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Monday, May 11, 2020 | History

6 edition of Nuclear reactor theory and design found in the catalog.

Nuclear reactor theory and design

by Roger A. Rydin

  • 150 Want to read
  • 23 Currently reading

Published by University Publications in Blacksburg, Va .
Written in English

    Subjects:
  • Nuclear reactors,
  • Nuclear reactors -- Design and construction

  • About the Edition

    Table of Contents Page


    CHAPTER 1 INTRODUCTION 1

    1.1 Background 1
    1.2 Historical Approach 2
    1.3 Neutron Density 5
    1.4 Reaction Rates 6
    1.5 Design Approximations 11
    1.6 Reactor Design Implications 12

    CHAPTER 2 INTERACTIONS OF NEUTRONS
    WITH MATTER 17

    2.1 Compound Nucleus - Cross Sections 17
    2.2 Nuclear Systematics of Naturally Occurring
    Isotopes 23
    2.3 Level Widths and Partial Cross Sections 25
    2.3 Cross Section for Formulation of the Compound
    Nucleus 26
    2.5 Reaction Probabilities 28
    2.6 Kinematics in the Center-of-Mass System 30
    2.7 Relationships Between the Scattering
    Angles in the LAB and CM Systems 36

    CHAPTER 3 NUCLEAR FISSION 45

    3.1 Binding Energy 45
    3.2 Liquid Drop Model of Fission 48
    3.3 Fission Product Yields 55
    3.4 Fission Neutron Spectrum 57
    3.5 Prompt Neutrons 59
    3.6 Delayed Neutrons 62
    3.7 Energy Production in Fission 64

    CHAPTER 4 DERIVATION OF THE NEUTRON
    DIFFUSION EQUATION 69

    4.1 Fick"s Law Derivation of the Diffusion Equation 69
    4.2* The One-Speed Transport Equation 74
    4.3* One-Dimensional, One-Speed Transport Equation 80
    4.4* Derivation of the P1 Equations 86
    4.5 The P1 Diffusion Theory Approximation 89
    4.6 Comments on the P1 Equations of Diffusion Theory 92
    4.7* Alternate Derivation of the Diffusion Equation 94






    CHAPTER 5 ANALYTIC SOLUTIONS TO THE
    ONE-SPEED DIFFUSION EQUATION 99

    5.1 Partial Currents and the Extrapolated Boundary
    Condition 99
    5.2 Source Plane Boundary Conditions 107
    5.3 Two Region Planar Problem 111
    5.4 Point and Line Sources 113
    5.5 Solution to the Inhomogeneous Source Problem 120
    5.6* General Derivation of the Green"s Function
    Superposition Integral 123
    5.7 Diffusion Length 126
    5.8 Critical Reactors 128
    5.9 Homogeneous Bare Critical Slab Reactor 131
    5.10 Two Region Slab Reactor 135
    5.11 One-Dimensional Bare Homogeneous Cylindrical Reactor 138
    5.12 Bare Homogeneous Spherical Reactor 141
    5.13 Comments on Multi-region One-Dimensional
    Reactors 145
    5.14 Multidimensional Reactors 149
    5.15* Diffusion Length Experiment 152

    CHAPTER 6 FEW-GROUP EQUATIONS AND
    NUMERICAL SOLUTION METHODS 165

    6.1 Energy-Dependent Diffusion Equation 165
    6.2 Few-Group Diffusion Equations 167
    6.3 Finite Difference Few-Group Equations in
    One Dimension 172
    6.4 Specification of Boundary Conditions 180
    6.5 Direct Solution of the Source Problem 182
    6.6* Iterative Solution of the Source Problem 187
    6.7 Iterative Solution of the Critical Reactor
    Problem 193
    6.8* Convergence of the Outer Iteration to the
    Fundamental Mode Solution 198
    6.9 Qualitative Comparison Between One-Speed
    and Two-Group Solutions 202

    CHAPTER 7 PERTURBATION THEORY 211

    7.1 Adjoint Equations 211
    7.2 Matrix Form of the Adjoint Equations 217
    7.3 First-Order Perturbation Theory 220
    7.4* Perturbation Effects on Higher Harmonic
    Modes 224
    7.5 Control Rod Worth 226
    7.6* Inhomogeneous Case 230





    CHAPTER 8 REACTOR KINETICS 239

    8.1 Multigroup Reactor Kinetics Equation 240
    8.2 Interpretation of Spatial Kinetics Results 246
    8.3 Point Kinetics Equations 249
    8.4 Results for One Group of Delayed Neutrons 255
    8.5 Experimental Measurement of Control Rod Worth 261
    8.6* "Point" Kinetics Equations Derivation 263
    8.7 Method of Obtaining and 267

    CHAPTER 9 POISONING, TEMPERATURE EFFECTS,
    AND DEPLETION IN REACTORS 275

    9.1 The Fission Product Xenon-135 276
    9.2 Xenon Poisoning 277
    9.3 General Transient Solution for Buildup
    of Xenon and Iodine 279
    9.4 Spatial Xenon Transients 283
    9.5 Xenon-Induced Spatial Power Oscillations 284
    9.6 Samarium Poisoning 289
    9.7 Temperature Effects on Reactivity 293
    9.8 Effect of Thermal Feedback on Reactor Kinetics 297
    9.9 Depletion 308

    CHAPTER 10 NEUTRON MODERATION 321

    10.1 Scattering Collisions 322
    10.2 Slowing Down Problem 329
    10.3 Slowing Down in Hydrogen With No Absorption 330
    10.4 The Slowing Down Density in Hydrogen,
    No Absorption 333
    10.5 Moderation for A > 1, No Absorption 335
    10.6 Asymptotic Slowing Down Theory, A > 1,
    No Absorption 339
    10.7* Slowing Down in Hydrogen With Absorption 343
    10.8* Special Cases of Slowing Down With
    Absorption, A > 1 347
    10.9 Final Comments 353

    CHAPTER 11 SLOWING DOWN IN THE PRESENCE
    OF RESONANCES 357

    11.1 Resonance Cross Sections 358
    11.2 Doppler Effect 365
    11.3 Slowing Down in the Presence of Resonances 373
    11.4 Homogeneous-Medium Resonance Absorption 376
    11.5 Homogeneous Resonance Integrals 385
    11.6* Heterogeneous System Resonance Absorption 391
    11.7 Reactor Design Implications of
    Heterogeneous Lumping 407
    11.8 The GAM Multigroup Slowing Down Equations 412




    CHAPTER 12 THERMALIZATION 429

    12.1 Neutron Balance Equation 430
    12.2* Monatomic Gas Moderator Cross Sections 432
    12.3 Solution to the Monatomic Gas
    Thermalization Problem 443
    12.4 General Case Solution 446
    12.5 Spatial Effects in the Thermalization
    Problem 451


    APPENDIX A. THE SINGULARITY FUNCTIONS 461

    APPENDIX B. THE LAPLACE TRANSFORM 465

    APPENDIX C. MATRIX RELATIONSHIPS 473

    APPENDIX D. SPHERICAL HARMONICS 479

    APPENDIX E. DIFFERENTIATION OF AN
    INTEGRAL 483

    INDEX 485

    Edition Notes

    Includes bibliographies and index. Third edition available from author in pdf form, [email protected]

    StatementRoger A. Rydin.
    SeriesPBS series in reactor physics
    Classifications
    LC ClassificationsTK9202 R85
    The Physical Object
    Paginationxi, 385 p. :
    Number of Pages385
    ID Numbers
    Open LibraryOL18944429M

    Introduction to Nuclear Reactor Theory book. Read reviews from world’s largest community for readers/5.   An introductory course in Nuclear Reactor Theory based on lectures from several reactor theory textbooks like Lamarsh, Stacey, and Lewis.

      Nuclear Structure Theory provides a guide to nuclear structure theory. The book is comprised of 23 chapters that are organized into four parts; each part covers an aspect of nuclear structure theory. In the first part, the text discusses the experimentally observed phenomena, which nuclear structure theories need to look into and detail the Book Edition: 1.   Lecture 1 - Definition of a plasma, Nuclear Reactor - Understanding how it works Nuclear Fission Reactor Design - Duration: In addition, nuclear fuel cycle and associated economics analysis are presented, together with the application of modern control theory to reactor operation. This important book: Provides a comprehensive introduction to the fundamental concepts of nuclear reactor physics and engineering Contains information on nuclear reactor kinetics and.

    Nuclear Reactor Engineering book. Read 2 reviews from the world's largest community for readers. yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Trivia About Nuclear Reactor E /5. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. INTRODUCTION TO NUCLEAR REACTOR PHYSICS is the most comprehensive, modern and readable textbook for this course/module. It explains reactors, fuel cycles, radioisotopes, radioactive materials, design, and operation. Chain reaction and fission reactor concepts are presented, plus advanced coverage including neutron diffusion theory.


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