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Mathematical Topics in Neutron Transport Theory
  • Language: en
  • Pages: 372

Mathematical Topics in Neutron Transport Theory

This book presents some recent mathematical developments about neutron transport equations. Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness properties of perturbed of 0-semigroups in Banach spaces with applications to transport theory, Miyadera perturbations of c0-semigroups in Banach spaces with applications to singular transport equations, a thorough analysis of the leading eigenelements of transport operators and their approximation, scattering theory. Besides the new problems addressed in this book a unification and extension of the classical spectral analysis of neutron transport equations is given.

Neutron Transport
  • Language: en
  • Pages: 284

Neutron Transport

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.

Numerical Methods in the Theory of Neutron Transport
  • Language: en
  • Pages: 632
Mathematical Topics In Neutron Transport Theory: New Aspects
  • Language: en
  • Pages: 372

Mathematical Topics In Neutron Transport Theory: New Aspects

This book presents some recent mathematical developments about neutron transport equations. Several different topics are dealt with including regularity of velocity averages, spectral analysis of transport operators, inverse problems, nonlinear problems arising in the stochastic theory of neutron chain fissions, compactness properties of perturbed of c0-semigroups in Banach spaces with applications to transport theory, Miyadera perturbations of c0-semigroups in Banach spaces with applications to singular transport equations, a thorough analysis of the leading eigenelements of transport operators and their approximation, scattering theory. Besides the new problems addressed in this book a unification and extension of the classical spectral analysis of neutron transport equations is given.

Introduction to the Theory of Neutron Diffusion
  • Language: en
  • Pages: 192

Introduction to the Theory of Neutron Diffusion

  • Type: Book
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  • Published: 1953
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  • Publisher: Unknown

None

Solution of an Initial-value Problem in Linear Transport Theory
  • Language: en
  • Pages: 122

Solution of an Initial-value Problem in Linear Transport Theory

  • Type: Book
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  • Published: 1971
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  • Publisher: Unknown

The solution of an initial-value problem in linear transport theory is obtained by using the normal-mode expansion technique of Case. The problem is that of monoenergetic neutrons migrating in a thin slab surrounded by infinitely thick reflectors and the scattering is taken to be isotropic. The results obtained indicate that the reflector may give rise to a branch-cut integral term typical of a semi-infinite medium whereas the central slab may contribute a summation over discrete residue terms. Exact expressions are obtained for these discrete time eigenvalues, and numerical results showing the behavior of real time eigenvalues as a function of the material properties of the slab and reflect...

Mathematical Methods in Particle Transport Theory
  • Language: en
  • Pages: 466

Mathematical Methods in Particle Transport Theory

None

Handbook of Nuclear Engineering
  • Language: en
  • Pages: 3701

Handbook of Nuclear Engineering

This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Linear Transport Theory
  • Language: en
  • Pages: 360

Linear Transport Theory

  • Type: Book
  • -
  • Published: 1967
  • -
  • Publisher: Unknown

None

Transport Theory
  • Language: en
  • Pages: 340

Transport Theory

The industrial and military applications of atomic energy have stimulated much mathematical research in neutron transport theory. The possibility of controlled thermonuclear processes has similarly focussed attention upon plasmas, sometimes called the "fourth state of matter". Independently, many classical aspects of kinetic theory and radiative transfer theory have been studied both because of their basic mathematical interest and of their physical applications to areas such as upper-atmosphere meteorology - introduction.