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20231120111841.0 |
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cr cnu---unuuu |
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141027s1976 nyua o 001 0 eng d |
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|a OPELS
|b eng
|e rda
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|c OPELS
|d N$T
|d EBLCP
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|a 897651993
|a 948742289
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|a 9781483215662
|q (electronic bk.)
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|a 1483215660
|q (electronic bk.)
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|z 0120293099
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|z 9780120293094
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|a (OCoLC)893872999
|z (OCoLC)897651993
|z (OCoLC)948742289
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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 Vol. 9 /
|c edited by Ernest J. Henley, Jeffery Lewins.
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264 |
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|a New York ;
|a London :
|b Academic Press,
|c 1976.
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300 |
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|a 1 online resource (xvii, 359 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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|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 9; Copyright Page; Table of Contents; CONTRIBUTORS; PREFACE; CONTENTS OF PREVIOUS VOLUMES; CHAPTER 1. NUCLEAR POWER REACTORS AND THE EVALUATION OF POPULATIONHAZARDS; I. Possibility of Radiological Hazards from an Escape of Fission Products: Historical Introduction; II. Reactor Accidents in Relation to Fission Product Release; III. Fission Products in Fuel and the Release of Radioactivity; IV. Atmospheric Dispersal of a Release and Deposition and Wash-Out of Contamination; V. Analysis of Hazards from Fission Products Releases.
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|a VI. An Outline of Potential Hazards to the Population from Accidents to Sodium-Cooled Fast Neutron ReactorsVII. Risks to the Individual and to the Population from Radiation ExposureDue to Fission Product Release; VIII. Conclusions; References; CHAPTER 2. THE SOLUTION OF CRITICALITY PROBLEMS BY MONTE CARLO METHODS; I. Introduction; II. Nuclear Data; III. Group Nuclear Data; IV. Geometry; V. Neutron Sources; VI. Neutron Tracking; VII. Neutron Interaction between Fissile Units in an Array; VIII. Program Output; IX. Checking Facilities; Acknowledgments; References.
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|a CHAPTER 3. HIGH TEMPERATURE CHEMISTRY OF CERAMIC NUCLEAR FUELS WITHEMPHASIS ON NONSTOICHIOMETRYI. Introduction; II. Phase Equilibrium and Defect Structures; III. Diffusion; IV. Vaporization; References; CHAPTER 4. DEVELOPMENTS IN PERTURBATION THEORY; I. Introduction; II. Perturbation Expressions for Reactivity; III. Methods for the Calculation of Perturbed Fluxes; IV. Integral Transport Theory Formulations for Reactivity; V. Generalized Perturbation Theory; VI. Sensitivity and Optimization Studies; VII. Multigroup Calculations of Bilinear Functionals.
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|a VIII. Solution of Inhomogeneous Boltzmann Equations with Singular OperatorsIX. Concluding Remarks; Acknowledgments; References; CHAPTER 5. COMPUTER TECHNOLOGY, PROGRAM INTERCHANGE, AND STANDARDS; I. Introduction; II. Hardware Development; III. Software Developments; IV. Program Interchange; V. Standardization Activities; Appendix A: Argonne Code Center Abstract Format; Appendix B; References; SUBJECT INDEX.
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|a Advances in Nuclear Science and Technology.
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|a Nuclear engineering.
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650 |
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|a G�enie nucl�eaire.
|0 (CaQQLa)201-0007585
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650 |
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7 |
|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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700 |
1 |
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|a Henley, Ernest Justus.
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700 |
1 |
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|a Lewins, Jeffery,
|d 1930-
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776 |
0 |
8 |
|i Print version:
|t Advances in nuclear science and technology. Vol. 9
|z 0120293099
|w (DLC) 62013039
|w (OCoLC)502209408
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856 |
4 |
0 |
|u https://sciencedirect.uam.elogim.com/science/book/9780120293094
|z Texto completo
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