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 thermal-hydraulics or materials studies, which play a major role in determining a reactor design.

James 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.

PART 1 Introductory Concepts of Nuclear Reactor Analysis

An Introduction to Nuclear Power Generation

3

(7)

Nuclear Fission Reactors

4

(2)

Role of the Nuclear Engineer

6

(1)

Scope of the Text

7

(3)

The Nuclear Physics of Fission Chain Reactions

10

(64)

Nuclear Reactions

12

(42)

Nuclear Fission

54

(20)

Fission Chain Reactions and Nuclear Reactors--an Introduction

74

(29)

The Multiplication Factor and Nuclear Criticality

74

(14)

An Introduction to Nuclear Power Reactors

88

(8)

Nuclear Reactor Design

96

(7)

PART 2 The One-Speed Diffusion Model of a Nuclear Reactor

Neutron Transport

103

(46)

Introductory Concepts

105

(6)

The Neutron Transport Equation

111

(6)

Direct Numerical Solution of the Transport Equation

117

(7)

The Diffusion Approximation

124

(25)

The One-Speed Diffusion Theory Model

149

(84)

The One-Speed Diffusion Equation

150

(7)

Neutron Diffusion in Nonmultiplying Equation

157

(39)

The One-Speed Diffusion Model of a Nuclear Reactor

196

(18)

Reactor Criticality Calculations

214

(5)

Perturbation Theory

219

(14)

Nuclear Reactor Kinetics

233

(52)

The Point Reactor Kinetics Model

235

(6)

Solution of the Point Reactor Kinetics Equations

241

(16)

Reactivity Feedback and Reactor Dynamics

257

(11)

Experimental Determination of Reactor Kinetic Parameters

268

(8)

Spatial Effects in Reactor Kinetics

276

(9)

PART 3 The Multigroup Diffusion Method

Multigroup Diffusion Theory

285

(30)

A Heuristic Derivation of the Multigroup Diffusion Equations

286

Derivation of the Multigroup Equations from Energy-Dependent Diffusion Theory

288

(7)

Simple Applications of the Multigroup Diffusion Model

295

(6)

Numerical Solution of the Multigroup Diffusion Equations

301

(7)

Multigroup Perturbation Theory

308

(3)

Some Concluding Remarks

311

(4)

Fast Spectrum Calculations and Fast Group Constants

315

(60)

Neutron Slowing Down in an Infinite Medium

317

(15)

Resonance Absorption (Infinite Medium)

332

(15)

Neutron Slowing Down in Finite Media

347

(11)

Fast Spectrum Calculations and Fast Group Constants

358

(17)

Thermal Spectrum Calculations and Thermal Group Constants

375

(23)

General Features of Thermal Neutron Spectra

377

(7)

Approximate Models of Neutron Thermalization

384

(8)

General Calculations of Thermal Neutron Spectra

392

(6)

Cell Calculations for Heterogeneous Core Lattices

398

(49)

Lattice Effects in Nuclear Reactor Analysis

399

(14)

Heterogeneous Effects in Thermal Neutron Physics

413

(14)

Heterogeneous Effects in Fast Neutron Physics

427

(12)

Some Concluding Remarks in the Multigroup Diffusion Methods

439

(8)

PART 4 An Introduction to Nuclear Reactor Core Design

General Aspects of Nuclear Reactor Core Design

447

(20)

Nuclear Core Analysis

448

(6)

Other Areas of Reactor Core Analysis

454

(6)

Reactor Calculation Models

460

(7)

Thermal-hydraulic Analysis of Nuclear Reactor Cores

467

(48)

Introduction

467

(6)

Power Generation in Nuclear Reactor Cores

473

(2)

Radial Heat Conduction in Reactor Fuel Elements

475

(8)

Forced Convection Heat Transfer in Single-Phase Coolants

483

(6)

Boiling Heat Transfer in Nuclear Reactor Cores

489

(9)

Hydrodynamic Core Analysis

498

(4)

Thermal-hydraulic Core Analysis

502

(13)

The Calculation of Core Power Distributions

515

(22)

Static Multigroup Diffusion Calculations

516

(3)

Interaction of Thermal-hydraulics, Neutronics, and Fuel Depletion

519

(3)

Parameterization of Few-Group Constants

522

(3)

Flux Synthesis Methods

525

(4)

Local Power-Peaking Effects

529

(8)

Reactivity Control

537

(29)

Introduction

537

(3)

Movable Control Rods

540

(11)

Burnable Poisons

551

(3)

Chemical Shim

554

(2)

Inherent Reactivity Effects

556

(10)

Analysis of Core Composition Changes

566

Fission Product Poisoning

567

Fuel Depletion Analysis

580

Nuclear Fuel Management

589

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Nuclear Reactor Analysis

9780471223634

0471223638

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