Advances in Nuclear Science and Technology - 1st Edition - ISBN: 9780120293063, 9781483215631

Advances in Nuclear Science and Technology

1st Edition

Volume 6

Editors: Ernest J. Henley Jeffery Lewins
eBook ISBN: 9781483215631
Imprint: Academic Press
Published Date: 1st January 1972
Page Count: 254
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Description

Advances in Nuclear Science and Technology, Volume 6 provides information pertinent to the fundamental aspects of nuclear science and technology. This book covers a variety of topics, including nuclear steam generator, oscillations, fast reactor fuel, gas centrifuge, thermal transport system, and fuel cycle.

Organized into six chapters, this volume begins with an overview of the high standards of technical safety for Europe's first nuclear-propelled merchant ship. This text then examines the state of knowledge concerning qualitative results on the behavior of the solutions of the nonlinear point kinetics equations with linear feedback. Other chapters consider the mathematical methods used in the calculations and outline the main features peculiar to fast systems. This book discusses as well the thermal transport in reactors. The final chapter deals with the status of nuclear energy in Western Europe, which depends on the development and introduction of reactor types that make a better use of the nuclear resources.

This book is a valuable resource for reactor physicists.

Table of Contents


Contributors


Preface


Contents of Previous Volumes


The Core Design of the Reactor for the Nuclear Ship “Otto Hahn”


Introduction


I. General Design Aspects


II. Description of the Nuclear Steam Generator FDR


III. Most Significant Nuclear and Thermal Data of Operation


IV. Methods of Calculation


V. Zero Power Experiments


VI. Operational Experience


VII. Layout of the Second Core


VIII. Concluding Remarks


References


Stability Analysis of Nonlinear Point Reactor Kinetics


I. Introduction


II. Existence of Solutions


III. Asymptotic Stability in the Large


IV. Boundedness Criteria


V. Limited Perturbations


VI. Role of Delayed Neutrons


VII. Oscillations


VIII. Area for Research


References


The Quantitative Description of Deformation and Stress in Cylindrical Fast Reactor Fuel Pins


I. Introduction


II. Fast Reactor Fuel and Its Behavior


III. Axial Considerations


IV. The Mechanics of Creep and Swelling


V. Steady-State Calculations


VI. Transient Calculations


VII. Accommodation of Swelling


VIII. Clad Deformation and Failure


IX. Data


X. An Example


XI. Conclusions


List of Symbols


References


Technical Basis of the Gas Centrifuge


I. Introduction


II. Separative Properties of the Gas Centrifuge


III. Hydrodynamics


IV. Conclusions


Appendix. Hydrodynamic Derivation of the Maximum Separative Power of a Centrifuge


List of Symbols


References


Heat Transfer in Liquid-Metal Cooled Fast Reactors

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Details

No. of pages:
254
Language:
English
Copyright:
© Academic Press 1972
Published:
Imprint:
Academic Press
eBook ISBN:
9781483215631

About the Editor

Ernest J. Henley

Jeffery Lewins

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