Vincenzini | 6th Forum on New Materials - Part B | Sonstiges | 978-3-03859-007-1 | sack.de

Sonstiges, Englisch, Band Volume 94, 156 Seiten, Format (B × H): 125 mm x 142 mm, Gewicht: 200 g

Reihe: Advances in Science and Technology

Vincenzini

6th Forum on New Materials - Part B

Sonstiges, Englisch, Band Volume 94, 156 Seiten, Format (B × H): 125 mm x 142 mm, Gewicht: 200 g

Reihe: Advances in Science and Technology

ISBN: 978-3-03859-007-1
Verlag: Trans Tech Publications


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.
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Autoren/Hrsg.


Weitere Infos & Material


Indian Test Blanket Module in ITER - Development of RAFM Steel and Fabrication TechnologyStudy on the Creep and Fatigue Properties of CLAM SteelBehavior at High Temperature of Metallic Liners (Ta, Nb) Used in the Sandwich Cladding Material of the GFRUtilization Research and Development of Hydride Materials in Fast ReactorsDepleted Uranium as Hydrogen Storage MaterialCharacterization of SiC Ceramic Tube Prepared by the Combined CVI and CVD ProcessStatus of the Low Enriched Uranium Fuel Development for High Performance Research ReactorsA Microfluidic-Assisted Fabrication of Size-Controlled Porose CeO2 Microspheres as an Analog Production of Nuclear Fuel BeadsXenon Ion Irradiation Effects on a Ni-Base Ni-17Mo-7Cr AlloySelective Decontamination and Stable Solidification of Cs-Insoluble Ferrocyanide by ZeolitesFabrication and Chemical Durability of Ceramic Technetium-Based Pyrochlores and Perovskites as Potential Waste FormsBehavior of Fuel and Structural Materials in Severely Damaged ReactorsA New Matrix for Conditioning Chloride Salt Wastes from the Electrorefining of Spent Nuclear FuelAdsorption Materials Development for the Separation of Actinides and Specific Fission Products from High Level WasteProgress at ANSTO on a Synroc Plant for Intermediate-Level Waste from Reactor Production of 99MoReview of the Development of the Proposed Yucca Mountain Geologic RepositoryRADON Operational Experience in High-Temperature Treatment of Radioactive WastesLeaching Behavior of Salt Wastes Conditioned with Sodalite Blended with Two Different Glass Powders


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