J. V. Dunworth – författare
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9 produkter
9 produkter
E-bok
PDF, Engelska, 2016756 kr
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The Propagation of Gamma Quanta in Matter deals with various problems of the propagation and absorption of gamma quanta in matter, including the occurrence of multiple scattering of radiation. A general account of theoretical methods of solving problems of multiple scattering of quanta is presented, with emphasis on the results of solving such problems. This book consists of three chapters and begins with a discussion on the interaction of gamma radiation with matter; multiple scattering of gamma quanta; and the distribution function and quantities connected with it. The next chapter focuses on the theory of multiple scattering of gamma quanta and covers subjects such as the transport equation and its analytical solution; method of moments; method of random sampling; and method of successive collisions. The last chapter examines the propagation of radiation for various geometrical configurations of the sources and absorbing media, paying particular attention to a point source in a homogeneous medium and on the boundary of two media; unidirectional radiation in a homogeneous medium; reflexion of gamma radiation from the surface of a scattering medium; a plane isotropic source; and a thick radiating layer of an absorbing medium. This monograph will appeal to students as well as physicists and engineers engaged in shield design problems.
E-bok
PDF, Engelska, 2013756 kr
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The Theory of Neutron Slowing Down in Nuclear Reactors focuses on one facet of nuclear reactor design: the slowing down (or moderation) of neutrons from the high energies with which they are born in fission to the energies at which they are ultimately absorbed. In conjunction with the study of neutron moderation, calculations of reactor criticality are presented. A mathematical description of the slowing-down process is given, with particular emphasis on the problems encountered in the design of thermal reactors. This volume is comprised of four chapters and begins by considering the problems of neutron moderation and their importance in all types of reactors. An asymptotic reactor model is described, and the calculation of the elastic scattering frequency is explained. Subsequent chapters focus on the process of slowing down in finite and infinite medium by analyzing capture by individual resonances; resonance integrals in heterogeneous systems; the slowing-down kernels; the spherical harmonics method; statistical methods; and small source theory. The final chapter presents numerical solutions of the Boltzmann equation and covers topics such as the multigroup approach, group constants, and solution of the multigroup equations. This book will be a useful resource for nuclear physicists and engineers.
E-bok
PDF, Engelska, 2013763 kr
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Spectroscopy and Photochemistry of Uranyl Compounds is a guide to the research and physics of the actinide elements, particularly the uranyl ion. The book is introduced with the subject of the spectroscopy of uranyl salts in the solid state. Studies dealing with the fluorescence and absorption spectra of solid uranyl salts through band measurements and empirical classification, term analysis, and fluorescence spectrum in relation to excitation by light of various wavelengths are then discussed. The book also mentions the analysis of the uranyl spectrum by Dieke and co-workers, because of the precise measurements of the fluorescence and absorption bands obtained under the Manhattan project. The table determined by Pant and Sakhwalkar in their study of the florescence spectrum of solid, hydrated uranyl fluoride at -185 degrees centigrade is presented. The text also discusses the theory of electronic structure and spectra of the uranyl ion. The spectroscopy of uranyl compounds in solution and the uranyl fluorescence intensity and decay are then presented. The book then explains the process of measuring the intensity of slowly decaying florescence of uranyl salts. The primary photochemical reactions in uranyl compounds are found to be slow, giving rise to many secondary thermal reactions that may be unwanted. Researchers in the fields of chemistry and physics working on actinide elements will find this collection of monographs invaluable.
E-bok
PDF, Engelska, 2013979 kr
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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.
E-bok
PDF, Engelska, 2013347 kr
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The Pharmacology of Synapses details the advancements in the understanding of synaptic pharmacology. The book examines the development in various areas of synaptic pharmacology research. The text first covers the basic concepts of synaptic pharmacology, and then proceeds to tackling the metabolism of acetylcholine. Next, the selection deals with monoamine in the central nervous system, and neuromuscular transmission in vertebrates. The text also discusses the pharmacology of autonomic ganglia. Chapters 7 and 8 detail the pharmacological studies on neurons in the brain and spinal cord. The ninth chapter deals with the neuromuscular transmission in invertebrates, while the 10th chapter deals with drugs, transmission, and molluskan neurons. The book will be of great use to researchers and practitioners of pharmacology, neurology, biological psychology, and psychiatry.
E-bok
PDF, Engelska, 2013756 kr
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Nuclear Energy, Volume 102: Radiation Damage in Graphite provides a general account of the effects of irradiation on graphite. This book presents valuable work on the structure of the defects produced in graphite crystals by irradiation. Organized into eight chapters, this volume begins with an overview of the description of the methods of manufacturing graphite and of its physical properties. This text then presents details of the method of setting up a scale of irradiation dose. Other chapters consider the effect of irradiation at a given temperature on a physical property of graphite. This book discusses as well the changes in dimensions produced by irradiation and the effects of irradiation on the mechanical properties of graphite. The final chapter deals with the accumulation of stored energy, which is one of the main problems caused by the irradiation of graphite in nuclear reactors. This book is a valuable resource for physicists and chemical physicists.
Resonance Absorption in Nuclear Reactors
International Series of Monographs on Nuclear Energy, Vol. 4
E-bok
PDF, Engelska, 2013344 kr
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Reactor Design Physics, Volume 4: Resonance Absorption in Nuclear Reactors provides a systematic and detailed exposition of the theory of resonance absorption in nuclear reactors. This book is composed of eight chapters, and begins with a brief historical review of the subject. The second chapter deals with the resonance absorption in homogeneous media and with an alternative method of obtaining some of the formula, while the third chapter considers the natural and Doppler broadened fine shapes, as well as explicit formula for resonance absorption in homogeneous media. The succeeding chapters discuss some results of transport theory necessary for the study of the resonance absorption problem in heterogeneous media and the estimation of the errors introduced by the various simplifying assumptions. The final chapters examine the special topics of the Dancoff effect and the estimation of absorption in unresolved resonances. This book will prove useful to nuclear physicists and design engineers.
E-bok
PDF, Engelska, 2013756 kr
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Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactors, the dispersion of radioactive material, and requirements for reactor sites. The final chapter focuses on operating experience with nuclear reactors. It presents a of history of reactor incidents which are useful to study since much of the knowledge of reactor safety has come from the conscientious reporting of the details and circumstances of failure.
E-bok
PDF, Engelska, 2016344 kr
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Neutron Cross Sections presents the principles of cross-section measurement and use, as well as sufficient theory so that the general behavior of cross sections is made understandable. This compilation is a direct result of experiences connected with the collection and evaluation of cross-section data during the past eight years at ""Sigma Centre"", Brookhaven National Laboratory. Here, experimental results received from laboratories throughout the world are carefully evaluated and compiled in the curves and tables of the large volume Neutron Cross Sections, The most recent version of the compilation, known as BNL 325, appeared 1 July 1955, and Supplement 1 to BNL 325 was published on 1 January 1957. The compilation itself consists almost completely of cross sections at specific energies, shown in the form of curves or tables, with only brief explanatory texts. The text opens with discussions of the general properties of cross sections and principles of nuclear structure that are important to the understanding of cross-section behavior. Separate chapters follow that describe specific techniques for measuring cross sections along with experimental results involving fast neutrons, resonance neutrons, resonances in fissionable materials, and thermal neutrons.