Download or read book Solution of the Few group Neutron Diffusion Equations written by Charles Sheppard Henkel and published by . This book was released on 1995 with total page 262 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Twenty Grand Program for the Numerical Solution of Few group Neutron Diffusion Equations in Two Dimensions written by M. L. Tobias and published by . This book was released on 1962 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NESTLE written by and published by . This book was released on 1994 with total page 147 pages. Available in PDF, EPUB and Kindle. Book excerpt: NESTLE is a FORTRAN77 code that solves the few-group neutron diffusion equation utilizing the Nodal Expansion Method (NEM). NESTLE can solve the eigenvalue (criticality); eigenvalue adjoint; external fixed-source steady-state; or external fixed-source. or eigenvalue initiated transient problems. The code name NESTLE originates from the multi-problem solution capability, abbreviating Nodal Eigenvalue, Steady-state, Transient, Le core Evaluator. The eigenvalue problem allows criticality searches to be completed, and the external fixed-source steady-state problem can search to achieve a specified power level. Transient problems model delayed neutrons via precursor groups. Several core properties can be input as time dependent. Two or four energy groups can be utilized, with all energy groups being thermal groups (i.e. upscatter exits) if desired. Core geometries modelled include Cartesian and Hexagonal. Three, two and one dimensional models can be utilized with various symmetries. The non-linear iterative strategy associated with the NEM method is employed. An advantage of the non-linear iterative strategy is that NSTLE can be utilized to solve either the nodal or Finite Difference Method representation of the few-group neutron diffusion equation.
Download or read book Equations and Programs for Solutions of the Neutron Group Diffusion Equations by Synthesis Approximations written by S. Kaplan and published by . This book was released on 1963 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
Download or read book Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this thesis two unrelated topics of reactor physics are examined: the prompt jump approximation and alternating direction checkerboard methods. In the prompt jump approximation it is assumed that the prompt and delayed neutrons in a nuclear reactor may be described mathematically as being instantaneously in equilibrium with each other. This approximation is applied to the spatially dependent neutron diffusion theory reactor kinetics model. Alternating direction checkerboard methods are a family of finite difference alternating direction methods which may be used to solve the multigroup, multidimension, time-dependent neutron diffusion equations. The reactor mesh grid is not swept line by line or point by point as in implicit or explicit alternating direction methods; instead, the reactor mesh grid may be thought of as a checkerboard in which all the ''red squares'' and '' black squares'' are treated successively. Two members of this family of methods, the ADC and NSADC methods, are at least as good as other alternating direction methods. It has been found that the accuracy of implicit and explicit alternating direction methods can be greatly improved by the application of an exponential transformation. This transformation is incompatible with checkerboard methods. Therefore, a new formulation of the exponential transformation has been developed which is compatible with checkerboard methods and at least as good as the former transformation for other alternating direction methods. (auth).
Download or read book STREAK a Numerical Solution for Space time Neutron Diffusion Equations written by James W. Smiley and published by . This book was released on 1966 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PDQ written by Gerald G. Bilodeau and published by . This book was released on 1957 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The KAK program for the numerical solution of few group neutron diffusion equations in two dimensions written by Nihon Genshiryoku Kenkyūjo and published by . This book was released on 1966 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Development of Parallel Numerical Algorithms for the Solution of the Few group Neutron Diffusion Equations Using Coarse Grain Parallel Algorithms written by Hisham Naji Sarsour and published by . This book was released on 1991 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 216 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.
Download or read book The Twenty Grand Program for the Numerical Solution of Few Group Neutron Diffusion Equations in Two Dimensions written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylindrical or slab geometry for one to six groups. Up to 3000 mesh points may be used. Neutron transfer from any group to any other group is permitted. Leakage in the third dimension in X-Y geometry may be treated by a buckling which can vary with region and group. Three types of symmetry conditions may be handled automatically. The zero flux, zero derivative, and logarithmic boundary conditions are available. Normalization of fluxes to an arbitrary input power is allowed. The fission source distribution and the adjoint fluxes and associated integrals may be computed at the user's option. The number of mesh sweeps permitted is stated as input. The average running time in seconds per iteration per group is approximately 0.0035. (auth).
Download or read book Finite Difference Solution of the Time Dependent Neutron Group Diffusion Equations written by John Stanley Hendricks and published by . This book was released on 1975 with total page 550 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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."
Download or read book Solution of the Multi group Neutron Diffusion Equations on a Digital Computer written by A. Hassitt and published by . This book was released on 1956 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A New Transverse Leakage Approximation for the Nodal Solution of the Steady state Multi group Neutron Diffusion Equations written by Qi Deng and published by . This book was released on 2001 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nonlinear Methods for Solving the Diffusion Equation written by Robert Anthony Shober and published by . This book was released on 1976 with total page 318 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis is concerned with methods for the transient solution of the neutron diffusion equations in one or two energy groups. Initially, nonlinear methods for solving the static diffusion equations using the finite element method were investigated. By formulating a new eigenvalue equation, some improvement in the solution efficiency was obtained. However, the transient solution of the diffusion equation using the finite element method was considered to be overly expensive. An analytic method for solving the one-dimensional diffusion equation was then developed. Numerical examples confirmed that this method is exact in one dimension. The method was extended to two dimensions, and results compared employing two different approximations for the transverse leakage. The method based on a flat approximation to the leakage was found to be superior, and it was extended to time-dependent problems. Results of time-dependent test problems show the procedure to be accurate and efficient. Comparisons with conventional finite difference techniques (such as TWIGL or MEKIN) indicate that the scheme can be an order of magnitude more cost effective.
