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Book Corrosion Behavior of Zircaloy 4 Cladding Material

Download or read book Corrosion Behavior of Zircaloy 4 Cladding Material written by M. Blat and published by . This book was released on 1997 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Oxidation of Zirconium and Zirconium Alloys

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.

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 Corrosion Protection and Control Using Nanomaterials

Download or read book Corrosion Protection and Control Using Nanomaterials written by V S Saji and published by Elsevier. This book was released on 2012-02-21 with total page 421 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion is an expensive and potentially dangerous problem in many industries. The potential application of different nanostructured materials in corrosion protection, prevention and control is a subject of increasing interest. Corrosion protection and control using nanomaterials explores the potential use of nanotechnology in corrosion control.The book is divided into two parts. Part one looks at the fundamentals of corrosion behaviour and the manufacture of nanocrystalline materials. Chapters discuss the impact of nanotechnology in reducing corrosion cost, and investigate the influence of various factors including thermodynamics, kinetics and grain size on the corrosion behaviour of nanocrystalline materials. There are also chapters on electrodeposition and the corrosion behaviour of electrodeposited nanocrystalline materials. Part two provides a series of case studies of applications of nanomaterials in corrosion control. Chapters review oxidation protection using nanocrystalline structures at various temperatures, sol- gel and self-healing nanocoatings and the use of nanoreservoirs and polymer nanocomposites in corrosion control.With its distinguished editors and international team of expert contributors, Corrosion protection and control using nanomaterials is an invaluable reference tool for researchers and engineers working with nanomaterials in a variety of industries including, aerospace, automotive and chemical engineering as well as academics studying the unique protection and control offered by nanomaterials against corrosion. - Explores the potential use of nanotechnology and nanomaterials for corrosion prevention, protection and control - Discusses the impact of nanotechnology in reducing corrosion cost and investigates various factors on the corrosion behaviour of nanocrystalline materials - Provides a series of case studies and applications of nanomaterials for corrosion control

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 Leo F. P. Van Swam and published by ASTM International. This book was released on 1989 with total page 781 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 Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRs

Download or read book Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRs written by P. Beslu and published by . This book was released on 1989 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Out-of-pile corrosion experiments form a part of the program implemented to progress in understanding power water reactor (PWR) fuel rod waterside corrosion. Thus, out-of-pile loop tests were performed in order to correlate the thermal/hydraulic and chemical environment of the fuel rods to the corrosion rates of the Zircaloy-4 cladding material. Comparison of corrosion data yielded by in-loop, PWR, and autoclave tests then made it possible to demonstrate the effects of heat flux on corrosion kinetics through the temperature gradient in the oxide layer. PWR corrosion data also showed that the activation energy corresponding to Zircaloy oxidation by water does not vary under neutron flux compared to out-of-pile conditions. The influence of irradiation is either a threshold phenomenon dependent on fast neutron flux or a factor related to the chemical environment (for example, inclusion of lithium by recoil effect caused by thermal neutrons). Different destructive examination techniques to characterize the zirconium oxide morphology and (Li/K) concentration profile in the oxide have allowed us to suggest a relationship between operating conditions, such as two-phase flow heat transfer, lithium hydroxide/potassium hydroxide (LiOH/KOH) levels at the metal-coolant interface, and the kinetics of the growing oxide film. Then, the corrosion model makes the following calculations possible: (1) the precise thermal/hydraulic conditions in the environment of the fuel rods in the core of a PWR; (2) the localized coolant pH and overconcentration of soluble species in the coolant under boiling regime and its influence on the waterside corrosion of the Zircaloy cladding; (3) the contribution of irradiation flux to the enhancement of the oxidation rate, and (4) the axial and azimuthal oxide thicknesses on fuel rods. Simultaneously, a study has consisted in correlating the behavior of the Zircaloy materials under different autoclave experiments, out-of-pile tests, and in-reactor conditions. The future objective is to include the metallurgical properties in the corrosion model.

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 2000 with total page 953 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 Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 852 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Reactor Materials

Download or read book Reactor Materials written by and published by . This book was released on 1968 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Reactor Core Materials

Download or read book Reactor Core Materials written by and published by . This book was released on 1964 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Corrosion Characteristics  Mechanisms and Control Methods of Candidate Alloys in Sub  and Supercritical Water

Download or read book Corrosion Characteristics Mechanisms and Control Methods of Candidate Alloys in Sub and Supercritical Water written by Donghai Xu and published by Springer Nature. This book was released on 2021-12-07 with total page 248 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book aims to provide comprehensive and systematic introduction and summary of corrosion characteristics, mechanisms, and control methods of candidate alloys in sub- and supercritical water environment. First of all, corrosion types of candidate alloys and the effects of major alloying elements on corrosion resistance of potential alloys in sub- and supercritical water are compared and analyzed. At the same time, research status of candidate materials, and development and application trends of several corrosion-resistant alloys are summarized. Then, corrosion characteristics of Ni-Cr, Ni-Cr-Mo, Ni-Fe-Cr and Ni-Fe-Cr-Mo-Cu corrosion-resistant alloys, FeCrAl alloy, and Zircaloy are discussed in detail, including the corrosion rate, the structure and composition of oxide film, and the effects of various surface treatment processes, etc. More specifically, it also investigates corrosion behavior of Ni-based alloy, Fe-Ni-based, and stainless steels in supercritical water. The effects of aggressive species on the corrosion behavior of Ni-base alloys are also explored in supercritical water. Readers will further discover the total corrosion processes and mechanisms of typical candidate alloys in sub- and supercritical water environment. Finally, the work explores the corrosion control methods such as ceramic coatings and passivation processes in supercritical water oxidation and in subcritical water, respectively. Future challenges and development trends of corrosion research of candidate materials in sub- and supercritical water environments are covered at the end of this book. It offers valuable reference for theoretically guiding material selection and design and operating parameter optimization of key equipment in the sub- and supercritical water technologies. The book is written for senior undergraduates, graduate students, scholars, and researchers who are interested in corrosion behavior of candidate materials of supercritical water oxidation system, supercritical water gasification system, and nuclear reactor.

Book Comprehensive Nuclear Materials

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Book Oxidation and the Testing of Turbine Oils

Download or read book Oxidation and the Testing of Turbine Oils written by Cyril A. Migdal and published by ASTM International. This book was released on 2008 with total page 929 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work presents papers from a December 2005 symposium held in Norfolk, Virginia, and sponsored by ASTM Committee D2 on Petroleum Products and Lubricants and its Subcommittees D02.09 on Oxidation and D02.C0 on Turbine Oils. Contributors include equipment manufacturers, end users, lubricant producers, lubricant additive suppliers, test equipment manufacturers, and standard test method developers. They share information on industry trends, evolving technologies, and changing equipment designs and operating conditions, with a focus on how these factors impact oxidation. Some topics covered include turbine oil performance limits, a new form of the rotating pressure vessel oxidation test, and degradation mechanisms leading to sludge and varnish in modern turbine oil formulations. B&w photos are included. There is no subject index. Migdal is affiliated with Chemtura Corporation.