ONE-SPEED NEUTRON TRANSPORT PROBLEMS IN PLANE GEOMETRY.

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ISBN 13 :
Total Pages : 198 pages
Book Rating : 4.:/5 (682 download)

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Book Synopsis ONE-SPEED NEUTRON TRANSPORT PROBLEMS IN PLANE GEOMETRY. by : Norman J. McCormick

Download or read book ONE-SPEED NEUTRON TRANSPORT PROBLEMS IN PLANE GEOMETRY. written by Norman J. McCormick and published by . This book was released on 1965 with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:

SOLUTIONS OF THE ONE-SPEED NEUTRON TRANSPORT EQUATION IN PLANE GEOMETRY.

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ISBN 13 :
Total Pages : 219 pages
Book Rating : 4.:/5 (682 download)

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Book Synopsis SOLUTIONS OF THE ONE-SPEED NEUTRON TRANSPORT EQUATION IN PLANE GEOMETRY. by : MAX RICHARD MENDELSON

Download or read book SOLUTIONS OF THE ONE-SPEED NEUTRON TRANSPORT EQUATION IN PLANE GEOMETRY. written by MAX RICHARD MENDELSON and published by . This book was released on 1964 with total page 219 pages. Available in PDF, EPUB and Kindle. Book excerpt:

one-spred neutron transport problems in plane geometry

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ISBN 13 :
Total Pages : 206 pages
Book Rating : 4.L/5 ( download)

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Book Synopsis one-spred neutron transport problems in plane geometry by : norman j. mccormic

Download or read book one-spred neutron transport problems in plane geometry written by norman j. mccormic and published by . This book was released on 1965 with total page 206 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.

Energy-dependent Neutron Transport Theory in Plane Geometry. Iii. Half-range Completeness and Half-space Problems

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ISBN 13 :
Total Pages : 35 pages
Book Rating : 4.:/5 (227 download)

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Book Synopsis Energy-dependent Neutron Transport Theory in Plane Geometry. Iii. Half-range Completeness and Half-space Problems by : A. Leonard

Download or read book Energy-dependent Neutron Transport Theory in Plane Geometry. Iii. Half-range Completeness and Half-space Problems written by A. Leonard and published by . This book was released on 1965 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt: A set of elementary solutions to the energy-dependent Boltzmann equation, which was derived in an earlier paper, is shown to possess a half-range completeness property allowing the exact solution to energy-dependent half-space problems and the reduction of finiteslab problems to rapidly convergent Fredholm equations. Results follow in analogy with Case's work on the one-velocity transport equation except that a system of singular integral equations is encountered, giving rise to the Hilbert problems for matrices. It is shown that the methods of Muskhelishvili and Vekua are applicable to this matrix problem and lead to the consideration of a class of Fredholm equations to obtain the solution. The explicit form the Fredholm equation for the present problem is derived by extending the analysis of the scalar Hilbert problem to the matrix case. Applications of the completeness proof are made to the albedo and Milne problems for a half-space. (Author).

An Introduction to Neutron Transport Theory

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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:

solutions of the two-group transport equation in plane geometry

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ISBN 13 :
Total Pages : 144 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis solutions of the two-group transport equation in plane geometry by : dale r. ketcalr, paul f. zweifel

Download or read book solutions of the two-group transport equation in plane geometry written by dale r. ketcalr, paul f. zweifel and published by . This book was released on 1968 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Half-Space Multigroup Transport Theory In Plane Geometry

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ISBN 13 :
Total Pages : 142 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Half-Space Multigroup Transport Theory In Plane Geometry by : John K. Shultis

Download or read book Half-Space Multigroup Transport Theory In Plane Geometry written by John K. Shultis and published by . This book was released on 1968 with total page 142 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 1216 pages
Book Rating : 4.0/5 ( 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 1976-06 with total page 1216 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Numerical Solution of Transient and Steady-state Neutron Transport Problems

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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:

Solution of an Initial-value Problem in Linear Transport Theory

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ISBN 13 :
Total Pages : 122 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis Solution of an Initial-value Problem in Linear Transport Theory by : Perry A. Newman

Download or read book Solution of an Initial-value Problem in Linear Transport Theory written by Perry A. Newman and published by . This book was released on 1971 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 reflector are presented. These eigenvalues are finite in number and may disappear into the branch cut or continuum as the material properties are varied; such disappearing eigenvalues correspond to exponentially time-decaying modes. The two largest eigenvalues can be compared with critical dimensions of slabs and spheres, and the numerical values are shown to agree with the critically results of others. In the limit of purely absorbing reflectors or a bare slab, the present solution has the same properties as have been previously reported by others who used the approach of Lehner and Wing.

Nuclear Reaction Data And Nuclear Reactors - Physics, Design And Safety: Proceedings Of The Workshop

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Publisher : World Scientific
ISBN 13 : 9814543675
Total Pages : 550 pages
Book Rating : 4.8/5 (145 download)

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Book Synopsis Nuclear Reaction Data And Nuclear Reactors - Physics, Design And Safety: Proceedings Of The Workshop by : Pavol Oblozinsky

Download or read book Nuclear Reaction Data And Nuclear Reactors - Physics, Design And Safety: Proceedings Of The Workshop written by Pavol Oblozinsky and published by World Scientific. This book was released on 1999-07-22 with total page 550 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume provides the up-to-date information behind nuclear reactor calculations, focusing on a key role of nuclear reaction data, down to the physics of nuclear interactions. It is divided into three parts. Part 1 deals with nuclear reaction models, including neutron resonances, fission, the optical model, statistical and preequilibrium models as well as nuclear level densities. Part 2 is devoted to nuclear data filling and processing; it includes lectures on nuclear data evaluation and formatting, data libraries and services, with emphasis on nuclear-data-processing codes. Part 3 presents applications in nuclear reactor calculations, emphasizing physics, design and safety.

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:

NBS Special Publication

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ISBN 13 :
Total Pages : 726 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis NBS Special Publication by :

Download or read book NBS Special Publication written by and published by . This book was released on 1977 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Transport-corrected Boundary Conditions for Neutron Diffusion Calculations

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ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Transport-corrected Boundary Conditions for Neutron Diffusion Calculations by : R. J. Doyas

Download or read book Transport-corrected Boundary Conditions for Neutron Diffusion Calculations written by R. J. Doyas and published by . This book was released on 1968 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Energy-dependent Neutron Transport Theory in Plane Geometry. Ii. Eigenfunctions and Full-range Completeness

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ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.:/5 (227 download)

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Book Synopsis Energy-dependent Neutron Transport Theory in Plane Geometry. Ii. Eigenfunctions and Full-range Completeness by : A. LEONARD

Download or read book Energy-dependent Neutron Transport Theory in Plane Geometry. Ii. Eigenfunctions and Full-range Completeness written by A. LEONARD and published by . This book was released on 1965 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: An earlier treatment of the energy-dependent transport equation is extended to include the case in which cross sections are functions of energy. The technique again consists of finding solutions to the homogeneous transport equation after expanding in terms of a complete set of functions in the energy variable. The full-range completeness theorem for these eigenfunctions requires the solution of a coupled set of singular integral equations. This solution is effected by a generalization of a trick used by Case and is applied to the problem for the infinite medium Green's function. Numerical results are given for a heavy gas model. The half-range completeness theorem, which may be applied to half-space and finite slab problems, is proven in a companion paper. (Author).

NASA Technical Report

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Publisher :
ISBN 13 :
Total Pages : 272 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis NASA Technical Report by :

Download or read book NASA Technical Report written by and published by . This book was released on 1971 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt: