Numerical Methods of Reactor Analysis von Clark, Melville: Good paperback (1964)

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Bibliografische Details

Titel: Numerical Methods of Reactor Analysis
Verlag: Academic Press
Erscheinungsjahr: 1964
Sprache: Englisch
ISBN-10: 1483237354
ISBN-13: 9781483237350
Einband: paperback
Zustand: Good
Buchtyp: book

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Inhaltsangabe

Numerical Methods of Reactor Analysis is an introduction to topics of numerical analysis frequently used in the nuclear reactor field. Emphasis is placed on methods by which machine calculations are performed on practical problems related to nuclear reactors. The multigroup diffusion methods and the Monte Carlo method are discussed. Comprised of six chapters, this volume begins by describing a simplified formulation of linear algebra, with emphasis on matrices and operations with matrices as well as the properties of special matrices. Following the introduction of a geometric interpretation of matrix equations, many matrix relations are derived, including relations used in nuclear engineering. The next chapter reviews the elementary properties of finite difference equations, with particular reference to techniques suited to digital computers. Subsequent chapters focus on numerical solutions of equations; multigroup diffusion methods; transport methods; and the Monte Carlo method. This book will be a valuable resource for first and second year graduate students taking an introductory course in reactor physics.

Rese�a del editor

Numerical Methods of Reactor Analysis is an introduction to topics of numerical analysis frequently used in the nuclear reactor field. Emphasis is placed on methods by which machine calculations are performed on practical problems related to nuclear reactors. The multigroup diffusion methods and the Monte Carlo method are discussed. Comprised of six chapters, this volume begins by describing a simplified formulation of linear algebra, with emphasis on matrices and operations with matrices as well as the properties of special matrices. Following the introduction of a geometric interpretation of matrix equations, many matrix relations are derived, including relations used in nuclear engineering. The next chapter reviews the elementary properties of finite difference equations, with particular reference to techniques suited to digital computers. Subsequent chapters focus on numerical solutions of equations; multigroup diffusion methods; transport methods; and the Monte Carlo method. This book will be a valuable resource for first and second year graduate students taking an introductory course in reactor physics.

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