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.

ContributorsPrefaceContents of Previous VolumesQuasi-Exponential Decay of Neutron Fields I. Introduction II. Exponential and Quasi-Exponential Behavior III. Experiments IV. Theory V. Epilogue ReferencesEvaluation 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 ReferencesEvaluated 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 ReferencesThe 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 ReferencesFinite 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 Appendix-Nomenclature ReferencesCoated 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 ReferencesSubject Index