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Advances in nuclear science and technology. Volume 6 /
Advances in Nuclear Science and Technology.
| Clasificación: | Libro Electrónico |
|---|---|
| Otros Autores: | , |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
New York :
Academic Press,
1972.
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| Temas: | |
| Acceso en línea: | Texto completo |
Tabla de Contenidos:
- Front Cover; Advances in Nuclear Science and Technology, Volume 6; Copyright Page; Table of Contents; CONTRIBUTORS; PREFACE; CONTENTS OF PREVIOUS VOLUMES; CHAPTER 1. THE 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; References.
- CHAPTER 2. STABILITY ANALYSIS OF NONLINEAR POINT REACTOR KINETICSI. 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; References; CHAPTER 3. THE 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 SwellingVIII. Clad Deformation and Failure; IX. Data; X. An Example; XI Conclusions; List of Symbols; References; CHAPTER 4. TECHNICAL 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; References; CHAPTER 5. HEAT 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 ModelsV. Hot-Channel Factors; VI. Spatial and Burnup Effects on Fuel Pin Temperature Profile; VII. Safety-Related Heat Transfer Considerations; VIII. Thermal Transport System; References; CHAPTER 6. THE 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; References; AUTHOR INDEX; SUBJECT INDEX.