Advances in Nuclear Science and Technology - 1st Edition - ISBN: 9780120293094, 9781483215662

Advances in Nuclear Science and Technology

1st Edition

Volume 9

Editors: Ernest J. Henley Jeffery Lewins
eBook ISBN: 9781483215662
Imprint: Academic Press
Published Date: 1st January 1976
Page Count: 578
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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.

Table of Contents


Contributors


Preface


Contents of Previous Volumes


Nuclear 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


References


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


References


High Temperature Chemistry of Ceramic Nuclear Fuels with Emphasis on Nonstoichiometry


I. Introduction


II. Phase Equilibrium and Defect Structures


III. Diffusion


IV. Vaporization


References


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 B

Details

No. of pages:
578
Language:
English
Copyright:
© Academic Press 1976
Published:
Imprint:
Academic Press
eBook ISBN:
9781483215662

About the Editor

Ernest J. Henley

Jeffery Lewins

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