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Nuclear fuels : manufacturing processes, forms, and safety /

Detalles Bibliográficos
Clasificación:Libro Electrónico
Otros Autores: Lesage, Antoine (Editor ), Tondreau, Jérôme (Editor )
Formato: Electrónico eBook
Idioma:Inglés
Publicado: New York : Nova Science Publishers, Inc., [2010]
Colección:Energy science, engineering and technology series.
Temas:
Acceso en línea:Texto completo

MARC

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245 0 0 |a Nuclear fuels :  |b manufacturing processes, forms, and safety /  |c Antoine Lesage and Jérôme Tondreau, editors. 
264 1 |a New York :  |b Nova Science Publishers, Inc.,  |c [2010] 
300 |a 1 online resource. 
336 |a text  |b txt  |2 rdacontent 
337 |a computer  |b c  |2 rdamedia 
338 |a online resource  |b cr  |2 rdacarrier 
490 1 |a Energy science, engineering and technology 
504 |a Includes bibliographical references and index. 
588 |a Description based on print version record. 
505 0 |a NUCLEAR FUELS: MANUFACTURING PROCESSES, FORMS AND SAFETY; NUCLEAR FUELS: MANUFACTURING PROCESSES, FORMS AND SAFETY; LIBRARY OF CONGRESS CATALOGING-IN-PUBLICATION DATA; CONTENTS; PREFACE; Chapter 1: TRANSIENT DIFFUSION IN NUCLEAR FUELS PROCESSES; ABSTRACT; NOMENCLATURE; GREEK; 1.0. INTRODUCTION; 2.0. THEORY; 2.1. Fick's Laws of Molecular Diffusion; 2.2. Generalized Fick's Laws of Molecular Diffusion; 2.3. Derivation of Generalized Fick's Law of Diffusion; 3.0. SIMULTANEOUS FAST REACTIONS AND GENERALIZED FICK'SDIFFUSION; 3.1 Solution by Method of Laplace Transforms. 
505 8 |a 3.2. Generalized Fick's Diffusion with Fast Chemical Reaction in Infinite Catalyst in Cylindrical Coordinates3.3 Finite Speed Diffusion with Fast Chemical Reaction in Infinite Catalyst in Spherical Coordinates; 3.4 Taitel Paradox and Final Time Condition; 3.5. Relativistic Transformation of Coordinates; 3.6 Periodic Boundary Condition; 3.7. Finite Cylinder at Constant Wall Concentration; 3. 8. Finite Sphere with Constant Wall Concentration; 3.10. Critical Radii of Nuclear Fuel Rod Neither Less than the CyclingLimit Nor Greater than the Shape Limit. 
505 8 |a 3.11. Cooling of Nuclear Fuel Rods -- Temperature Dependent Heat Source3.12 Critical Point of Zero Transfer; REFERENCES; Chapter 2: USE OF DICYCLOHEXANO-SUBSTITUTED CROWN ETHERS FOR LIQUID RADIOACTIVE WASTE REPROCESSING: PRESENT-DAY TRENDS; ABSTRACT; 1. INTRODUCTION; 2. PURIFICATION AND ISOMER SEPARATION; 3. RADIATION CHEMISTRY AND RADIATION RESISTANCE OF CROWN ETHERS; 3.1. Intermediate Products of Radiolysis; 3.2. Final Radiolysis Products of Crown-Containing Systems; 3.3. Effect of Ionizing Radiation on Properties of Crown-Containing Systems; 4. LABORATORY SCALE AND PILOT TESTING. 
505 8 |a 5. CONCLUSIONREFERENCES; Chapter 3: HIGHLY RADIOACTIVE WASTE DISPOSAL: A GLOBAL CONCERN; ABSTRACT; INTRODUCTION; The Actors; National Efforts; International Conventions Governing Radioactive Waste Disposal; IGOs and NGOs; The International Atomic Energy Agency (IAEA); The Nuclear Energy Agency (NEA); The United Nations; Professional Organizations; Environmental Organizations; CONCLUSION; REFERENCES; Chapter 4: THE RUPTURE OF CARBON STEEL PIPES THAT TRANSPORT HIGH-TEMPERATURE AND HIGH-PRESSURE PURE WATER IN NUCLEAR POWER PLANTS; ABSTRACT; INTRODUCTION; 1. THE HISTORY OF EROSION-CORROSION. 
505 8 |a 1.1 Erosion-Corrosion in Seawater1.2 Wall Thinning of Carbon Steel Pipes in Deoxidized Pure Water; 1.3. Computer Programs Estimating the Rate of Flow-Accelerated Corrosion(FAC); 2. THEORIES OF ELECTROCHEMICAL CORROSION; 2.1. Micro-Cell Model for Uniform Corrosion; 2.2. Potential vs. Current Density Diagram for Uniform Corrosion; 2.3. Theory of Macro-Cell Corrosion for Localized Corrosion; 3. WALL THINNING OF CARBON STEEL PIPES IN POWER PLANTS; 3.1. Case Studies of Wall Thinning; 3.2. Categories of Wall Thinning; 3.3. Experimental Results of Laboratory Corrosion Tests on Carbon Steels. 
546 |a English. 
590 |a eBooks on EBSCOhost  |b EBSCO eBook Subscription Academic Collection - Worldwide 
650 0 |a Nuclear fuels. 
650 6 |a Combustibles nucléaires. 
650 7 |a TECHNOLOGY & ENGINEERING  |x Power Resources  |x Nuclear.  |2 bisacsh 
650 7 |a Nuclear fuels  |2 fast 
700 1 |a Lesage, Antoine,  |e editor. 
700 1 |a Tondreau, Jérôme,  |e editor. 
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830 0 |a Energy science, engineering and technology series. 
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