Advances in Nuclear Science and Technology
Volume 9
Published on 9. May 2014
578 pages
978-1-4832-1566-2 (ISBN)
Description
Advances in Nuclear Science and Technology, Volume 9 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants. Organized into five chapters, this volume begins with an overview of the possible consequences of a large-scale release of radioactivity from a nuclear reactor in the event of a serious accident. This text then discusses the extension of conventional perturbation techniques to multidimensional systems and to high-order approximations of the Boltzmann equation. Other chapters consider details of probability treatment of the conventionally assumed loss-of-pressure accident to a modern gas-cooled reactor. This book discusses as well details of reliability analysis of a typical electromechanical protective system. The final chapter deals with the computer applications and the need for standardization as both computing and nuclear energy shifted from research and development to industry status. This book is a valuable resource for reactor physicists, engineers, scientists, and research workers.
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Ernest J. Henley | Jeffery Lewins
Advances in Nuclear Science and Technology: v. 9
Book
11/1976
Academic Press
€86.66
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Content
ContributorsPrefaceContents of Previous VolumesNuclear Power Reactors and the Evaluation of Population Hazards 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 VI. An Outline of Potential Hazards to the Population from Accidents to Sodium-Cooled Fast Neutron Reactors VII. Risks to the Individual and to the Population from Radiation Exposure Due to Fission Product Release VIII. Conclusions ReferencesThe 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 ReferencesHigh Temperature Chemistry of Ceramic Nuclear Fuels with Emphasis on Nonstoichiometry I. Introduction II. Phase Equilibrium and Defect Structures III. Diffusion IV. Vaporization ReferencesDevelopments 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 VIII. Solution of Inhomogeneous Boltzmann Equations with Singular Operators IX. Concluding Remarks ReferencesComputer 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 ReferencesSubject Index
