencer Harrison Bush
Download or read book Recovery and Recrystallization of Zirconium and Its Alloys written by Spencer Harrison Bush and published by . This book was released on 1961 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Corrosion of the Zircaloy-2 - Niobium Couple by : R. E. Campagnoni
Download or read book Corrosion of the Zircaloy-2 - Niobium Couple written by R. E. Campagnoni and published by . This book was released on 1960 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hydrogen Absorption in Zircaloy During Aqueous Corrosion by : E. Hillner
Download or read book Hydrogen Absorption in Zircaloy During Aqueous Corrosion written by E. Hillner and published by . This book was released on 1964 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effect of Heat-treatment on the Corrosion of Zirconium-2 At.% Tin-2 At.% Niobium by : David Leslie Douglass
Download or read book Effect of Heat-treatment on the Corrosion of Zirconium-2 At.% Tin-2 At.% Niobium written by David Leslie Douglass and published by . This book was released on 1960 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Observations on the Corrosion of Zircaloy-2, Containing Palladium and Gold by :
Download or read book Observations on the Corrosion of Zircaloy-2, Containing Palladium and Gold written by and published by . This book was released on 1962 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: At the present time, zircaloy-2 is considered to be the most attractive material available for use as fuel sheathing and pressure tubing in water-cooled natural uranium nuclear reactors. However, to keep up with reactor design, considerable work is being done to develop zirconium alloys with greater strength than zircaloy-2 and with as good or better corrosion resistance. This report describes the effect of additions of 0.062 wt % Pd and 0.106 wt % Au on the corrosion resistance of zircaloy-2 in steam at 400C (750F) and 1500 psi.
Book Synopsis Zircaloy-2 Lined Zirconium Barrier Fuel Cladding by : CD. Williams
Download or read book Zircaloy-2 Lined Zirconium Barrier Fuel Cladding written by CD. Williams and published by . This book was released on 1996 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: The introduction of Zr-lined "barrier" fuel clad tubing by GE in the early 1980s to counter the pellet-clad interaction (PCI) failure mechanism in fuel for boiling water reactors provided a major improvement in fuel reliability and operational flexibility. While the frequency of fuel failures has been substantially reduced in the past decade, an increased tendency has been observed for failed fuel rods to exhibit post-failure degradation in the form of longer cracks that allow release of radioactive off-gas and contamination of the reactor coolant circuit with tramp fuel material. One factor involved in this degradation is hydriding of the cladding at a location remote from the initial perforation of the fuel rod. This local hydriding can lead to secondary crack initiation in the cladding when stressed by the fuel expansion accompanying a power increase.
