Author: Richard E. SchreiberPublisher:
ISBN:
Category : Stainless steel
Languages : en
Pages : 112
Book Description
Mechanical Properties of Irradiated Stainless Steels
Author: Richard E. SchreiberPublisher:
ISBN:
Category : Stainless steel
Languages : en
Pages : 112
Book Description
Mechanical Properties of Irradiated Welds in Stainless Steel
Author: J. Walter JosephPublisher:
ISBN:
Category : Stainless steel
Languages : en
Pages : 16
Book Description
Fundamentals of Radiation Materials Science
Author: GARY S. WASPublisher: Springer
ISBN: 1493934384
Category : Technology & Engineering
Languages : en
Pages : 1014
Book Description
The revised second edition of this established text offers readers a significantly expanded introduction to the effects of radiation on metals and alloys. It describes the various processes that occur when energetic particles strike a solid, inducing changes to the physical and mechanical properties of the material. Specifically it covers particle interaction with the metals and alloys used in nuclear reactor cores and hence subject to intense radiation fields. It describes the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys. Updated throughout, some major enhancements for the new edition include improved treatment of low- and intermediate-energy elastic collisions and stopping power, expanded sections on molecular dynamics and kinetic Monte Carlo methodologies describing collision cascade evolution, new treatment of the multi-frequency model of diffusion, numerous examples of RIS in austenitic and ferritic-martensitic alloys, expanded treatment of in-cascade defect clustering, cluster evolution, and cluster mobility, new discussion of void behavior near grain boundaries, a new section on ion beam assisted deposition, and reorganization of hardening, creep and fracture of irradiated materials (Chaps 12-14) to provide a smoother and more integrated transition between the topics. The book also contains two new chapters. Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking. Chapter 16 extends this treatment and considers the effects of irradiation on corrosion and environmentally assisted corrosion, including the effects of irradiation on water chemistry and the mechanisms of irradiation-induced stress corrosion cracking. The book maintains the previous style, concepts are developed systematically and quantitatively, supported by worked examples, references for further reading and end-of-chapter problem sets. Aimed primarily at students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals. Reviews of the first edition: "...nomenclature, problems and separate bibliography at the end of each chapter allow to the reader to reach a straightforward understanding of the subject, part by part. ... this book is very pleasant to read, well documented and can be seen as a very good introduction to the effects of irradiation on matter, or as a good references compilation for experimented readers." - Pauly Nicolas, Physicalia Magazine, Vol. 30 (1), 2008 “The text provides enough fundamental material to explain the science and theory behind radiation effects in solids, but is also written at a high enough level to be useful for professional scientists. Its organization suits a graduate level materials or nuclear science course... the text was written by a noted expert and active researcher in the field of radiation effects in metals, the selection and organization of the material is excellent... may well become a necessary reference for graduate students and researchers in radiation materials science.” - L.M. Dougherty, 07/11/2008, JOM, the Member Journal of The Minerals, Metals and Materials Society.
Zirconium in the Nuclear Industry
Author: Craig M. EuckenPublisher: ASTM International
ISBN: 080311463X
Category : Nuclear fuel claddings
Languages : en
Pages : 794
Book Description
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
Influence of Radiation on Material Properties
Author: F. A. GarnerPublisher: ASTM International
ISBN: 0803109636
Category : Building materials
Languages : en
Pages : 806
Book Description
Welding the Inconel 718 Superalloy
Author: S.G.K. ManikandanPublisher: Elsevier
ISBN: 0128181834
Category : Technology & Engineering
Languages : en
Pages : 326
Book Description
Welding the Inconel 718 Superalloy: Reduction of Micro-segregation and Laves Phases explores the day-to-day welding business in Alloy 718 and presents solutions to avoid or minimize micro-segregation. It considers the limitations of changing from lab scale models to actual production models and presents new technologies with proven experimental background. Various case studies are presented within the text, as well as proposed solutions backed by experimental evidence. Items previewed in this edition include enhanced cooling rates in the GTA welding process with cryogenic cooling and enhanced dendrite refinement using modified pulse waveform. This work will be useful to researchers from the aerospace, space, power generation, nuclear, and chemical industries, as well as students interested in superalloys and welding. - Resolves the industrial limitations in reducing the formation of laves phases in the welding of alloy 718 - Presents case studies in industrial applications - Discusses new technologies with proven experimental background - Includes a comparison of laves size and distribution between GTAW, EBW, LBW and FW
Manufacturing and Application of Stainless Steels
Author: Andrea Di SchinoPublisher: MDPI
ISBN: 3039286501
Category : Technology & Engineering
Languages : en
Pages : 260
Book Description
Stainless steels represent a quite interesting material family, both from a scientific and commercial point of view, following to their excellent combination in terms of strength and ductility together with corrosion resistance. Thanks to such properties, stainless steels have been indispensable for the technological progress during the last century and their annual consumption increased faster than other materials. They find application in all these fields requiring good corrosion resistance together with ability to be worked into complex geometries. Despite to their diffusion as a consolidated materials, many research fields are active regarding the possibility to increase stainless steels mechanical properties and corrosion resistance by grain refinement or by alloying by interstitial elements. At the same time innovations are coming from the manufacturing process of such a family of materials, also including the possibility to manufacture them starting from metals powder for 3D printing. The Special Issue scope embraces interdisciplinary work covering physical metallurgy and processes, reporting about experimental and theoretical progress concerning microstructural evolution during processing, microstructure-properties relations, applications including automotive, energy and structural.
Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys
Author: Structural Materials for Generation IV Nuclear Reactors
Author: Pascal YvonPublisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686
Book Description
Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area
Author: