Two-Group Neutron Transport Theory for Plane and Spherical Geometry

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (257 download)

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Book Synopsis Two-Group Neutron Transport Theory for Plane and Spherical Geometry by : Klaus Oswald Thielheim

Download or read book Two-Group Neutron Transport Theory for Plane and Spherical Geometry written by Klaus Oswald Thielheim and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Neutron Transport

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Publisher : Springer Nature
ISBN 13 : 3031269322
Total Pages : 284 pages
Book Rating : 4.0/5 (312 download)

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Book Synopsis Neutron Transport by : Ramadan M. Kuridan

Download or read book Neutron Transport written by Ramadan M. Kuridan and published by Springer Nature. This book was released on 2023-10-28 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Two-group Approach in Neutron Transport Theory in Plane Geometry

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (115 download)

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Book Synopsis Two-group Approach in Neutron Transport Theory in Plane Geometry by : Roman Żelazny

Download or read book Two-group Approach in Neutron Transport Theory in Plane Geometry written by Roman Żelazny and published by . This book was released on 1961 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

An Introduction to Neutron Transport Theory

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Publisher :
ISBN 13 :
Total Pages : 164 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis An Introduction to Neutron Transport Theory by : J. H. Tait

Download or read book An Introduction to Neutron Transport Theory written by J. H. Tait and published by . This book was released on 1965 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Two-group Appoach in Neutron Transport Theory in Plane Geometry

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Publisher :
ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (968 download)

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Book Synopsis Two-group Appoach in Neutron Transport Theory in Plane Geometry by : Roman Stanisław Żelazny

Download or read book Two-group Appoach in Neutron Transport Theory in Plane Geometry written by Roman Stanisław Żelazny and published by . This book was released on 1961 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Multi-group Neutron Transport Theory in Plane Geometry

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Publisher :
ISBN 13 :
Total Pages : 272 pages
Book Rating : 4.:/5 (27 download)

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Book Synopsis Multi-group Neutron Transport Theory in Plane Geometry by : Frank Joseph McCrosson

Download or read book Multi-group Neutron Transport Theory in Plane Geometry written by Frank Joseph McCrosson and published by . This book was released on 1968 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Neutron Transport in a Spherical Subcritical Assembly with an External Neutron Source

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ISBN 13 :
Total Pages : 103 pages
Book Rating : 4.:/5 (227 download)

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Book Synopsis Neutron Transport in a Spherical Subcritical Assembly with an External Neutron Source by : Frederick C. Damm

Download or read book Neutron Transport in a Spherical Subcritical Assembly with an External Neutron Source written by Frederick C. Damm and published by . This book was released on 1969 with total page 103 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron transport theory was used to predict resulting neutron distributions from an external neutron source in a spherical subcritical fissile assembly. A plane wave-delta function neutron source in time was assumed incident on the sphere containing fissionable material. Two methods of three-group calculations in r, theta spherical geometry were used. A time-space integrated diffusion equation was solved for fluence (nvt) as a function of energy and position. Secondly, the Boltzmann equation was solved by the discrete ordinates S sub n method. Computer codes for both methods were written in Fortran IV for the IBM 7094 computer. In a sphere 14 cm in diameter, composed of U-235 and aluminum, fission buildup from a fission spectrum source resulted in a total increase in neutron population of three times the source strength. A comparison of the results of the two methods is presented. (Author).

Numerical Solution of Transient and Steady-state Neutron Transport Problems

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Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Numerical Solution of Transient and Steady-state Neutron Transport Problems by : Bengt G. Carlson

Download or read book Numerical Solution of Transient and Steady-state Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1959 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations

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Publisher : Universal-Publishers
ISBN 13 : 1599423960
Total Pages : 161 pages
Book Rating : 4.5/5 (994 download)

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Book Synopsis New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations by : Jacques Tagoudjeu

Download or read book New Splitting Iterative Methods for Solving Multidimensional Neutron Transport Equations written by Jacques Tagoudjeu and published by Universal-Publishers. This book was released on 2011-04 with total page 161 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis focuses on iterative methods for the treatment of the steady state neutron transport equation in slab geometry, bounded convex domain of Rn (n = 2,3) and in 1-D spherical geometry. We introduce a generic Alternate Direction Implicit (ADI)-like iterative method based on positive definite and m-accretive splitting (PAS) for linear operator equations with operators admitting such splitting. This method converges unconditionally and its SOR acceleration yields convergence results similar to those obtained in presence of finite dimensional systems with matrices possessing the Young property A. The proposed methods are illustrated by a numerical example in which an integro-differential problem of transport theory is considered. In the particular case where the positive definite part of the linear equation operator is self-adjoint, an upper bound for the contraction factor of the iterative method, which depends solely on the spectrum of the self-adjoint part is derived. As such, this method has been successfully applied to the neutron transport equation in slab and 2-D cartesian geometry and in 1-D spherical geometry. The self-adjoint and m-accretive splitting leads to a fixed point problem where the operator is a 2 by 2 matrix of operators. An infinite dimensional adaptation of minimal residual and preconditioned minimal residual algorithms using Gauss-Seidel, symmetric Gauss-Seidel and polynomial preconditioning are then applied to solve the matrix operator equation. Theoretical analysis shows that the methods converge unconditionally and upper bounds of the rate of residual decreasing which depend solely on the spectrum of the self-adjoint part of the operator are derived. The convergence of theses solvers is illustrated numerically on a sample neutron transport problem in 2-D geometry. Various test cases, including pure scattering and optically thick domains are considered.

Nuclear Science Abstracts

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Publisher :
ISBN 13 :
Total Pages : 612 pages
Book Rating : 4.E/5 ( download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:

New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry

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Publisher :
ISBN 13 :
Total Pages : 100 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry by : Walter Kofink

Download or read book New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry written by Walter Kofink and published by . This book was released on 1961 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Bibliography on Neutral Particle Transport Theory

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ISBN 13 :
Total Pages : 188 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Bibliography on Neutral Particle Transport Theory by :

Download or read book Bibliography on Neutral Particle Transport Theory written by and published by . This book was released on 1970 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Numerical Studies of the Diffusion-transport Approximation

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ISBN 13 :
Total Pages : 192 pages
Book Rating : 4.:/5 (989 download)

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Book Synopsis Numerical Studies of the Diffusion-transport Approximation by : Arnold J. Sisk

Download or read book Numerical Studies of the Diffusion-transport Approximation written by Arnold J. Sisk and published by . This book was released on 1968 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt: Detailed reactor design calculations are routinely performed using group diffusion theory as the computational method for obtaining the neutron flux distribution. Diffusion theory, however, yields an adequate approximation to the correct neutron distribution only for limited situations which are not common in modern high performance reactors. The difficulty can be circumvented, in principle, by using neutron transport theory, but this alternative is not practical because of the complexity of the Boltzmann transport equation for neutrons. The Diffusion-Transport Approximation is a technique which uses two diffusion-type equations: a standard asymptotic equation and a correction equation which introduces the space transients of transport theory into the solution. The approximation yields excellent results in simple situations. The equations and the boundary conditions associated with them have been numerically analyzed and made amenable to computer solution by the line inversion technique, in the hope of developing a useful reactor design tool. This technique involves what is known as a forward elimination-bac kward substitution process. A program which is applicable to plane, cylindrical or spherical geometry has been written and has given excellent results for plane geometry situations. It was then tested on two problems in cylindrical geometry; these situations are considered much more representative of actual reactor design problems. It appears that the approximation gives results which are somewhat better than F-1 diffusion theory for regions which are not too small. However, the approximation failed for small regions. It is concluded that the parameters used in the theory need to be recalculated for cases involving cylindrical geometry. The numerical analysis and programming could then be tested on more complex multiregion problems in this geometry with the hope that a good approximation to the actual neutron flux will result.

Numerical Formulation and Solution of Neutron Transport Problems

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Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Numerical Formulation and Solution of Neutron Transport Problems by : Bengt G. Carlson

Download or read book Numerical Formulation and Solution of Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation

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Publisher :
ISBN 13 :
Total Pages : 598 pages
Book Rating : 4.:/5 (97 download)

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Book Synopsis Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation by : Mahendra Prinath Dias

Download or read book Variational Solutions to the Neutron Transport Equation in P[subscript N] Approximation written by Mahendra Prinath Dias and published by . This book was released on 1982 with total page 598 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Studies of the Spherical Harmonics Method in Neutron Transport Theory

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Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Studies of the Spherical Harmonics Method in Neutron Transport Theory by : Walter Kofink

Download or read book Studies of the Spherical Harmonics Method in Neutron Transport Theory written by Walter Kofink and published by . This book was released on 1960 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Reactor Handbook: Physics

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ISBN 13 :
Total Pages : 810 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis The Reactor Handbook: Physics by :

Download or read book The Reactor Handbook: Physics written by and published by . This book was released on 1955 with total page 810 pages. Available in PDF, EPUB and Kindle. Book excerpt: