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The Dsn And Tdc Neutron Transport Codes

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The Dsn And Tdc Neutron Transport Codes

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Author : B. Carlson
language : en
Publisher:
Release Date : 1960

The Dsn And Tdc Neutron Transport Codes written by B. Carlson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Neutron transport theory categories.

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.

The Dsn And Tdc Neutron Transport Codes

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Author : B. Carlson
language : en
Publisher:
Release Date : 1960

Engineering Compendium On Radiation Shielding

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Author : International Atomic Energy Agency
language : en
Publisher: Springer Science & Business Media
Release Date : 2013-06-29

Engineering Compendium On Radiation Shielding written by International Atomic Energy Agency and has been published by Springer Science & Business Media this book supported file pdf, txt, epub, kindle and other format this book has been release on 2013-06-29 with Science categories.

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.

Ornl

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Author :
language : en
Publisher:
Release Date : 1964

Ornl written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1964 with Nuclear energy categories.

Argonne Code Center

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Author :
language : en
Publisher:
Release Date : 1977

Argonne Code Center written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1977 with Computer programs categories.

Reactivity And Neutron Flux Distribution Studies In Multi Region Loaded Reactor Cores

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Author : W. J. Eich
language : en
Publisher:
Release Date : 1961

Reactivity And Neutron Flux Distribution Studies In Multi Region Loaded Reactor Cores written by W. J. Eich and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Neutron flux categories.