Advances in Nuclear Science and Technology - 1st Edition - ISBN: 9780120293087, 9781483215655

Advances in Nuclear Science and Technology

1st Edition

Volume 8

Editors: Ernest J. Henley Jeffery Lewins
eBook ISBN: 9781483215655
Imprint: Academic Press
Published Date: 1st January 1975
Page Count: 364
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Advances in Nuclear Science and Technology, Volume 8 discusses the development of nuclear power in several countries throughout the world. This book discusses the world's largest program of land-based electricity production in the United States.

Organized into six chapters, this volume begins with an overview of the phenomenon of quasi-exponential behavior by examining two mathematical models of the neutron field. This text then discusses the finite element method, which is a method for obtaining approximate solutions to integral or differential equations. Other chapters consider the status of the accuracy of nuclear data used for reactor calculations and the target accuracies required by reactor physics. This book discusses as well the role of integral experiments for the improvement of nuclear data and the different approaches taken to enhance them. The final chapter deals with the manufacture and application of coated particles.

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

Table of Contents



Contents of Previous Volumes

Quasi-Exponential Decay of Neutron Fields

I. Introduction

II. Exponential and Quasi-Exponential Behavior

III. Experiments

IV. Theory

V. Epilogue


Evaluation of Integral Physics Experiments in Fast Zero Power Facilities

I. Introduction

II. Accuracy of Nuclear Data Used for Reactor Calculations

III. Implications of Nuclear Data Uncertainties

IV. Role of Integral Experiments in Improving the Nuclear Data Basis

V. Status of Evaluation Efforts

VI. Summary and Future Aspects


Evaluated Nuclear Data Files

I. Introduction

II. Description of Evaluated Nuclear Data Files

III. Procedures for Data Evaluation

Appendix A: Formats for Evaluated Nuclear Data Libraries

Appendix B: Checking Procedures for Evaluated Data Files


The Management of Fission Product and Long-Lived Alpha Wastes

I. Introduction

II. Magnitude of the Problem

III. Current Situation: Practices, Experience, and General Planning

IV. Solidification Techniques and Final Product Characteristics

V. Storage, Disposal, and Transportation of the Solidified Waste

VI. Economic Considerations

VII. Conclusions


Finite Element Methods in Reactor Physics Analysis

I. Introduction

II. Piecewise Polynomial Spaces

III. Neutron Spectrum Calculations

IV. Static Diffusion Problems

V. Time-Dependent Problems

VI. Summary



Coated Nuclear Fuel Particles

I. Introduction

II. High-Temperature Reactors

III. The Fuel

IV. Pyrolytic Carbon Coated Particles

V. Pyrolytic Carbon

VI. Silicon Carbide

VII. Mathematical Models

VIII. Production Equipment

IX. Coating Characteristics According to the Deposition Conditions

X. Analysis and Control of the Finished Particles

XI. Irradiation Tests


Subject Index


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© Academic Press 1975
Academic Press
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About the Editor

Ernest J. Henley

Jeffery Lewins

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