Mechanical Metallurgy of Nuclear Materials

Mechanical Metallurgy of Nuclear Materials
Author: Korukonda L. Murty,Nilesh Kumar,Abdullah Alomari
Publsiher: Elsevier
Total Pages: 248
Release: 2023-01-15
ISBN 10: 9780128161869
ISBN 13: 0128161868
Language: EN, FR, DE, ES & NL

Mechanical Metallurgy of Nuclear Materials Book Review:

Mechanical Metallurgy of Nuclear Materials is a review of the mechanical metallurgy of metallic materials primarily in thermal and irradiation conditions and discusses the latest developments on this frontier. The contents contained in the book draws heavily upon the author's own research conducted over the past four decades on various metallic materials, as well as including the current research in the field. In the last six decades, materials for nuclear energy applications have seen unprecedented growth. We have come a long way in understanding alloy design and development that are resistant to aging and degradation effected by thermal, mechanical, environmental, and radiation boundary conditions. This book will detail the mechanical aspects of nuclear materials, including t materials processing, mechanical and fracture properties, and modelling and simulation of mechanical properties. It will conclude with a discussion of plant life management and extension. Provides an extensive evaluation of the mechanical behavior of nuclear materials under different service conditions in a nuclear reactor Includes a discussion of issues and challenges for materials in the past, present, and future for use in nuclear reactors Covers advances in materials for generation IV nuclear reactors

An Introduction to Nuclear Materials

An Introduction to Nuclear Materials
Author: K. Linga Murty,Indrajit Charit
Publsiher: John Wiley & Sons
Total Pages: 400
Release: 2013-08-05
ISBN 10: 3527677100
ISBN 13: 9783527677108
Language: EN, FR, DE, ES & NL

An Introduction to Nuclear Materials Book Review:

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
Publsiher: John Wiley & Sons
Total Pages: 400
Release: 2013-01-29
ISBN 10: 3527407677
ISBN 13: 9783527407675
Language: EN, FR, DE, ES & NL

An Introduction to Nuclear Materials Book Review:

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.

The Metallurgy of Nuclear Fuel

The Metallurgy of Nuclear Fuel
Author: V. S. Yemel'Yanov,A. I. Yevstyukhin
Publsiher: Elsevier
Total Pages: 560
Release: 2013-10-22
ISBN 10: 1483186024
ISBN 13: 9781483186023
Language: EN, FR, DE, ES & NL

The Metallurgy of Nuclear Fuel Book Review:

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.

Nuclear Science Abstracts

Nuclear Science Abstracts
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1975
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015026173891
Language: EN, FR, DE, ES & NL

Nuclear Science Abstracts Book Review:

Physical and Mechanical Metallurgy Studies on Delta Stabilized Plutonium gallium Alloys

Physical and Mechanical Metallurgy Studies on Delta Stabilized Plutonium gallium Alloys
Author: H. R. Gardner
Publsiher: Unknown
Total Pages: 74
Release: 1965
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015086509539
Language: EN, FR, DE, ES & NL

Physical and Mechanical Metallurgy Studies on Delta Stabilized Plutonium gallium Alloys Book Review:

Nuclear Science Abstracts

Nuclear Science Abstracts
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1969-03
ISBN 10: 1928374650XXX
ISBN 13: PSU:000047759299
Language: EN, FR, DE, ES & NL

Nuclear Science Abstracts Book Review:

Accredited Postsecondary Institutions and Programs

Accredited Postsecondary Institutions and Programs
Author: Anonim
Publsiher: Unknown
Total Pages: 220
Release: 2022
ISBN 10: 1928374650XXX
ISBN 13: WISC:89109307769
Language: EN, FR, DE, ES & NL

Accredited Postsecondary Institutions and Programs Book Review:

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications
Author: Anonim
Publsiher: Unknown
Total Pages: 216
Release: 2014
ISBN 10: 1928374650XXX
ISBN 13: OCLC:965188377
Language: EN, FR, DE, ES & NL

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications Book Review:

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.

A Directory of Information Resources in the United States Physical Sciences Engineering

A Directory of Information Resources in the United States  Physical Sciences  Engineering
Author: National Referral Center (U.S.)
Publsiher: Unknown
Total Pages: 803
Release: 1971
ISBN 10: 1928374650XXX
ISBN 13: UIUC:30112104132508
Language: EN, FR, DE, ES & NL

A Directory of Information Resources in the United States Physical Sciences Engineering Book Review:

Physics and Technology of Nuclear Materials

Physics and Technology of Nuclear Materials
Author: Ioan Ursu
Publsiher: Elsevier
Total Pages: 540
Release: 2015-08-03
ISBN 10: 1483150577
ISBN 13: 9781483150574
Language: EN, FR, DE, ES & NL

Physics and Technology of Nuclear Materials Book Review:

Physics and Technology of Nuclear Materials presents basic information regarding the structure, properties, processing methods, and response to irradiation of the key materials that fission and fusion nuclear reactors have to rely upon. Organized into 12 chapters, this book begins with selectively several fundamentals of nuclear physics. Subsequent chapters focus on the nuclear materials science; nuclear fuel; structural materials; moderator materials employed to ""slow down"" fission neutrons; and neutron highly absorbent materials that serve in reactor's power control. Other chapters explore the cooling agents; fluids carrying the energy to its final stage of conversion into electric power; thermal and biological shielding materials; some outstanding reactor components; and irradiated fuel reprocessing. The last two chapters deal with nuclear material quality inspection by destructive and non-destructive methods, and specific materials envisaged for use in future thermonuclear reactors. This monograph will be helpful for a wide range of specialists wishing to gear their research and development, education, and other activities toward the field of nuclear power and nuclear technology.

The Directory of Consultants in Robotics and Mechanics

The Directory of Consultants in Robotics and Mechanics
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1985
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015026556194
Language: EN, FR, DE, ES & NL

The Directory of Consultants in Robotics and Mechanics Book Review:

Nuclear News

Nuclear News
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1978
ISBN 10: 1928374650XXX
ISBN 13: CHI:37785067
Language: EN, FR, DE, ES & NL

Nuclear News Book Review:

Graduate Programs in Engineering Applied Sciences 2011 Grad 5

Graduate Programs in Engineering   Applied Sciences 2011  Grad 5
Author: Peterson's
Publsiher: Peterson's
Total Pages: 602
Release: 2011-05-01
ISBN 10: 076893091X
ISBN 13: 9780768930917
Language: EN, FR, DE, ES & NL

Graduate Programs in Engineering Applied Sciences 2011 Grad 5 Book Review:

Peterson's Graduate Programs in Engineering & Applied Sciences contains a wealth of information on colleges and universities that offer graduate degrees in the fields of Aerospace/Aeronautical Engineering; Agricultural Engineering & Bioengineering; Architectural Engineering, Biomedical Engineering & Biotechnology; Chemical Engineering; Civil & Environmental Engineering; Computer Science & Information Technology; Electrical & Computer Engineering; Energy & Power engineering; Engineering Design; Engineering Physics; Geological, Mineral/Mining, and Petroleum Engineering; Industrial Engineering; Management of Engineering & Technology; Materials Sciences & Engineering; Mechanical Engineering & Mechanics; Ocean Engineering; Paper & Textile Engineering; and Telecommunications. Up-to-date data, collected through Peterson's Annual Survey of Graduate and Professional Institutions, provides valuable information on degree offerings, professional accreditation, jointly offered degrees, part-time and evening/weekend programs, postbaccalaureate distance degrees, faculty, students, degree requirements, entrance requirements, expenses, financial support, faculty research, and unit head and application contact information. As an added bonus, readers will find a helpful "See Close-Up" link to in-depth program descriptions written by some of these institutions. These Close-Ups offer detailed information about the specific program or department, faculty members and their research, and links to the program Web site. In addition, there are valuable articles on financial assistance and support at the graduate level and the graduate admissions process, with special advice for international and minority students. Another article discusses important facts about accreditation and provides a current list of accrediting agencies.

Materials Engineering and Automatic Control III

Materials Engineering and Automatic Control III
Author: Shou Jun Wang
Publsiher: Trans Tech Publications Ltd
Total Pages: 1006
Release: 2014-06-25
ISBN 10: 3038265233
ISBN 13: 9783038265238
Language: EN, FR, DE, ES & NL

Materials Engineering and Automatic Control III Book Review:

Collection of selected, peer reviewed papers from the 3rd International Conference on Materials Engineering and Automatic Control (ICMEAC 2014), May 17-18, 2014, Tianjin, China. The 182 papers are grouped as follows: Chapter 1: Advanced Materials Engineering and Materials Processing Technologies, Chapter 2: Mechanical Engineering and Dynamics, Liquids and Gases Mechanics, Applied Mechanics in Technological Processes, Structural Design, Chapter 3: Instrumentation, Measurement and Testing Technologies, Analysis and Calculations Methodology, Chapter 4: Technologies of Power Systems, Energy and Thermal Engineering, Its Applications, Chapter 5: Mechatronics and Robotics, Chapter 6: Control Technologies, Automation and Simulation of Manufacturing, Chapter 7: Data Mining, Detection, Monitoring and Fault Diagnosis Technologies, Chapter 8: Networks and Information Technologies, Systems Design, Chapter 9: Product Design, Planning, Projects Management and Industrial Engineering

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications
Author: Michael Vasily Glazoff
Publsiher: Unknown
Total Pages: 187
Release: 2015
ISBN 10: 9781321738216
ISBN 13: 1321738218
Language: EN, FR, DE, ES & NL

Physical and Mechanical Metallurgy of Zirconium Alloys for Nuclear Applications Book Review:

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.

Who s who in Technology Today

Who s who in Technology Today
Author: Anonim
Publsiher: Unknown
Total Pages: 840
Release: 1982
ISBN 10: 1928374650XXX
ISBN 13: UCAL:B3942791
Language: EN, FR, DE, ES & NL

Who s who in Technology Today Book Review:

Effect of Nuclear Radiation at Cryogenic Temperatures on the Tensile Properties of Titanium and Titanium base Alloys

Effect of Nuclear Radiation at Cryogenic Temperatures on the Tensile Properties of Titanium and Titanium base Alloys
Author: Charles L. Younger,Fred A. Haley
Publsiher: Unknown
Total Pages: 51
Release: 1969
ISBN 10: 1928374650XXX
ISBN 13: UIUC:30112106779744
Language: EN, FR, DE, ES & NL

Effect of Nuclear Radiation at Cryogenic Temperatures on the Tensile Properties of Titanium and Titanium base Alloys Book Review:

Effects of reactor irradiation at cryogenic temperatures on tensile properties of titanium and titanium-base alloys.

Charpy Impact Test

Charpy Impact Test
Author: John M. Holt
Publsiher: ASTM International
Total Pages: 214
Release: 1990
ISBN 10: 0803112955
ISBN 13: 9780803112957
Language: EN, FR, DE, ES & NL

Charpy Impact Test Book Review:

Who s who in Technology Today Index

Who s who in Technology Today  Index
Author: Jan W. Churchwell
Publsiher: Primary Source Microfilm
Total Pages: 824
Release: 1982
ISBN 10: 1928374650XXX
ISBN 13: UCSC:32106021023673
Language: EN, FR, DE, ES & NL

Who s who in Technology Today Index Book Review:

Directory of leading scientists and engineers who are the leaders in the most important areas of American technology. Each entry gives education, publications, achievements, area of expertise, honors, patents, and personal information.