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Book Development of a Nodal Method for the Solution of the Neutron Diffusion Equation in General Cylindrical Geometry

Download or read book Development of a Nodal Method for the Solution of the Neutron Diffusion Equation in General Cylindrical Geometry written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The usual strategy for solving the neutron diffusion equation in two or three dimensions by nodal methods is to reduce the multidimensional partial differential equation to a set of ordinary differential equations (ODEs) in the separate spatial coordinates. This reduction is accomplished by "transverse integration" of the equation.1 For example, in three-dimensional Cartesian coordinates, the three-dimensional equation is first integrated over x and y to obtain an ODE in z, then over x and z to obtain an ODE in y, and finally over y and z to obtain an ODE in x. Then the ODEs are solved to obtain onedimensional solutions for the neutron fluxes averaged over the other two dimensions. These solutions are found in regions ("nodes") small enough for the material properties and cross sections in them to be adequately represented by average values. Because the solution in each node is an exact analytical solution, the nodes can be much larger than the mesh elements used in finite-difference solutions. Then the solutions in the different nodes are coupled by applying interface conditions, ultimately fixing the solutions to the external boundary conditions.

Book A Nodal Integral Method for the Neutron Diffusion Equation in Cylindrical Geometry

Download or read book A Nodal Integral Method for the Neutron Diffusion Equation in Cylindrical Geometry written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This Summary reports recent progress in deriving and numerically implementing a nodal integral method (NIM) for solving the neutron diffusion equation in cylindrical, r-z, geometry. Comparisons of numerical solutions to two test problems with those obtained by the code EXTERMINATOR-2 indicate the superior accuracy of the nodal integral method solutions on much coarser meshes. 6 refs., 1 fig., 1 tab.

Book Nuclear Science Abstracts

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:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1990 with total page 852 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Handbook of Nuclear Engineering

Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book ERDA Energy Research Abstracts

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1977 with total page 776 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Finite Difference Approximations to the Neutron Diffusion Equation

Download or read book Finite Difference Approximations to the Neutron Diffusion Equation written by H. P. Flatt and published by . This book was released on 1960 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: The finite difference approximations used in several one-dimensional neutron diffusion codes are studied from the point of view of conservation of neutrons. A new set of approximation formulae is proposed which conserve neutrons. These formulae differ only slightly from earlier formulae, thus allowing a small effect to be corrected by a small amount of effort."

Book Transactions of the American Nuclear Society

Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 2002 with total page 1096 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Neutron Diffusion

    Book Details:
  • Author : S. Chakraverty
  • Publisher : CRC Press
  • Release : 2017-04-21
  • ISBN : 1351667513
  • Pages : 184 pages

Download or read book Neutron Diffusion written by S. Chakraverty and published by CRC Press. This book was released on 2017-04-21 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is designed for a systematic understanding of nuclear diffusion theory along with fuzzy/interval/stochastic uncertainty. This will serve to be a benchmark book for graduate & postgraduate students, teachers, engineers and researchers throughout the globe. In view of the recent developments in nuclear engineering, it is important to study the basic concepts of this field along with the diffusion processes for nuclear reactor design. Also, it is known that uncertainty is a must in every field of engineering and science and, in particular, with regards to nuclear-related problems. As such, one may need to understand the nuclear diffusion principles/theories corresponding with reliable and efficient techniques for the solution of such uncertain problems. Accordingly this book aims to provide a new direction for readers with basic concepts of reactor physics as well as neutron diffusion theory. On the other hand, it also includes uncertainty (in terms of fuzzy, interval, stochastic) and their applications in nuclear diffusion problems in a systematic manner, along with recent developments. The underlying concepts of the presented methods in this book may very well be used/extended to various other engineering disciplines viz. electronics, marine, chemical, mining engineering and other sciences such as physics, chemistry, biotechnology etc. This book then can be widely applied wherever one wants to model their physical problems in terms of non-probabilistic methods viz. fuzzy/stochastic for the true essence of the real problems.

Book Nodal Method for Three dimensional Fast reactor Calculations in Hexagonal Geometry   LMFBR

Download or read book Nodal Method for Three dimensional Fast reactor Calculations in Hexagonal Geometry LMFBR written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A nodal method is developed for the solution of the multigroup neutron-diffusion equation in three-dimensional hexagonal-z geometry. The method employs an extension to hexagonal geometry of the transverse-integration procedure used extensively in the development of nodal schemes in Cartesian geometry. The partially-integrated fluxes in the three hex-plane directions are approximated by a polynomial tailored to the unique properties of the transverse-integrated equations in hexagonal geometry. The final equations, which are cast in the form of local inhomogeneous response matrix equations for each energy group, involve spatial moments of the node-interior flux distribution plus surface-averaged partial currents across the faces of the node.

Book Geometry independent Approach to Coarse mesh Neutron Diffusion Calculations

Download or read book Geometry independent Approach to Coarse mesh Neutron Diffusion Calculations written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Powerful coarse-mesh and nodal methods have been recently developed to calculate accurate node-average fluxes and eigenvalues. The nodal methods solve for the node-average flux by reducing the multidimensional diffusion problem to a coupled system of 1-D equations. These schemes are mainly limited to rectangular (xyz) nodes and cannot easily be extended to other geometries. The polynomial-based coarse-mesh methods have been applied to thetaRZ and HEXZ geometries. This summary describes the development of a boundary coarse-mesh nodal method applicable to arbitrary geometries using the boundary integral technique coupled with nodal source expansion.

Book An Investigation of Certain Aspects of the Nodal Expansion Method for the Solution of the Neutron Diffusion Equation

Download or read book An Investigation of Certain Aspects of the Nodal Expansion Method for the Solution of the Neutron Diffusion Equation written by Beryl Rene Davies and published by . This book was released on 1988 with total page 288 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Finite Element Bibliography

Download or read book Finite Element Bibliography written by Gerard De Vries and published by Springer. This book was released on 1976-12 with total page 706 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thjs bibliography had its inception in 1967, when the compilers first attempted a comprehensive cov erage of the finite element literature using both manual and computer-based retrieval. Initially, the data base was stored on a card index, but this was subsequently transferred to punched cards and magnetic tape. Computer processing was adopted at an early stage to derive the three index formats from the data base. Over the subsequent years, several versions of the bibliography were produced, with two of these being made available in a report form to other researchers. From the widespread interest in these documents, it became evident that there was a need for a commercially-available comprehensive bibliography in this area. A major effort was undertaken to revise, update, and extend the data base, resulting in this present volume. The bibliography covers the period 1956-1975 primarily, although some earlier publications of histori cal interest are included. The citations are not restricted to the English language and documents are listed in many languages and from diverse places of origin. All publication formats were accepted, so that references will be found to books, monographs, journal papers and articles, theses, dissertations, reports, surveys, and the like.