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Advances in nuclear science and technology. Volume 6 /

Advances in Nuclear Science and Technology.

Detalles Bibliográficos
Clasificación:Libro Electrónico
Otros Autores: Henley, Ernest J. (Editor ), Lewins, Jeffery (Editor )
Formato: Electrónico eBook
Idioma:Inglés
Publicado: New York : Academic Press, 1972.
Temas:
Acceso en línea:Texto completo

MARC

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245 0 0 |a Advances in nuclear science and technology.  |n Volume 6 /  |c edited by Ernest J. Henley, Jeffery Lewins. 
264 1 |a New York :  |b Academic Press,  |c 1972. 
300 |a 1 online resource (xiii, 239 pages) :  |b illustrations 
336 |a text  |b txt  |2 rdacontent 
337 |a computer  |b c  |2 rdamedia 
338 |a online resource  |b cr  |2 rdacarrier 
500 |a Includes index. 
588 0 |a Print version record. 
505 0 |a 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. 
505 8 |a 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. 
505 8 |a 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. 
505 8 |a 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. 
520 |a Advances in Nuclear Science and Technology. 
504 |a Includes bibliographical references and index. 
546 |a English. 
650 0 |a Nuclear engineering. 
650 0 |a Nuclear physics. 
650 6 |a G�enie nucl�eaire.  |0 (CaQQLa)201-0007585 
650 6 |a Physique nucl�eaire.  |0 (CaQQLa)201-0002614 
650 7 |a nuclear physics.  |2 aat  |0 (CStmoGRI)aat300054569 
650 7 |a TECHNOLOGY & ENGINEERING  |x Mechanical.  |2 bisacsh 
650 7 |a Nuclear engineering.  |2 fast  |0 (OCoLC)fst01040032 
650 7 |a Nuclear physics.  |2 fast  |0 (OCoLC)fst01040386 
700 1 |a Henley, Ernest J.,  |e editor. 
700 1 |a Lewins, Jeffery,  |e editor. 
776 0 8 |i Print version:  |t Advances in nuclear science and technology. Vol. 6: 1972  |z 0120293064  |w (DLC) 62013039  |w (OCoLC)655872930 
856 4 0 |u https://sciencedirect.uam.elogim.com/science/book/9780120293063  |z Texto completo