Advances in Nuclear Science and Technology

Advances in Nuclear Science and Technology

Volume 8

1st Edition - January 1, 1975

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  • Editors: Ernest J. Henley, Jeffery Lewins
  • eBook ISBN: 9781483215655

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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

  • Contributors


    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

Product details

  • No. of pages: 364
  • Language: English
  • Copyright: © Academic Press 1975
  • Published: January 1, 1975
  • Imprint: Academic Press
  • eBook ISBN: 9781483215655

About the Editors

Ernest J. Henley

Jeffery Lewins

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