The DSN and TDC Neutron Transport Codes


Book Description

This report describes two reactor codes, one for the one-dimensional geometries (DSN) and the other for the finite cylindrical case (TDC), based on the transport difference equations and calculation methods developed in "Numerical Solutions of Transient and Steady State Neutron Transport Problems" (LA-2260). Appendices I and II, which contain the actual machine codes, have been separated from the descriptive part of the report to make it easier for the user to study the material and apply it to problems.




Numerical Solution of Ordinary and Partial Differential Equations


Book Description

Numerical Solution of Ordinary and Partial Differential Equations is based on a summer school held in Oxford in August-September 1961. The book is organized into four parts. The first three cover the numerical solution of ordinary differential equations, integral equations, and partial differential equations of quasi-linear form. Most of the techniques are evaluated from the standpoints of accuracy, convergence, and stability (in the various senses of these terms) as well as ease of coding and convenience of machine computation. The last part, on practical problems, uses and develops the techniques for the treatment of problems of the greatest difficulty and complexity, which tax not only the best machines but also the best brains. This book was written for scientists who have problems to solve, and who want to know what methods exist, why and in what circumstances some are better than others, and how to adapt and develop techniques for new problems. The budding numerical analyst should also benefit from this book, and should find some topics for valuable research. The first three parts, in fact, could be used not only by practical men but also by students, though a preliminary elementary course would assist the reading.




Proceedings


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Argonne Code Center


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Advances in Nuclear Science and Technology


Book Description

Advances in Nuclear Science and Technology, Volume 2 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book discusses the advances in the atomic energy field. Organized into six chapters, this volume begins with an overview of the concept of transfer function of a system. This text then examines the classic plant cycles for the water-cooled, liquid metal, and gas-cooled reactor concepts to pinpoint those points in cycle that require nuclear grade heat exchanger equipment. Other chapters consider heat exchanger, which is applied to the full spectrum of apparatus and equipment designed to facilitate the flow of heat from medium to medium. This book discusses as well the hardware characteristics and the resulting effects on reactor calculations. The final chapter deals with the effect of digital computers on nuclear reactor calculations and discusses some of the numerical methods used in nuclear reactor codes. This book is a valuable resource for design engineers and plant operating personnel.




Reactor Physics Constants


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AGN-TM


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