Advances in Nuclear Science and Technology - 1st Edition - ISBN: 9780120293070, 9781483215648

Advances in Nuclear Science and Technology

1st Edition

Volume 7

Editors: Ernest J. Henley Jeffery Lewins
eBook ISBN: 9781483215648
Imprint: Academic Press
Published Date: 1st January 1973
Page Count: 394
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Description

Advances in Nuclear Science and Technology, Volume 7 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.

Organized into five chapters, this volume begins with an overview of irradiation-induced void swelling in austenitic stainless steels. This text then examines the importance of various transport processes for fission product redistribution, which depends on the diffusion data, the vaporization properties, and the solubility in the fuel matrix. Other chapters consider the integro-differential form of the linear transport equation, which forms the basis for the study of neutron distributions. This book discusses as well the W–H technique and its relevance in transport theory. The final chapter deals with nuclear reactor safety and describes the system in preventing thermal explosions.

This book is a valuable resource for thermal reactor physicists, industrial engineers, theoreticians, scientists, and research workers.

Table of Contents


List of Contributors


Preface


Contents of Previous Volumes


Void Formation in Irradiated Austenitic Stainless Steels


I. Introduction and Background


II. Experimental Observations


III. Theory


IV. Practical Consequences of Void Swelling


V. Recapitulation


Appendix: Austenitic Stainless Steels for LMFBR Core Service


References


Material Transport in the Temperature Gradient of Fast Reactor Fuels


I. Introduction


II. Solid State Transport


III. Gas-Phase Transport


IV. Redistribution Effects


V. Calculation of Thermal Diffusion Effects


VI. Conclusions


List of Symbols


References


Singular Eigenfunction Expansions in Neutron Transport Theory


I. Introduction


II. Transport in an Infinite Medium


III. Transport in Half-Space Media


IV. Transport in Slabs


V. Nonplane Boundaries


VI. A Comparison with Other Methods


VII. Comments


References


The Wiener-Hopf Technique: An Alternative to the Singular Eigenfunction Method


I. Introduction and Historical Background


II. The Basic Theory of the W-H Method


III. Application to the Critical Problem


IV. Applications to Spherical and Cylindrical Systems


V. Applications to Rectangular Systems


VI. Energy-Dependent Problems


VII. Time-Dependent Problems


VIII. Concluding Remarks


References


Bibliography


Thermal Explosion Hazards


I. Introduction


II. Explosive Vapor Formation Incidents


III. Early Controlled Experiments


IV. Recent Fragmentation Investigations


V. Identificati

Details

No. of pages:
394
Language:
English
Copyright:
© Academic Press 1973
Published:
Imprint:
Academic Press
eBook ISBN:
9781483215648

About the Editor

Ernest J. Henley

Jeffery Lewins

Ratings and Reviews