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Book Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors During Service

Download or read book Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors During Service written by PCK Chow and published by . This book was released on 1994 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: X-ray diffraction (XRD) and analytical electron microscopy (AEM) have been used to characterise microstructural and microchemical changes produced by neutron irradiation of Zr-2.5Nb, Zircaloy-2 and Zircaloy-4 nuclear reactor core components.

Book Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors During Service

Download or read book Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors During Service written by Griffiths, M and published by Pinawa, Man. : Whiteshell Laboratories. This book was released on 1993 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Microstructure Evolution in Zr Alloys During Irradiation

Download or read book Microstructure Evolution in Zr Alloys During Irradiation written by M. Griffiths and published by . This book was released on 2010 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The performance of zirconium alloys in BWR, PWR, and PHWR nuclear reactors is dependent on the microstructure. Accordingly, the characterization of the microstructure is an integral part of any study conducted to develop models for in-reactor performance. Although the as-fabricated microstructure (texture, grain size, dislocation density, and phase or precipitate distribution) determines the basic physical properties of a given component, there are changes that occur during irradiation that can have a significant effect on these properties. Microstructures that illustrate specific features of the radiation damage that forms in Zr alloys will be illustrated and discussed in terms of the dose, dose rate, and impurity factors that are applicable. The original paper was published by ASTM International in the Journal of ASTM International, December 2007.

Book Structural Alloys for Nuclear Energy Applications

Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Book Evolution of microstructure in zirconium alloys during irradiation

Download or read book Evolution of microstructure in zirconium alloys during irradiation written by M. Griffiths and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Zirconium in the Nuclear Industry

Download or read book Zirconium in the Nuclear Industry written by Craig M. Eucken and published by ASTM International. This book was released on 1991 with total page 794 pages. Available in PDF, EPUB and Kindle. Book excerpt: The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr

Book Zirconium in the Nuclear Industry

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:

Book Zirconium in the Nuclear Industry

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.

Book Evolution of Microstructure in Zirconium Alloys During Irradiation

Download or read book Evolution of Microstructure in Zirconium Alloys During Irradiation written by M. Griffiths and published by . This book was released on 1996 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: X-ray diffraction (XRD) and transmission electron microscopy (TEM) have been used to characterize microstructural and microchemical changes produced by neutron irradiation in zirconium and zirconium alloys. Zircaloy-2, Zircaloy-4, and Zr-2.5Nb alloys with differing metallurgical states have been analyzed after irradiation for neutron fluences up to 25 x 1025 n.m-2 (E > 1 MeV) for a range of temperatures between 330 and 580 K.

Book Deformation Mechanisms  Texture  and Anisotropy in Zirconium and Zircaloy

Download or read book Deformation Mechanisms Texture and Anisotropy in Zirconium and Zircaloy written by Erich Tenckhoff and published by ASTM International. This book was released on 1988 with total page 85 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Evolution of microstructure in zr alloys during irradiation

Download or read book Evolution of microstructure in zr alloys during irradiation written by M. Griffiths and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A review of microstructure evolution in zirconium alloys during irradiation

Download or read book A review of microstructure evolution in zirconium alloys during irradiation written by M. Griffiths and published by . This book was released on 1988 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Zirconium in the Nuclear Industry  Tenth International Symposium

Download or read book Zirconium in the Nuclear Industry Tenth International Symposium written by A. M. Garde and published by ASTM International. This book was released on 1994 with total page 805 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Modern Physical Metallurgy

Download or read book Modern Physical Metallurgy written by R. E. Smallman and published by Elsevier. This book was released on 2013-10-22 with total page 545 pages. Available in PDF, EPUB and Kindle. Book excerpt: Modern Physical Metallurgy, Fourth Edition explains the fundamental principles of physical metallurgy and their application, allowing its readers to understand the many important technological phenomena of the field. The book covers topics such as the molecular properties of metals; the different physical methods of metals and alloys; and the structure of alloys. Also covered are topics such as the deformation of metals and alloys; phase transformations; and related processes such as creep, fatigue, fracture, oxidation, and corrosion. The text is recommended for metallurgists, chemists, and engineers who would like to know more about the principles behind metallurgy and its application in different fields.

Book Irradiation Induced Growth and Microstructure Evolution of Zr 1 2Sn 1Nb 0 4Fe Under Neutron Irradiation to High Doses

Download or read book Irradiation Induced Growth and Microstructure Evolution of Zr 1 2Sn 1Nb 0 4Fe Under Neutron Irradiation to High Doses written by GP. Kobylyansky and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zirconium alloy components subjected to long-term operation and high doses in thermal reactors need to be highly irradiation resistant to provide integrity of components, primarily, their geometrical sizes. Transmission and scanning electron microscopy, energy dispersive X-ray microanalysis used to investigate thin foils and extraction replicas of irradiated zirconium, Zr-1Nb (E110) and Zr-1.2Sn-1Nb-0.4Fe (E635) alloys allowed us to analyze the evolution of their microstructure under neutron irradiation. The experimental irradiations that were conducted at 350°C to 1027 n/m2 (E >= 0.1 MeV) show that the most irradiation resistant alloy proved to be a multicomponent E635 alloy. It is not essentially subject to growth. Dislocation structure and phase composition were studied as interrelated to different stages of irradiation induced growth. The accelerated growth correlates with a high density of basal -- plane c-component dislocations.

Book Evolution of Microstructure and Nanoscale Chemistry of Zircaloy 2 Type Alloys During Nuclear Reactor Operation

Download or read book Evolution of Microstructure and Nanoscale Chemistry of Zircaloy 2 Type Alloys During Nuclear Reactor Operation written by Johan Eriksson (fysiker) and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: