1st Edition

Fractional Calculus with Applications for Nuclear Reactor Dynamics

By Santanu Saha Ray Copyright 2016
    240 Pages
    by CRC Press

    236 Pages 93 B/W Illustrations
    by CRC Press

    Introduces Novel Applications for Solving Neutron Transport Equations

    While deemed nonessential in the past, fractional calculus is now gaining momentum in the science and engineering community. Various disciplines have discovered that realistic models of physical phenomenon can be achieved with fractional calculus and are using them in numerous ways. Since fractional calculus represents a reactor more closely than classical integer order calculus, Fractional Calculus with Applications for Nuclear Reactor Dynamics focuses on the application of fractional calculus to describe the physical behavior of nuclear reactors. It applies fractional calculus to incorporate the mathematical methods used to analyze the diffusion theory model of neutron transport and explains the role of neutron transport in reactor theory.

    The author discusses fractional calculus and the numerical solution for fractional neutron point kinetic equation (FNPKE), introduces the technique for efficient and accurate numerical computation for FNPKE with different values of reactivity, and analyzes the fractional neutron point kinetic (FNPK) model for the dynamic behavior of neutron motion. The book begins with an overview of nuclear reactors, explains how nuclear energy is extracted from reactors, and explores the behavior of neutron density using reactivity functions. It also demonstrates the applicability of the Haar wavelet method and introduces the neutron diffusion concept to aid readers in understanding the complex behavior of average neutron motion.

    This text:

    • Applies the effective analytical and numerical methods to obtain the solution for the NDE
    • Determines the numerical solution for one-group delayed neutron FNPKE by the explicit finite difference method
    • Provides the numerical solution for classical as well as fractional neutron point kinetic equations
    • Proposes the Haar wavelet operational method (HWOM) to obtain the numerical approximate solution of the neutron point kinetic equation, and more

    Fractional Calculus with Applications for Nuclear Reactor Dynamics thoroughly and systematically presents the concepts of fractional calculus and emphasizes the relevance of its application to the nuclear reactor.

    Mathematical Methods in Nuclear Reactor Physics
    Analytical Methods and Numerical Techniques for Solving Deterministic Neutron Diffusion and Kinetic Models
    Numerical Methods for Solving Stochastic Point Kinetic Equations
    Neutron Diffusion Equation Model in Dynamical Systems
    Introduction
    Outline of the Present Study
    Application of the Variational Iteration Method to Obtain the Analytical Solution of the NDE
    Application of the Modified Decomposition Method to Obtain the Analytical Solution of NDE
    Numerical Results and Discussions for Neutron Diffusion Equations
    One-Group NDE in Cylindrical and Hemispherical Reactors
    Application of the ADM for One-Group Neutron Diffusion Equations
    Conclusion
    Fractional Order Neutron Point Kinetic Model
    Introduction
    Brief Description for Fractional Calculus
    FNPKE and Its Derivation
    Application of Explicit Finite Difference Scheme for FNPKE
    Analysis for Stability of Numerical Computation
    Numerical Experiments with Change of Reactivity
    Conclusion
    Numerical Solution for Deterministic Classical and Fractional Order Neutron Point Kinetic Model
    Introduction
    Application of MDTM to Classical Neutron Point Kinetic Equation
    Numerical Results and Discussions for Classical Neutron Point Kinetic Model Using Different Reactivity Functions
    Mathematical Model for Fractional Neutron Point Kinetic Equation
    Fractional Differential Transform Method
    Application of MDTM to Fractional Neutron Point Kinetic Equation
    Numerical Results and Discussions for Fractional Neutron Point Kinetic Equation
    Conclusion
    Classical and Fractional Order Stochastic Neutron Point Kinetic Model
    Introduction
    Evolution of Stochastic Neutron Point Kinetic Model
    Classical Order Stochastic Neutron Point Kinetic Model
    Numerical Solution of the Classical Stochastic Neutron Point Kinetic Equation
    Numerical Results and Discussions for the Solution of Stochastic Point Kinetic Model
    Application of Explicit Finite Difference Method for Solving Fractional Order Stochastic Neutron Point Kinetic Model
    Numerical Results and Discussions for the FSNPK Equations
    Analysis for Stability of Numerical Computation for the FSNPK Equations
    Conclusion
    Solution for Nonlinear Classical and Fractional Order Neutron Point Kinetic Model with Newtonian Temperature Feedback Reactivity
    Introduction
    Classical Order Nonlinear Neutron Point Kinetic Model
    Numerical Solution of Nonlinear Neutron Point Kinetic Equation in the Presence of Reactivity Function
    Numerical Results and Discussions for the Classical Order Nonlinear Neutron Point Kinetic Equation
    Mathematical Model for Nonlinear Fractional Neutron Point Kinetic Equation
    Application of EFDM for Solving the Fractional Order Nonlinear Neutron Point Kinetic Model
    Numerical Results and Discussions for Fractional Nonlinear Neutron Point Kinetic Equation with Temperature Feedback Reactivity Function
    Computational Error Analysis for the Fractional Order Nonlinear Neutron Point Kinetic Equation
    Conclusion
    Numerical Simulation Using Haar Wavelet Method for Neutron Point Kinetic Equation Involving Imposed Reactivity Function
    Introduction
    Haar Wavelets
    Function Approximation and Operational Matrix of the General Order Integration
    Application of the HWOM for Solving Neutron Point Kinetic Equation
    Numerical Results and Discussions
    Convergence Analysis and Error Estimation
    Conclusion
    Numerical Solution Using Two- Dimensional Haar Wavelet Method for Stationary Neutron Transport Equation in Homogeneous Isotropic Medium
    Introduction
    Formulation of Neutron Transport Equation Model
    Mathematical Model of the Stationary Neutron Transport Equation in a Homogeneous Isotropic Medium
    Application of the Two-Dimensional Haar Wavelet Collocation Method to Solve the Stationary Neutron Transport Equation
    Numerical Results and Discussions for Stationary Integer Order Neutron Transport Equation
    Mathematical Model for Fractional Order Stationary Neutron Transport Equation
    Application of the Two-Dimensional Haar Wavelet Collocation Method to the Fractional Order Stationary Neutron Transport Equation
    Numerical Results and Discussions for Fractional Order Neutron Transport Equation
    Convergence Analysis of the Two-Dimensional Haar Wavelet Method
    Conclusion
    References

    Biography

    Dr. Santanu Saha Ray is an associate professor at the National Institute of Technology, Rourkela, India. He earned a Ph. D. in applied mathematics at Jadavpur University. He is a member of SIAM, the AMS, and the Indian Science Congress Association, and serves as the editor-in-chief for the International Journal of Applied and Computational Mathematics. Dr. Saha Ray has done extensive work in the area of fractional calculus and its role in nuclear science and engineering.

    "The textbook covers a wide range of models and methods for neutron transport and will be a welcome addition to many undergraduate and graduate courses. Graduate students working in nuclear engineering neutron transport area will appreciate the details of the methods, and will find this book useful to guide their research."
    —Igor A. Bolotnov, Department of Nuclear Engineering, North Carolina State University

    "I have read the two sample chapters provided with me. I found no irregulaity in these two chapters. The table of content is absolutely ideal. This book focuses on the application of fractional calculus to describe the physical behavior of nuclear reactors. The sample chapters reflect the concept of the subject fairly.

    In my opinion this book will be indispensable in the field of nuclear reactor science and engineering."

    —Dr. Rasajit Kumar Bera, M. Sc. (Applied Maths., Gold Medalist), Ph. D.(Sc.), Retired Professor & Head of the Department of Science, National Institute of Technical Teacher’s Training and Research (Eastern Region), Block-FC, Sector-III, Salt Lake City, Kolkata-700106, India