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Nuclear Materials

Editat de Joel E. Keister
en Limba Engleză Hardback – 3 feb 2008
Nuclear materials include materials relevant to nuclear fission and fusion reactors and high power accelerator technologies, and closely related aspects of materials science and engineering. Processes and properties include atomic lattice defects, microstructures, thermodynamics, corrosion and mechanical and physical properties. Included are fission reactor materials, including fuels, cladding, core structures, pressure vessels, moderator and control components; fission product behaviour; Materials aspects of the entire fuel cycle; Performance of nuclear waste materials, glasses and ceramics, immobilisation of wastes; Fusion reactor materials, including first walls, blankets, insulators and magnets; Neutron radiation effects in materials, including defects, microstructures, transmutations, phase changes and macroscopic properties; Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials. The book presents state-of-the art research in this field which is crucial to the growth and exploitation of nuclear energy.
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Specificații

ISBN-13: 9781600214325
ISBN-10: 1600214320
Pagini: 412
Ilustrații: b/w illus
Dimensiuni: 186 x 260 x 29 mm
Greutate: 1.08 kg
Editura: Nova Science Publishers Inc

Cuprins

Preface; Studies on Ceramics and Glass-Ceramics for Immobilisation of High-Level Nuclear Wastes; Equilibrium Phases in Zirconium Alloys Concerning to Nuclear Industry; Isothermal Sections of the Zr-Cr-Sn and Zr-Cr-Ti Systems; Comprehensive Models for Accurate Prediction of Graphite Oxidation Rates in Safety Analysis of HTGR; The Surface Reactions of Uranium Oxides; Characterisation of Nanostructural Features in Reactor Materials using Positron Annihilation Spectroscopy; Hydrogen Outgassing from Lithium Hydride; The Gap Width and Microstructure Change on the Burn-up in FBR MOX Fuel Pins Irradiated to High Burn-up; Structural Characterisation of the GdxZr1-xO2-x/2 System by 155Gd Mössbauer Spectroscopic Study; Cyclic Behaviour and Microstructure Developed in Zircaloy-4 Between 300 and 873K; Analysis of Damage Evolution in FCC Metals Irradiated with High Energy Neutrons Under Well Defined Boundary Conditions; Index.