June 18, 2021

Download Ebook Free Mechanical Metallurgy Of Nuclear Materials

An Introduction to Nuclear Materials

An Introduction to Nuclear Materials
Author : K. Linga Murty,Indrajit Charit
Publisher : John Wiley & Sons
Release Date : 2013-07-26
Category : Technology & Engineering
Total pages :398
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Covering both fundamental and advanced aspects in an accessible way, this textbook begins with an overview of nuclear reactor systems, helping readers to familiarize themselves with the varied designs. Then the readers are introduced to different possibilities for materials applications in the various sections of nuclear energy systems. Materials selection and life prediction methodologies for nuclear reactors are also presented in relation to creep, corrosion and other degradation mechanisms. An appendix compiles useful property data relevant for nuclear reactor applications. Throughout the book, there is a thorough coverage of various materials science principles, such as physical and mechanical metallurgy, defects and diffusion and radiation effects on materials, with serious efforts made to establish structure-property correlations wherever possible. With its emphasis on the latest developments and outstanding problems in the field, this is both a valuable introduction and a ready reference for beginners and experienced practitioners alike.

An Introduction to Nuclear Materials

An Introduction to Nuclear Materials
Author : K. Linga Murty,Indrajit Charit
Publisher : John Wiley & Sons
Release Date : 2013-01-29
Category : Technology & Engineering
Total pages :382
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Are you a visual learner? Do you prefer instructions that show you how to do something – and skip the long–winded explanations? If so, then this book is for you. Open it up and you′ll find clear, step–by–step screen shots that show you how to tackle more than 175 tasks involving HTML and CSS. Each task–based spread covers a single technique, sure to help you get up and running with HTML and CSS in no time. You′ll learn to: View HTML code in a browser Add and format text Prepare images for the Web Insert links to other pages Control layout with style sheets Add JavaScript to a Web page Helpful sidebars offer practical tips and tricks Succinct explanations walk you through step by step Full–color screen shots demonstrate each task Two–page lessons break big topics into bite–sized modules

Structural Alloys for Nuclear Energy Applications

Structural Alloys for Nuclear Energy Applications
Author : Robert Odette,Steven Zinkle
Publisher : Newnes
Release Date : 2019-08-15
Category : Technology & Engineering
Total pages :673
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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.

The Metallurgy of Nuclear Fuel

The Metallurgy of Nuclear Fuel
Author : V. S. Yemel'Yanov,A. I. Yevstyukhin
Publisher : Elsevier
Release Date : 2013-10-22
Category : Technology & Engineering
Total pages :560
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The Metallurgy of Nuclear Fuel: Properties and Principles of the Technology of Uranium, Thorium and Plutonium is a systematic analysis of the metallurgy of nuclear fuel, with emphasis on the physical, mechanical, and chemical properties as well as the technology of uranium, thorium, and plutonium, together with their alloys and compounds. The minerals and raw material sources of nuclear fuel are discussed, along with the principles of the technology of the raw material processing and the production of the principal compounds, and of the pure metals and alloys. Comprised of three parts, this volume begins with an introduction to the history of the discovery of uranium and its position in the periodic system; its use as a nuclear fuel; radioactivity and isotopic composition; alloys and compounds; and physical, mechanical, and chemical properties. The effect of mechanical and thermal treatment, thermal cycling and irradiation on the physicochemical properties of uranium is also examined. The next two sections are devoted to thorium and plutonium and includes chapters dealing with their uses, alloys and compounds, and methods of recovery and purification. This book is written for university students, but should also prove useful to young production engineers and scientific workers who are concerned with problems in the metallurgy of nuclear fuel.

Scientific and Technical Organizations and Agencies Directory

Scientific and Technical Organizations and Agencies Directory
Author : Margaret Labash Young
Publisher : Gale / Cengage Learning
Release Date : 1987
Category : Science
Total pages :1670
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Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications
Author : Anonim
Publisher : Unknown
Release Date : 2014
Category :
Total pages :216
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In the post-Fukushima world, the stability of materials under extreme conditions is an important issue for the safety of nuclear reactors. Because the nuclear industry is going to continue using advanced zirconium cladding materials in the foreseeable future, it become critical to gain fundamental understanding of the several interconnected problems. First, what are the thermodynamic and kinetic factors affecting the oxidation and hydrogen pick-up by these materials at normal, off-normal conditions, and in long-term storage? Secondly, what protective coatings (if any) could be used in order to gain extremely valuable time at off-normal conditions, e.g., when temperature exceeds the critical value of 2200°F? Thirdly, the kinetics of oxidation of such protective coating or braiding needs to be quantified. Lastly, even if some degree of success is achieved along this path, it is absolutely critical to have automated inspection algorithms allowing identifying defects of cladding as soon as possible. This work strives to explore these interconnected factors from the most advanced computational perspective, utilizing such modern techniques as first-principles atomistic simulations, computational thermodynamics of materials, diffusion modeling, and the morphological algorithms of image processing for defect identification. Consequently, it consists of the four parts dealing with these four problem areas preceded by the introduction and formulation of the studied problems. In the 1st part an effort was made to employ computational thermodynamics and ab initio calculations to shed light upon the different stages of oxidation of ziraloys (2 and 4), the role of microstructure optimization in increasing their thermal stability, and the process of hydrogen pick-up, both in normal working conditions and in long-term storage. The 2nd part deals with the need to understand the influence and respective roles of the two different plasticity mechanisms in Zr nuclear alloys: twinning (at low T) and crystallographic slip (higher T's). For that goal, a description of the advanced plasticity model is outlined featuring the non-associated flow rule in hcp materials including Zr. The 3rd part describes the kinetic theory of oxidation of the several materials considered to be perspective coating materials for Zr alloys: SiC and ZrSiO4. In the 4th part novel and advanced projectional algorithms for defect identification in zircaloy coatings are described. In so doing, the author capitalized on some 12 years of his applied industrial research in this area. Our conclusions and recommendations are presented in the 5th part of this work, along with the list of used literature and the scripts for atomistic, thermodynamic, kinetic, and morphological computations.

Mechanical Behavior of Materials

Mechanical Behavior of Materials
Author : Rajiv S. Mishra,Indrajit Charit
Publisher : Butterworth-Heinemann
Release Date : 2019-05-01
Category : Architecture
Total pages :480
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Mechanical Behavior of Materials: Deformation and Design is the first textbook to adopt a design-led approach to the teaching of mechanical behavior of materials in which the underlying fundamental science is presented in the context of design. This approach has been found to help motivate and engage students through real-life case studies and illustrative applications. The book also includes three ‘Guided Learning Units,’ which are essentially special self-teaching tutorials on certain difficult topics. In addition to the design-led approach, Mishra and Charit cover newer content not found in other textbooks, such as recent advances in microstructural characterization techniques and up-to-date presentation of fundamentals that link the microstructure of engineering materials with realistic mechanical response. Relates microstructural distribution in engineering materials to mechanical behavior and failure Presents ‘Guided Learning Units’ on strengthening mechanisms Discusses the deviation of engineering microstructure from ideal microstructure Contains examples of mechanical properties that are brought together under the basic microstructural framework Provides aspects of design-led and systems approaches to materials that are integrated in one book Includes an online solutions manual, image bank, and lecture slides that are available for instructors

Who's who in Technology Today

Who's who in Technology Today
Author : Anonim
Publisher : Unknown
Release Date : 1981
Category : Engineers
Total pages :129
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Peterson's Annual Guides to Graduate Study

Peterson's Annual Guides to Graduate Study
Author : Anonim
Publisher : Unknown
Release Date : 1982-12
Category : Engineering
Total pages :800
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Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications
Author : Michael Vasily Glazoff
Publisher : Unknown
Release Date : 2015
Category : Nuclear fuel claddings
Total pages :187
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In the post-Fukushima world, thermal and structural stability of materials under extreme conditions is an important issue for the safety of nuclear reactors. Because the nuclear industry will continue using zirconium (Zr) cladding for the foreseeable future, it becomes critical to gain a fundamental understanding of several interconnected problems. First, what are the thermodynamic and kinetic factors affecting oxidation and hydrogen pick-up by these materials at normal, off-normal conditions, and in long-term storage? Secondly, what protective coatings could be used in order to gain valuable time at off-normal conditions (temperature exceeds ~1200°C (2200°F)? Thirdly, the kinetics of the coating's oxidation must be understood. Lastly, one needs automated inspection algorithms allowing identifying cladding's defects. This work attempts to explore the problem from a computational perspective, utilizing first principles atomistic simulations, computational thermodynamics, plasticity theory, and morphological algorithms of image processing for defect identification. It consists of the four parts dealing with these four problem areas preceded by the introduction. In the 1st part, computational thermodynamics and ab initio calculations were used to shed light upon the different stages of zircaloy oxidation and hydrogen pickup, and microstructure optimization to increase thermal stability. The 2nd part describes the kinetic theory of oxidation of the several materials considered to be perspective coatings for Zr alloys: SiC and ZrSiO4. The 3rd part deals with understanding the respective roles of the two different plasticity mechanisms in Zr nuclear alloys: twinning (at low T) and crystallographic slip (higher T's). For that goal, an advanced plasticity model was proposed. In the 4th part projectional algorithms for defect identification in zircaloy coatings are described. Conclusions and recommendations are presented in the 5th part. This integrative approach's value is in developing multi-faceted understanding of complex processes taking place in nuclear fuel rods. It helped identify several problems pertaining to the safe operations with nuclear fuel: limits of temperature that should be strictly obeyed in storage to retard zircaloy hydriding; understanding the benefits and limitations of coatings; developing in-depth understanding of Zr plasticity; developing original algorithms for defect identification in SiC-braided zircaloy. The obtained results will be useful for the nuclear industry.

Nuclear News

Nuclear News
Author : Anonim
Publisher : Unknown
Release Date : 2008
Category : Nuclear energy
Total pages :129
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World Nuclear Directory

World Nuclear Directory
Author : Arthur Woods Haslett
Publisher : Unknown
Release Date : 1963
Category : Nuclear energy
Total pages :129
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Materials & Process Technology

Materials & Process Technology
Author : Anonim
Publisher : Unknown
Release Date : 1968
Category : Materials
Total pages :129
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Who's Who, Indian Personages

Who's Who, Indian Personages
Author : Purnendu Chavda,H. L. Sagar
Publisher : Unknown
Release Date : 1986
Category : Biography
Total pages :129
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Japanese Universities and Colleges

Japanese Universities and Colleges
Author : Anonim
Publisher : Unknown
Release Date : 1965
Category : Research
Total pages :129
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