Nuclear Reactor Analysis
Published on 1. January 1976
Book
Paperback/Softback
672 pages
978-0-471-22363-4 (ISBN)
Description
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.
More details
Product info
50:B&W 7.44 x 9.69 in or 246 x 189 mm (Crown 4vo) Perfect Bound on White w/Gloss Lam
Language
English
Place of publication
New York
United States
Target group
College/higher education
Professional and scholarly
Dimensions
Height: 264 mm
Width: 183 mm
Thickness: 39 mm
Weight
1288 gr
ISBN-13
978-0-471-22363-4 (9780471223634)
Schweitzer Classification
Persons
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.
Content
Part 1: INTRODUCTORY CONCEPTS OF NUCLEAR REACTOR ANALYSIS. Chapter 1: An Introduction to Nuclear Power Generation. Chapter 2: The Nuclear Physics of Fission Chain Reactions. Chapter 3: Fission Chain Reactions and Nuclear Reactor--An Introduction. Part 2: THE ONE-SPEED DIFFUSION MODEL OF A NUCLEAR REACTOR. Chapter 4: Neutron Transport. Chapter 5: The One-Speed Diffusion-Theory Model. Chapter 6: Nuclear Reactor Kinetics. Part 3: THE MULTIGROUP DIFFUSION METHOD. Chapter 7: Multigroup Diffusion Theory. Chapter 8: Fast-Spectrum Calculations and Fast-Group Constants. Chapter 9: Thermal Spectrum Calculations and Thermal Group Constants. Chapter 10: Cell Calculations for Heterogeneous Core Lattices. Part 4: AN INTRODUCTION TO NUCLEAR REACTOR-CORE DESIGN. Chapter 11: General Aspects of Nuclear Reactor Core Design. Chapter 12: Thermo-Hydraulic Analysis of Nuclear Reactor Cores. Chapter 13: The Calculation of Core Power Distributions. Chapter 14: Reactivity Control. Chapter 15: Analysis of Core-Composition Changes. Appendices.