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.
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.
This report describes a code, the TOP code, designed to perform finite cylinder neutron tranport theory calculations from a general input tape prepared by other calculations. The transport theory is based upon the difference equations and calculational methods developed in "Numerical Methods for Solving Transient and Steady State Neutron Transport Problems" (LA-2260) and "The DSN and TDC Neutron Transport Codes" (LAMS-2346).
The survey articles included in Volume 5 have been selected with two aims in mind: to arrive at a balanced sampling of the computer field, and to emphasize the subjects of most active current interest. Articles cover topics such as the role of computers in delivering election results; the state of computer development in the Soviet Union and its neighbors; artificial intelligence; and applications of computers to the design of optical instruments, to nuclear reactor design, and to the determination of the structure of crystals or molecules from X-ray diffraction patterns.
The need has arisen for a comprehensive handbook for engineers faced with problems of radiation shielding design. Although there are several excellent books on shielding, they either do not give enough consideration to the many practical design problems, or are limited to special aspects of the subject. Recognizing the universal need, the International Atomic Energy Agency decided to sponsor the publication ofthe present Engineering Compendium on Radiation Shield ing. At the first editorial discussions it was agreed that, if such a book were to be undertaken, it would be appropriate not only to create a useful design tool for the practising engineer but also to include well-referenced basic data for the research worker. Although trying to keep the book down to a reasonable size, the editors have aimed at a complete presentation of the subject, covering and linking both the tech nology and the science of shielding. Efforts to make terms and definitions consistent throughout have been only partially successful, owing to the continuing development of new ideas. However, inconsisten cies that could not be eliminated are identified whenever possible.
