6th Forum on New Materials - Part B -- Preface -- Table of Contents -- Chapter 1: Materials for Nuclear Fission and Fusion Technologies -- Indian Test Blanket Module in ITER - Development of RAFM Steel and Fabrication Technology -- Study on the Creep and Fatigue Properties of CLAM Steel -- Behavior at High Temperature of Metallic Liners (Ta, Nb) Used in the Sandwich Cladding Material of the GFR -- Utilization Research and Development of Hydride Materials in Fast Reactors -- Depleted Uranium as Hydrogen Storage Material -- Characterization of SiC Ceramic Tube Prepared by the Combined CVI and CVD Process -- Status of the Low Enriched Uranium Fuel Development for High Performance Research Reactors -- A Microfluidic-Assisted Fabrication of Size-Controlled Porose CeO2 Microspheres as an Analog Production of Nuclear Fuel Beads -- Xenon Ion Irradiation Effects on a Ni-Base Ni-17Mo-7Cr Alloy -- Chapter 2: Materials for Nuclear Waste Treatment and Disposal -- Selective Decontamination and Stable Solidification of Cs-Insoluble Ferrocyanide by Zeolites -- Fabrication and Chemical Durability of Ceramic Technetium-Based Pyrochlores and Perovskites as Potential Waste Forms -- Behavior of Fuel and Structural Materials in Severely Damaged Reactors -- A New Matrix for Conditioning Chloride Salt Wastes from the Electrorefining of Spent Nuclear Fuel -- Adsorption Materials Development for the Separation of Actinides and Specific Fission Products from High Level Waste -- Progress at ANSTO on a Synroc Plant for Intermediate-Level Waste from Reactor Production of 99Mo -- Review of the Development of the Proposed Yucca Mountain Geologic Repository -- RADON Operational Experience in High-Temperature Treatment of Radioactive Wastes -- Leaching Behavior of Salt Wastes Conditioned with Sodalite Blended with Two Different Glass Powders -- Keywords Index -- Authors Index.