Book Description:
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 behavior; Materials aspects of the entire fuel cycle; Performance of nuclear waste materials, glasses and ceramics, immobilization 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. This new book presents state-of-the art research in this field which is crucial to the growth and exploitation of nuclear energy.

Table of Contents:
Preface

Chapter 1 - Studies on Ceramics and Glass-Ceramics for Immobilization of High-Level Nuclear Wastes; pp. 1-138
(D. Caurant, P. Loiseau and V. Aubin-Chevaldonnet et al., Laboratoire de Chimie de la Matière Condensée de Paris, France)

Chapter 2 - Equilibrium Phases in Zirconium Alloys Concerning to Nuclear Industry - Isothermal Sections of the Zr-Cr-Sn and Zr-Cr-Ti Systems; pp. 139-160
(S.F. Aricó, R.O. González and L.M. Gribaudo, Comisión Nacional de Energía Atómica, Argentina)

Chapter 3 - Comprehensive Models for Accurate Prediction of Graphite Oxidation Rates in Safety Analysis of HTGR; pp. 161-184
(Eung Soo Kim and Hee Cheon NO)

Chapter 4 - The Surface Reactions of Uranium Oxides; pp. 185-214 (R.I. King and H. Idriss, Univ. of Auckland, New Zealand)

Chapter 5 - Characterization of Nanostructural Features in Reactor Materials using Positron Annihilation Spectroscopy; pp. 215-256 (Anatoly P. Druzhkov and Denis A. Perminov, Institute of Metal Physics, Russia)

Chapter 6 - Hydrogen Outgassing from Lithium Hydride; pp. 257-283 (L.N. Dinh, M.A. Schildbach, Lawrence Livermore National Laboratory, USA and R.A. Smith et al., BWXT-Y-12, USA)

Chapter 7 - The Gap Width and Microstructure Change on the Burnup in FBR MOX Fuel Pins Irradiated to High Burnup; pp. 285-315
(Koji Maeda, Japan Atomic Energy Agency, Japan and Hirotaka Furuya, Kyushu Univ., Japan)

Chapter 8 - Structural Characterization of the GdxZr1-xO2-x/2 System by 155Gd Mössbauer Spectroscopic Study; pp. 317-340
(Junhu Wang, Laboratory of Aerospace Catalysis and New Materials, Dalian Institute of Chemical Physics,
Chinese Academy of Science, China)

Chapter 9 - Cyclic Behavior and Microstructure Developed in Zircaloy-4 Between 300 and 873K; pp. 341-367
(Iris Alvarez-Armas and Alberto F. Armas, Univ. Nacional de Rosario, Argentina)

Chapter 10 - Analysis of Damage Evolution in FCC Metals Irradiated with High Energy Neutrons Undeer Well Defined Boundary Conditions; pp. 369-397
(T. Yoshiie, Research Reactor Institute, Kyoto University, Japan.)

Index