Nuclear Engineering
An Introduction
Published on 6. December 2012
X, 566 pages
978-3-642-48876-4 (ISBN)
Description
***VERKAUFSKATEGORIE*** 1 e This textbook covers the core subjects of nuclear engineering. Developed to meet the needs of today's students and nuclear power plant operators, the text establishes a framework for the various areas of knowledge that comprise the field and explains rather than just defines the relevant physical phenomena. For today's engineer the principal analytical design tool is the personal computer. The text takes advantage of this recent development. PC programs are provided which either expand the computational range accessible to the student, or serve to illustrate the relevant physical phenomena. Some of the included programs are simplified versions of computational procedures used in the field and can be used as training tool for design calculations. The text devotes special attention to subjects which have an impact on the safe operation of nuclear power reactors. This includes the design of safety optimized core configurations, the physical mechanisms underlying the various reactivity coefficients, and the calibration procedures for control rods. A final chapter is devoted to the licensing and safety evaluation of power reactors.
More details
Other editions
Additional editions
Book
04/2014
Springer
€74.99
Article exhausted; check different version
Book
03/1992
Springer
€85.55
Article exhausted; check different version
Content
1 Introduction.- 1.1 The General and the Unique.- 1.2 The Law of Laws.- 1.3 A Neutron Population Balance.- 2 Neutron/Nuclei Balance - The Fission Source.- 2.1 Fission Process as an Example.- 2.2 Radioactive Decay.- Rroblems.- 3 Neutron Interaction with Matter.- 3.1 Macroscopic and Microscopic Cross Sections.- 3.2 Neutron Fluxes, Currents, and Beams.- 3.3 Cross-Sections Type.- 3.4 Macroscopic Cross-Sections.- 3.5 Energy Dependence of Cross-Sections.- 3.6 The "Six Factor" Formula.- 3.7 The SIXFAC Program.- 3.8 Calculation of k?.- 3.9 Calculation of k? for a "fast reactor".- 3.10 Effective multiplication factor, keff.- Problems.- 4 Neutron Diffusion - Basic Concepts.- 4.1 Fick's Law.- 4.2 The Diffusion Coefficient.- 4.3 Fick's Law Analogues in Other Branches of Science.- 4.4 The One-group Diffusion Equation.- 4.5 Boundary Conditions.- 4.6 Solution to the One-group Diffusion Equation.- Problems.- 5 Neutron Balance - Energy.- 5.1 Neutron Moderation.- 5.2 Neutron Energy Distribution in the Epithenmal Region.- 5.3 Properties and Classification of Moderators.- 5.4 Thermal Neutrons.- Problems.- 6 Criticality.- 6.1 Criticality and the Neutron Balance Equation.- 6.2 Basic Relationships. The 'Text Book' Slab Core.- 6.3 Criticality Condition for the Generic Bare Core.- 6.4 Criticality for Multienergy Group Neutron Balances.- 6.5 Finite Difference Solution Methods.- 6.6 The MULTIDIF (MULTI-group DIF-usion) Code.- Problems.- 7 Neutron Balance - Time.- 7.1 Prompt and Delayed Neutrons.- 7.2 Solution of Kinetics Equations.- 7.3 Reactor Control Methods.- 7.4 Control Practice.- 7.5 Temperature and Power Coefficients of Reactivity.- 7.6 Fission Product Effects.- Problems.- 8 Gamma and Neutron Radiation Effects.- 8.1 Importance of Gamma Rays.- 8.2 RadiationUnits.- 8.3 Radiation Sources.- 8.4 Biological Effects of Radiation.- 8.5 Radiation Protection Standards.- Problems.- 9 Shielding.- 9.1 Basic Concepts.- 9.2 Buildup Factors.- 9.3 Basic Shield Geometries.- 9.4 Computer Methods in Gamma Shield Design.- 9.5 Reactor Shielding Problems.- 9.6 Neutron Shielding. Exact Methods.- Problems.- 10 Core Heat Removal.- 10.1 Core Energy Balance.- 10.2 Energy Sources.- 10.3 The Heat Transfer Path.- 10.4 DNB and CHF Ratios.- Problems.- 11 Reactor Licensing.- 11.1 The Nuclear Regulatory Commission: Historical Background.- 11.2 The NRC: Organizational Structure and the "Licensing Process".- 11.3 Title 10 of the Code of Federal Regulations (10 CFR).- 11.4 The Design-Basis Accidents.- 11.5 The Multiple Barriers.- 11.6 Fission Product Release.- 11.7 Atmospheric Dispersion.- 11.8 Class Nine Accidents.- 11.9 Accident Risk Analysis.- Problems.
