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m o d |
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cr cnu---unuuu |
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141204s1972 nyua ob 001 0 eng d |
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|a OPELS
|b eng
|e rda
|e pn
|c OPELS
|d N$T
|d E7B
|d OCLCF
|d S4S
|d EBLCP
|d DEBSZ
|d YDXCP
|d MERUC
|d STF
|d OCLCQ
|d VLY
|d OCLCQ
|d OCLCO
|d OCLCQ
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|a 897651990
|a 948757792
|a 1162149155
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|a 9781483215631
|q (electronic bk.)
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|a 1483215636
|q (electronic bk.)
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|z 9780120293063
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|a (OCoLC)897473669
|z (OCoLC)897651990
|z (OCoLC)948757792
|z (OCoLC)1162149155
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|a TK9145
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|a TEC
|x 009070
|2 bisacsh
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|a 621.48
|2 22
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|a Advances in nuclear science and technology.
|n Volume 6 /
|c edited by Ernest J. Henley, Jeffery Lewins.
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264 |
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1 |
|a New York :
|b Academic Press,
|c 1972.
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300 |
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|a 1 online resource (xiii, 239 pages) :
|b illustrations
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336 |
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|a text
|b txt
|2 rdacontent
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|a computer
|b c
|2 rdamedia
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|a online resource
|b cr
|2 rdacarrier
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500 |
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|a Includes index.
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|a Print version record.
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|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.
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|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.
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|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.
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|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.
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520 |
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|a Advances in Nuclear Science and Technology.
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504 |
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|a Includes bibliographical references and index.
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546 |
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|a English.
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650 |
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0 |
|a Nuclear engineering.
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650 |
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0 |
|a Nuclear physics.
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650 |
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6 |
|a G�enie nucl�eaire.
|0 (CaQQLa)201-0007585
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650 |
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6 |
|a Physique nucl�eaire.
|0 (CaQQLa)201-0002614
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650 |
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7 |
|a nuclear physics.
|2 aat
|0 (CStmoGRI)aat300054569
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650 |
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|a TECHNOLOGY & ENGINEERING
|x Mechanical.
|2 bisacsh
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650 |
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7 |
|a Nuclear engineering.
|2 fast
|0 (OCoLC)fst01040032
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650 |
|
7 |
|a Nuclear physics.
|2 fast
|0 (OCoLC)fst01040386
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700 |
1 |
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|a Henley, Ernest J.,
|e editor.
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700 |
1 |
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|a Lewins, Jeffery,
|e editor.
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776 |
0 |
8 |
|i Print version:
|t Advances in nuclear science and technology. Vol. 6: 1972
|z 0120293064
|w (DLC) 62013039
|w (OCoLC)655872930
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856 |
4 |
0 |
|u https://sciencedirect.uam.elogim.com/science/book/9780120293063
|z Texto completo
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