Description

Book Synopsis
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.

Table of Contents

Part 1: Introductory Concepts Of Nuclear Reactor Analysis

Chapter 1: An Introduction to Nuclear Power Generation 3

Chapter 2: The Nuclear Physics of Fission Chain Reactions 10

Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74

Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor

Chapter 4: Neutron Transport 103

Chapter 5: The One-Speed Diffusion-Theory Model 149

Chapter 6: Nuclear Reactor Kinetics 233

Part 3: The Multigroup Diffusion Method

Chapter 7: Multigroup Diffusion Theory 285

Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315

Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375

Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398

Part 4: An Introduction To Nuclear Reactor-Core Design

Chapter 11: General Aspects of Nuclear Reactor Core Design 447

Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467

Chapter 13: The Calculation of Core Power Distributions 515

Chapter 14: Reactivity Control 537

Chapter 15: Analysis of Core-Composition Changes 566

Appendices

A. Some useful Nuclear Data 605

B. Some useful Mathematical Formulas 611

C. Step Functions, Delta Functions, and Other Exotic Beasts 613

D. Some Properties of Special Functions 616

E. Some Assorted Facts on Linear Operators 621

F. An Introduction to Matrices and Matrix Algebra 626

G. An Introduction to Laplace Transforms 629

H. Typical Nuclear Power Reactor Data 634

I. Units Utilized in Text 636

Index 639

Nuclear Reactor Analysis

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    A Paperback / softback by James J. Duderstadt, Louis J. Hamilton

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      View other formats and editions of Nuclear Reactor Analysis by James J. Duderstadt

      Publisher: John Wiley & Sons Inc
      Publication Date: 01/01/1976
      ISBN13: 9780471223634, 978-0471223634
      ISBN10: 0471223638

      Description

      Book Synopsis
      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.

      Table of Contents

      Part 1: Introductory Concepts Of Nuclear Reactor Analysis

      Chapter 1: An Introduction to Nuclear Power Generation 3

      Chapter 2: The Nuclear Physics of Fission Chain Reactions 10

      Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction 74

      Part 2: The One-Speed Diffusion Model Of A Nuclear Reactor

      Chapter 4: Neutron Transport 103

      Chapter 5: The One-Speed Diffusion-Theory Model 149

      Chapter 6: Nuclear Reactor Kinetics 233

      Part 3: The Multigroup Diffusion Method

      Chapter 7: Multigroup Diffusion Theory 285

      Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants 315

      Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants 375

      Chapter 10: Cell Calculations for Heterogeneous Core Lattices 398

      Part 4: An Introduction To Nuclear Reactor-Core Design

      Chapter 11: General Aspects of Nuclear Reactor Core Design 447

      Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores 467

      Chapter 13: The Calculation of Core Power Distributions 515

      Chapter 14: Reactivity Control 537

      Chapter 15: Analysis of Core-Composition Changes 566

      Appendices

      A. Some useful Nuclear Data 605

      B. Some useful Mathematical Formulas 611

      C. Step Functions, Delta Functions, and Other Exotic Beasts 613

      D. Some Properties of Special Functions 616

      E. Some Assorted Facts on Linear Operators 621

      F. An Introduction to Matrices and Matrix Algebra 626

      G. An Introduction to Laplace Transforms 629

      H. Typical Nuclear Power Reactor Data 634

      I. Units Utilized in Text 636

      Index 639

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