{"product_id":"nuclear-reactor-analysis-isbn-9780471223634","title":"Nuclear Reactor Analysis","description":"A classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores.  This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural.  The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermalhydrolics or materials studies, which play a major role in determining a reactor design. \u003cp\u003e\u003cb\u003ePart 1:  Introductory Concepts Of Nuclear Reactor Analysis\u003cbr\u003e \u003c\/b\u003e\u003cbr\u003e Chapter 1:  An Introduction to Nuclear Power Generation 3\u003cbr\u003e \u003cbr\u003e Chapter 2:  The Nuclear Physics of Fission Chain Reactions 10\u003cbr\u003e \u003cbr\u003e Chapter 3:  Fission Chain Reactions and Nuclear Reactor--An Introduction 74\u003cbr\u003e \u003cbr\u003e \u003cb\u003ePart 2:  The One-Speed Diffusion Model Of A Nuclear Reactor\u003cbr\u003e \u003c\/b\u003e\u003cbr\u003e Chapter 4:  Neutron Transport 103\u003cbr\u003e \u003cbr\u003e Chapter 5:  The One-Speed Diffusion-Theory Model 149\u003cbr\u003e \u003cbr\u003e Chapter 6:  Nuclear Reactor Kinetics 233\u003cbr\u003e \u003cbr\u003e \u003cb\u003ePart 3:  The Multigroup Diffusion Method\u003cbr\u003e \u003c\/b\u003e\u003cbr\u003e Chapter 7:  Multigroup Diffusion Theory 285\u003cbr\u003e \u003cbr\u003e Chapter 8:  Fast-Spectrum Calculations and Fast-Group Constants 315\u003cbr\u003e \u003cbr\u003e Chapter 9:  Thermal Spectrum Calculations and Thermal Group Constants 375\u003cbr\u003e \u003cbr\u003e Chapter 10:  Cell Calculations for Heterogeneous Core Lattices 398\u003cbr\u003e \u003cbr\u003e \u003cb\u003ePart 4:  An Introduction To Nuclear Reactor-Core Design\u003cbr\u003e \u003c\/b\u003e\u003cbr\u003e Chapter 11:  General Aspects of Nuclear Reactor Core Design 447\u003cbr\u003e \u003cbr\u003e Chapter 12:  Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467\u003cbr\u003e \u003cbr\u003e Chapter 13:  The Calculation of Core Power Distributions 515\u003cbr\u003e \u003cbr\u003e Chapter 14:  Reactivity Control 537\u003cbr\u003e \u003cbr\u003e Chapter 15:  Analysis of Core-Composition Changes 566\u003cbr\u003e \u003cbr\u003e Appendices\u003c\/p\u003e \u003cp\u003eA. Some useful Nuclear Data 605\u003c\/p\u003e \u003cp\u003eB. Some useful Mathematical Formulas 611\u003c\/p\u003e \u003cp\u003eC. Step Functions, Delta Functions, and Other Exotic Beasts 613\u003c\/p\u003e \u003cp\u003eD. Some Properties of Special Functions 616\u003c\/p\u003e \u003cp\u003eE. Some Assorted Facts on Linear Operators 621\u003c\/p\u003e \u003cp\u003eF. An Introduction to Matrices and Matrix Algebra 626\u003c\/p\u003e \u003cp\u003eG. An Introduction to Laplace Transforms 629\u003c\/p\u003e \u003cp\u003eH. Typical Nuclear Power Reactor Data 634\u003c\/p\u003e \u003cp\u003eI. Units Utilized in Text 636\u003c\/p\u003e \u003cp\u003eIndex 639\u003c\/p\u003e  \u003cp\u003eJames Johnson Duderstadt was the President of the University of Michigan from 1988 to 1996. He currently holds the title of President Emeritus and University Professor of Science and Engineering at the University of Michigan. Louis J. Hamilton is the author of Nuclear Reactor Analysis, published by Wiley.\u003c\/p\u003e","brand":"Wiley","offers":[{"title":"Default Title","offer_id":47989701542117,"sku":"NP9780471223634","price":234.5,"currency_code":"USD","in_stock":false}],"thumbnail_url":"\/\/cdn.shopify.com\/s\/files\/1\/1842\/7735\/files\/9780471223634.jpg?v=1761785164","url":"https:\/\/k12savings.com\/es\/products\/nuclear-reactor-analysis-isbn-9780471223634","provider":"K12savings","version":"1.0","type":"link"}