This textbook provides a thorough explanation of the physical concepts and presents the general theory of different forms through approximations of the neutron transport processes in nuclear reactors and emphasize the numerical computing methods that lead to the prediction of neutron behavior.
Detailed derivations and thorough discussions are the prominent features of this book unlike the brevity and conciseness which are the characteristic of most available textbooks on the subject where students find them difficult to follow. This conclusion has been reached from the experience gained through decades of teaching.
The topics covered in this book are suitable for senior undergraduate and graduate students in the fields of nuclear engineering and physics. Other engineering and science students may find the construction and methodology of tackling problems as presented in this book appealing from which they can benefit in solving other problems numerically. The book provides access to a one dimensional, two energy group neutron diffusion program including a user manual, examples, and test problems for student practice. An option of a Matlab user interface is also available.
Neutron Transport The Neutron Transport Equation.- Neutron Diffusion -
The Finite Difference Solution of The Neutron Diffusion Equation.- Spherical
Harmonics The PN Method.- The Adjoint Transport Equation The Equation of
Neutron Importance.- Perturbation Theory.- The Method of Discrete Ordinates
The SN Method.
Ramadan M. Kuridan is an emeritus professor of nuclear engineering at The University of Tripoli after almost forty years of teaching. In the last eight years of his academic career, he was appointed Director of the Libyan Atomic Energy. He has been teaching the subjects covered in this book for at least twenty years. His previous book on Nuclear Reactor Theory (2004) was published in Arabic. His main research interests and publications focus on new generation reactors and Monte Carlo calculations.
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