Advances in Nuclear Science and Technology
Volume 6
Published on 9. May 2014
254 pages
978-1-4832-1563-1 (ISBN)
Description
Advances in Nuclear Science and Technology, Volume 6 provides information pertinent to the fundamental aspects of nuclear science and technology. This book covers a variety of topics, including nuclear steam generator, oscillations, fast reactor fuel, gas centrifuge, thermal transport system, and fuel cycle. Organized into six chapters, this volume begins with an overview of the high standards of technical safety for Europe's first nuclear-propelled merchant ship. This text then examines the state of knowledge concerning qualitative results on the behavior of the solutions of the nonlinear point kinetics equations with linear feedback. Other chapters consider the mathematical methods used in the calculations and outline the main features peculiar to fast systems. This book discusses as well the thermal transport in reactors. The final chapter deals with the status of nuclear energy in Western Europe, which depends on the development and introduction of reactor types that make a better use of the nuclear resources. This book is a valuable resource for reactor physicists.
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Ernest J. Henley | Jeffery Lewins
Advances in Nuclear Science and Technology: v. 6
Book
07/1972
Academic Press
€86.66
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Content
ContributorsPrefaceContents of Previous VolumesThe Core Design of the Reactor for the Nuclear Ship "Otto Hahn Introduction I. General Design Aspects II. Description of the Nuclear Steam Generator FDR III. Most Significant Nuclear and Thermal Data of Operation IV. Methods of Calculation V. Zero Power Experiments VI. Operational Experience VII. Layout of the Second Core VIII. Concluding Remarks ReferencesStability Analysis of Nonlinear Point Reactor Kinetics I. Introduction II. Existence of Solutions III. Asymptotic Stability in the Large IV. Boundedness Criteria V. Limited Perturbations VI. Role of Delayed Neutrons VII. Oscillations VIII. Area for Research ReferencesThe Quantitative Description of Deformation and Stress in Cylindrical Fast Reactor Fuel Pins I. Introduction II. Fast Reactor Fuel and Its Behavior III. Axial Considerations IV. The Mechanics of Creep and Swelling V. Steady-State Calculations VI. Transient Calculations VII. Accommodation of Swelling VIII. Clad Deformation and Failure IX. Data X. An Example XI. Conclusions List of Symbols ReferencesTechnical Basis of the Gas Centrifuge I. Introduction II. Separative Properties of the Gas Centrifuge III. Hydrodynamics IV. Conclusions Appendix. Hydrodynamic Derivation of the Maximum Separative Power of a Centrifuge List of Symbols ReferencesHeat Transfer in Liquid-Metal Cooled Fast Reactors I. Introduction II. Thermal Analysis and Core Design Considerations III. Heat Transfer Design Limitations IV. Fuel Pin Performance Models V. Hot-Channel Factors VI. Spatial and Burnup Effects on Fuel Pin Temperature Profile VII. Safety-Related Heat Transfer Considerations VIII. Thermal Transport System ReferencesThe Impact of Fuel Cycle Economics on the Future Development of Nuclear Power I. Introduction II. Physical Properties of Various Reactor Types III. Relative Importance of the Fuel Cycle IV. Reactor Model to Calculate Future Fuel Cycle Requirements V. Consequences of Alternative Nuclear Programs VI. Conclusion ReferencesAuthor IndexSubject Index
