Download or read book Mechanical Properties of Zirconium written by F. D. Rosi and published by . This book was released on 1952 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanical Properties of Zirconium and Its Alloys written by Department of Metal Physics, Charles University and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components written by Manfred P. Puls and published by Springer Science & Business Media. This book was released on 2012-08-04 with total page 475 pages. Available in PDF, EPUB and Kindle. Book excerpt: By drawing together the current theoretical and experimental understanding of the phenomena of delayed hydride cracking (DHC) in zirconium alloys, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking provides a detailed explanation focusing on the properties of hydrogen and hydrides in these alloys. Whilst the emphasis lies on zirconium alloys, the combination of both the empirical and mechanistic approaches creates a solid understanding that can also be applied to other hydride forming metals. This up-to-date reference focuses on documented research surrounding DHC, including current methodologies for design and assessment of the results of periodic in-service inspections of pressure tubes in nuclear reactors. Emphasis is placed on showing how our understanding of DHC is supported by progress in general understanding of such broad fields as the study of hysteresis associated with first order phase transformations, phase relationships in coherent crystalline metallic solids, the physics of point and line defects, diffusion of substitutional and interstitial atoms in crystalline solids, and continuum fracture and solid mechanics. Furthermore, an account of current methodologies is given illustrating how such understanding of hydrogen, hydrides and DHC in zirconium alloys underpins these methodologies for assessments of real life cases in the Canadian nuclear industry. The all-encompassing approach makes The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Component: Delayed Hydride Cracking an ideal reference source for students, researchers and industry professionals alike.

Download or read book Applications Related Phenomena in Zirconium and Its Alloys written by Committee B-10 Staff and published by ASTM International. This book was released on 1969 with total page 393 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanical properties of zirconium and its alloys written by J. Čadek and published by . This book was released on 1981 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in Nuclear Applications written by J. H. Schemel and published by ASTM International. This book was released on 1974 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 428 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effect of Hydrogen on Mechanical Properties of Zirconium and Its Tin Alloys written by G. T. Muehlenkamp and published by . This book was released on 1953 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Comprehensive Nuclear Materials written by Todd R Allen and published by Elsevier. This book was released on 2011-05-12 with total page 3552 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants

Download or read book The Mechanical Properties of Consumable arc Melted Kroll process Zirconium written by R. G. Nelson and published by . This book was released on 1954 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanical Properties of Zirconium Alloys and Zirconium Hydrides Predicted from Density Functional Perturbation Theory written by and published by . This book was released on 2015 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Here, the elastic properties and mechanical stability of zirconium alloys and zirconium hydrides have been investigated within the framework of density functional perturbation theory. Results show that the lowest-energy cubic Pn-3m with combining macron]m polymorph of [delta]-ZrH1.5 does not satisfy all the Born requirements for mechanical stability, unlike its nearly degenerate tetragonal P42/mcm polymorph. Elastic moduli predicted with the Voigt-Reuss-Hill approximations suggest that mechanical stability of [alpha]-Zr, Zr-alloy and Zr-hydride polycrystalline aggregates is limited by the shear modulus. According to both Pugh's and Poisson's ratios, [alpha]-Zr, Zr-alloy and Zr-hydride polycrystalline aggregates can be considered ductile. The Debye temperatures predicted for [gamma]-ZrH, [delta]-ZrH1.5 and [epsilon]-ZrH2 are [theta]D = 299.7, 415.6 and 356.9 K, respectively, while [theta]D = 273.6, 284.2, 264.1 and 257.1 K for the [alpha]-Zr, Zry-4, ZIRLO and M5 matrices, i.e. suggesting that Zry-4 possesses the highest micro-hardness among Zr matrices.

Download or read book Mechanical Properties of Ternary Zirconium Alloys written by A. D. Schwope and published by . This book was released on 1955 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book High strength Zirconium Alloys written by R. K. Wagner and published by . This book was released on 1959 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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:

Download or read book The Metallurgy of Zirconium written by Benjamin Lustman and published by . This book was released on 2013-05 with total page 794 pages. Available in PDF, EPUB and Kindle. Book excerpt: Contributing Authors Include H. Etherington, R. C. Dalzell, D. W. Lillie And Others.

Download or read book The Heat Treatment Transformation Reactions and Mechanical Properties of Some High strength Zirconium base Alloys written by and published by . This book was released on 1956 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Transformation Reactions and Mechanical Properties of Zirconium Alloys Containing Copper and Molybdenum written by and published by . This book was released on 1960 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: At the present time, zircaloy is generally considered to be the most attractive material available for water-cooled power reactor fuel cladding and core components such as pressure tubes, but projected power reactor designs already require a better material having improved mechanical properties and corrosion resistance at the higher operating temperatures contemplated. As part of the Canadian program directed toward natural uranium fuelled power reactor development, a study of zirconium-based alloys containing between 1 and 2 wt% copper, combined with from 1.5 to 2.5 wt% molybdenum was made. In this investigation, the effects of solution and ageing heat treatments were examined in metallographic structure and resulting room temperature mechanical properties. An assessment of hot working fabrication characteristics was also made.