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Author : T. L. Mackay
Publisher :
ISBN 13 :
Total Pages : 26 pages
Book Rating : 4.3/5 (91 download)
Download or read book Oxidation of Zirconium and Zirconium Alloys in Liquid Sodium written by T. L. Mackay and published by . This book was released on 1962 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.3/5 (91 download)
Download or read book Oxidation of Zirconium and Zirconium Alloys written by and published by . This book was released on 1959 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Author :
Publisher :
ISBN 13 :
Total Pages : 302 pages
Book Rating : 4.3/5 (91 download)
Download or read book Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962 written by and published by . This book was released on 1962 with total page 302 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Oxidation of Zirconium and Zirconium Alloys written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Zirconium oxidation was investigaied in the temperature range 400 io 900 deg C at oxygen pressures of 50, 200, and 800 mm. The reaction rate of massive (parallelepiped) samples was best expressed by the cubic rate law. At an oxygen pressure of 200 mm the activation energy was calculated to be 42.7 kcal per mole, and the cubic rate constant in (mu g per sq cm) per minute can be expressed as k = (5.94 x 10/sup 16/)e/sup -42//sup,70//sup 0//sRs/sup T/. The oxidaiion rate was found to be relatively insensitive to various types of surface preparations in ihe 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. The oxidations of zirconium binary alloys containing nominally one, two, and four atom% additives of aluminum, beryllium, carbon, chromium, cobalt, copper, hafnium, iron, lead, molybdenum, nickel, niobium, platinum, silicon, tantalum, tin, titanium, tungsten, uranium, and vanadium were studied at 700 deg C and 200 mm oxygen. The alloys were grouped according to four types of oxidation behavior. Two groups consisted of alloys which oxidized according to the cubic rate law (Group I) or parabolic rate law (Group II) and did not exhibit breakaway phenomena. The other groups were alloys which initially oxidized according to the cubic rate law (Group III) or parabolic rate law (Group IV) but later exhibited breakaway oxidation phenomena. For alloys of those additives which are soluble in zirconium the initial oxidation rates are explained according to a valency effect in terms of the Wagner-Hauffe theory of alloy oxidation. For additives insoluble in zirconium, no single theory is felt to be adequate. The breakaway phenomena observed for many of the alloys is explained in terms of a 15% deviation of the additive ionic radius from the ionic radius of Zr/sup 4+/. Some x-ray and electron diffraction studies, which indicate that for zirconium and some of its alloys the breakaway occurs as a result of a polymorphic transformation in the zirconium dioxide film, were made. (auth).
Author : M. G. Cowgill
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book Oxidation of zirconium and zirconium alloys : quarterly report, February-June 1964 written by M. G. Cowgill and published by . This book was released on 1964 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : George P. Sabol
Publisher : ASTM International
ISBN 13 : 0803124996
Total Pages : 953 pages
Book Rating : 4.8/5 (31 download)
Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 2000 with total page 953 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : George Baker Adams
Publisher :
ISBN 13 :
Total Pages : 32 pages
Book Rating : 4.3/5 (91 download)
Download or read book The Anodic Oxidation of Some Dilute Binary Zirconium Alloys written by George Baker Adams and published by . This book was released on 1957 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. Paul Pemsler
Publisher :
ISBN 13 :
Total Pages : 26 pages
Book Rating : 4.3/5 (91 download)
Download or read book Corrosion of Zirconium Alloys in 900° Steam written by J. Paul Pemsler and published by . This book was released on 1958 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : David John Young
Publisher : Elsevier
ISBN 13 : 008044587X
Total Pages : 593 pages
Book Rating : 4.0/5 (84 download)
Download or read book High Temperature Oxidation and Corrosion of Metals written by David John Young and published by Elsevier. This book was released on 2008-10-03 with total page 593 pages. Available in PDF, EPUB and Kindle. Book excerpt: The book is concerned with understanding the fundamental mechanisms of high temperature alloy oxidation. It uses this understanding to develop methods of predicting oxidation rates and the way they change with temperature, gas chemistry and alloy composition. The focus is on designing (or selecting) alloy compositions which provide optimal resistance to attack by corrosive gases. . Emphasises quantitative calculations for predicting reaction rates and the effects of temperature, oxidant activities and alloy compositions. . Uses phase diagrams and diffusion paths to analyse and interpret scale structures and internal precipitation distributions . Provides a detailed examination of corrosion in industrial gases (water vapour effects, carburisation and metal dusting, sulphidation) . Text is well supported by numerous micrographs, phase diagrams and tabulations of relevant thermodynamic and kinetic data . Combines physical chemistry and materials science methodologies.
Author :
Publisher :
ISBN 13 :
Total Pages : 156 pages
Book Rating : 4.3/5 (91 download)
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:
Author : Atomic Energy of Canada Limited
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (562 download)
Download or read book On the Oxidation of Zirconium Alloys in Air and the Dimensional Changes Associated with Oxidation written by Atomic Energy of Canada Limited and published by . This book was released on 1969 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Boris Grigorevich Parfenov
Publisher :
ISBN 13 :
Total Pages : 200 pages
Book Rating : 4.:/5 (43 download)
Download or read book Corrosion of Zirconium and Zirconium Alloys written by Boris Grigorevich Parfenov and published by . This book was released on 1969 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. Paul Pemsler
Publisher :
ISBN 13 :
Total Pages : 28 pages
Book Rating : 4.3/5 (91 download)
Download or read book Corrosion of Zirconium Alloys in 900 and 1000° Steam written by J. Paul Pemsler and published by . This book was released on 1960 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Jordan Lee Vandegrift
Publisher :
ISBN 13 :
Total Pages : 122 pages
Book Rating : 4.:/5 (112 download)
Download or read book Oxidation Behavior of Zirconium Alloys in Transient Conditions written by Jordan Lee Vandegrift and published by . This book was released on 2019 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: "The effect of sample geometry, welding strategies, atmosphere, plastic deformation, and rapid heating on the oxidation behavior of zirconium alloys has been investigated in this work. The goal of this work was to determine which zirconium alloy would be best suited as nuclear fuel cladding material in the Transient Reactor Test (TREAT) facility at the Idaho National Laboratory (INL), which has unique operating conditions compared to typical reactors. TREAT is air-cooled, operates at high temperatures (400-600°C), and produces rapid transients (less than or equal to 700°C/s). Additionally, TREAT's cladding geometry is unique in that it has chamfers and welds. Alloying elements such as Fe, Sn, Cr, and Nb are typically added to zirconium and can drastically alter the corrosion properties of the material. The effects of such fabrication on the oxidation behavior of zirconium alloys is not well documented in literature and no direct comparison is provided for the alloys of interest, thus it is unclear how these alloys will behave under TREAT's conditions. Isothermal and non-isothermal oxidation studies were completed on pure Zr, Zircaloy-3 (Zry-3), Zircaloy-4 (Zry-4), Zr-1Nb, and Zr-2.5Nb plate specimens in both Ar+20%O2 and N2+20%O2 to study the effect of nitrogen on the oxidation behavior. Electron beam welded (EBW) and tungsten inert gas (TIG) welded Zry-3, Zry-4, and Zr-1Nb tube samples were oxidized under rapid heating and isothermal conditions in dry and humid N2+20%O2. Through these studies, the effect of chamfering, welding, humidity, and rapid heating were characterized. Macroscopic images of the samples were taken after oxidation, the oxide thickness was measured, and mass gain data was used to determine the oxidation rate constants and activation energies. It was found that Zry-3, Zry-4, and Zr-1Nb experience faster oxidation in N2+20%O2 than Ar+20%O2 at 800°C, while Zr and Zr-2.5Nb were relatively unaffected. Zry-3, Zry-4, and Zr-1Nb were found to experience accelerated oxidation in the weld region. Additionally, Zry-3 and Zry-4 experienced accelerated oxidation at the chamfers, while the chamfered region of Zr-1Nb experienced less oxidation. In all oxidation experiments, Zr-1Nb had the most favorable oxidation behavior."--Boise State University ScholarWorks.
Author : George P. Sabol
Publisher : ASTM International
ISBN 13 : 0803124066
Total Pages : 907 pages
Book Rating : 4.8/5 (31 download)
Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 1996 with total page 907 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. E. Westerman
Publisher :
ISBN 13 :
Total Pages : 88 pages
Book Rating : 4.3/5 (91 download)
Download or read book High Temperature Oxidation of Zirconium and Zircaloy-2 in Oxygen and Water Vapor written by R. E. Westerman and published by . This book was released on 1962 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Gerry D. Moan
Publisher : ASTM International
ISBN 13 : 0803128959
Total Pages : 891 pages
Book Rating : 4.8/5 (31 download)
Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
