6th Forum on New Materials - Part B

Proceedings of the 6th Forum on New Materials, part of CIMTEC 2014-13th International Ceramics Congress and 6th Forum on New Materials, June 15-19, 2014, Montecatini Terme, Italy
Erscheinungsjahr 2014
ISBN: 978-3-03835-307-2
Verlag: Trans Tech Publications

Buch, Englisch, 156 Seiten, Format (B × H): 170 mm x 240 mm, Gewicht: 500 g

Collection of selected, peer reviewed papers from the 6th Forum on New Materials, part of CIMTEC 2014-13th International Ceramics Congress and 6th Forum on New Materials, June 15-19, 2014, Montecatini Terme, Italy. The 18 papers are grouped as follows: Chapter 1: Materials for Nuclear Fission and Fusion Technologies, Chapter 2: Materials for Nuclear Waste Treatment and Disposal.

Autoren/Hrsg.

Vincenzini, Pietro

Fachgebiete

• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Elektronik, Optik
• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Metallische Werkstoffe
• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Keramik, Glas, Sonstige Werkstoffe

Inhaltsverzeichnis

Preface
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

Über Autor(innen)

Ed. Pietro Vincenzini