Advances in Nuclear Science and Technology
Volume 8
- 1st Edition - September 20, 2014
- Editors: Ernest J. Henley, Jeffery Lewins
- Language: English
- Paperback ISBN:9 7 8 - 1 - 4 8 3 2 - 0 2 2 2 - 8
- eBook ISBN:9 7 8 - 1 - 4 8 3 2 - 1 5 6 5 - 5
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… Read more
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.
Contributors
Preface
Contents of Previous Volumes
Quasi-Exponential Decay of Neutron Fields
I. Introduction
II. Exponential and Quasi-Exponential Behavior
III. Experiments
IV. Theory
V. Epilogue
References
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
References
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
References
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
References
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
Appendix—Nomenclature
References
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
References
Subject Index
- Edition: 1
- Published: September 20, 2014
- Language: English
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