Advances in Nuclear Science and Technology
Volume 2
Published on 12. May 2014
388 pages
978-1-4832-2459-6 (ISBN)
Description
Advances in Nuclear Science and Technology, Volume 2 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book discusses the advances in the atomic energy field. Organized into six chapters, this volume begins with an overview of the concept of transfer function of a system. This text then examines the classic plant cycles for the water-cooled, liquid metal, and gas-cooled reactor concepts to pinpoint those points in cycle that require nuclear grade heat exchanger equipment. Other chapters consider heat exchanger, which is applied to the full spectrum of apparatus and equipment designed to facilitate the flow of heat from medium to medium. This book discusses as well the hardware characteristics and the resulting effects on reactor calculations. The final chapter deals with the effect of digital computers on nuclear reactor calculations and discusses some of the numerical methods used in nuclear reactor codes. This book is a valuable resource for design engineers and plant operating personnel.
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Content
ContributorsPrefaceReactor Transfer Functions I. Introduction II. Theory III. Applications to Reactors ReferencesHeat Exchangers in Nuclear Power Plants I. Introduction and General Discussion II. Types and Configurations III. Design Considerations: Performance Criteria IV. Design Considerations: Reliability Criteria V. Cost Criteria ReferencesThe Formation of Free Radicals in Polymers by Radiation, Their Reactions and Reactivities I. Introduction II. The Detection of Free Radicals in Polymers III. Radical Formation IV. Radical Reactions V. Radical Stability VI. Radical Behavior in Specific Polymers VII. The Effect of Gases on Polymer Radicals VIII. The Effect of Additives IX. The Formation of Radicals Other Than by Radiation ReferencesMeasurements of Reactor Parameters in Subcritical and Critical Assemblies I. Introduction II. Graphite-Moderated Reactors III. Uranium-Heavy Water Lattices IV. Uranium-Water Lattices V. Summary and Recommendations ReferencesScattering of Thermal Neutrons from Solids and their Thermalization Near Equilibrium I. Introduction II. Scattering Cross Section III. Transport Cross Section str and Diffusion Constant Do IV. Fermi Age V. Slowing Down Relaxation Time, tth VI. Diffusion Cooling Constant, C VII. Energy Spectrum of Neutrons ReferencesSome Aspects of the Use of Digital Computers in Nuclear Reactor Design I. Introduction II. The Role of Digital Computers in Reactor Design III. Hardware IV. Software V. Reactor-Code Classification VI. Multigroup Diffusion Codes VII. Transport Calculations VIII. Kinetics Calculations IX. Remaining Codes ReferencesAuthor IndexSubject Index
