Advances in Nuclear Science and Technology

Advances in Nuclear Science and Technology

Volume 9

1st Edition - January 1, 1976

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  • Editors: Ernest J. Henley, Jeffery Lewins
  • eBook ISBN: 9781483215662

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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


    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


    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


    High Temperature Chemistry of Ceramic Nuclear Fuels with Emphasis on Nonstoichiometry

    I. Introduction

    II. Phase Equilibrium and Defect Structures

    III. Diffusion

    IV. Vaporization


    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

    VIII. Solution of Inhomogeneous Boltzmann Equations with Singular Operators

    IX. Concluding Remarks


    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


    Subject Index

Product details

  • No. of pages: 578
  • Language: English
  • Copyright: © Academic Press 1976
  • Published: January 1, 1976
  • Imprint: Academic Press
  • eBook ISBN: 9781483215662

About the Editors

Ernest J. Henley

Jeffery Lewins

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