Diffusion of Neutrons in Nuclear Reactors
An Introductory Textbook for Neutronics
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Beschreibung
This book provides an introductory exploration of nuclear reactor theory, designed for students, physicists, and engineers entering the field for the first time. It employs simplified models based on diffusion theory to facilitate numerical calculations, with direct applications to pressurized water reactors. A consistent dataset underpins the analyses throughout the text, ensuring coherence across topics.
This book offers a fundamental understanding of key reactor physics concepts, including the fundamental mode, harmonics, point kinetics, adjoint flux and perturbation method. It also examines reactor behavior in subcritical approach conditions, Dynamic Rod Weight Measurement, shadowing and anti-shadowing effects.
To maintain conciseness, the text does not cover the fundamental principles of nuclear physics required for neutronics. Readers are expected to have prior knowledge of essential topics such as the fission process and neutron cross sections. Synthetic presentations of the mathematical and physical concepts used in the book are provided in the different appendices.
This book provides an introductory exploration of nuclear reactor theory, designed for students, physicists, and engineers entering the field for the first time. It employs simplified models based on diffusion theory to facilitate numerical calculations, with direct applications to pressurized water reactors. A consistent dataset underpins the analyses throughout the text, ensuring coherence across topics.
This book offers a fundamental understanding of key reactor physics concepts, including the fundamental mode, harmonics, point kinetics, adjoint flux and perturbation method. It also examines reactor behavior in subcritical approach conditions, Dynamic Rod Weight Measurement, shadowing and anti-shadowing effects.
To maintain conciseness, the text does not cover the fundamental principles of nuclear physics required for neutronics. Readers are expected to have prior knowledge of essential topics such as the fission process and neutron cross sections. Synthetic presentations of the mathematical and physical concepts used in the book are provided in the different appendices.
Makes every effort to develop the physical sense and relies on simplified models Provides numerous illustrations, charts, tables, and calculations with a consistent set of input data for the whole book Includes many cross-references that interconnect the chapters, and quotations or references to renewed classic books
Autor*in
Hubert Grard (Deceased)
Themen in »Diffusion of Neutrons in Nuclear Reactors«
Adjoint flux Subcritical approach Inverse of the counting rate Reciprocal multiplication curve Approach to criticality Point kinetics equations Effective delayed neutrons fraction Criticality of the bare reactor Age of Fermi Two groups diffusion theory Equation of diffusion Slowing down and thermalization of neutrons Neutron density flux current Migration area for neutrons nuclear reactor xenon poisoning