Download Mechanical Metallurgy of Nuclear Materials Ebook PDF

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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.

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.

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.

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.

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.

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

The Book Has Been Designed To Cover All Relevant Topics In B.E. (Mechanical/Metallurgy / Material Science / Production Engineering), M.Sc. (Material Science), B.Sc. (Honours), M.Sc. (Physics), M.Sc. (Chemistry), Amie And Diploma Students. Students Appearing For Gate, Upsc, Net, Slet And Other Entrance Examinations Will Also Find Book Quite Useful.In Nineteen Chapters, The Book Deals With Atomic Structure, The Structure Of Solids; Crystal Defects; Chemical Bonding; Diffusion In Solids; Mechanical Properties And Tests Of Materials; Alloys, Phase Diagrams And Phase Transformations; Heat Treatment; Deformation Of Materials; Oxidation And Corrosion; Electric, Magnetic, Thermal And Optical Properties; Semiconductors; Superconductivity; Organic Materials; Composites; And Nanostructured Materials.Special Features: * Fundamental Principles And Applications Are Discussed With Explanatory Diagrams In A Clear Way. * A Full Coverage Of Background Topics With Latest Development Is Provided. * Special Chapters On Nanostructured Materials, Superconductivity, Semiconductors, Polymers, Composites, Organic Materials Are Given . * Solved Problems, Review Questions, Problems, Short-Question Answers And Typical Objective Type Questions Alongwith Suggested Readings Are Given With Each Chapter.

Identifies non-government facilities active in commercial research, including development of products and processes. Arrangement is alphabetic, geographic, and by concept classification.

This is the fourteenth volume in the series of Memorial Tributes compiled by the National Academy of Engineering as a personal remembrance of the lives and outstanding achievements of its members and foreign associates. These volumes are intended to stand as an enduring record of the many contributions of engineers and engineering to the benefit of humankind. In most cases, the authors of the tributes are contemporaries or colleagues who had personal knowledge of the interests and the engineering accomplishments of the deceased.

The First Conference on materials science and engineering, including physics, physical chemistry, condensed matter chemistry, and technology in general, was held in September 1995, in Herceg Novi. An initiative to establish Yugoslav Materials Research Society was born at the conference and, similar to other MR societies in the world, the programme was made and objectives determined. The Yugoslav Materials Research Society (Yu-MRS), a nongovernment and non-profit scientific association, was founded in 1997 to promote multidisciplinary goal-oriented research in materials science and engineering. The main task and objective of the Society has been to encourage creativity in materials research and engineering to reach a harmonic coordination between achievements in this field in our country and analogous activities in the world with an aim to include our country into global international projects. Until 2003, Conferences were held every second year and then they grew into Annual Conferences that were traditionally held in Herceg Novi in September of every year. In 2007 Yu-MRS formed two new MRS: MRS-Serbia (official successor of Yu-MRS) and MRS-Montenegro (in founding). In 2008, MRS тАУ Serbia became a member of FEMS (Federation of European Materials Societies).