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[null,"1.","Record Nr.",null,"UNINA9910824371203321"]
[null,null,"Titolo",null,"6th Forum on New Materials : 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. Part B / / edited by Pietro Vincenzini, World Academy of Ceramics and National Research Council, Italy ; co-edited by Hua-Tay Lin, Oak Ridge National Laboratory, USA, Kevin Fox, Savannah River National Laboratory, USA"]
[null,null,"Pubbl/distr/stampa",null,"Faenza, Italy : , : TTP, , [2014]"]
[{"$nulls":4},"©2014"]
[null,null,"ISBN",null,"3-03826-691-4"]
[null,null,"Descrizione fisica",null,"1 online resource (147 p.)"]
[null,null,"Collana",null,"Advances in science and technology, , 1662-8969 ; ; volume 94"]
[null,null,"Disciplina",null,"620.14"]
[null,null,"Soggetti",null,"Ceramics"]
[{"$nulls":4},"Ceramic materials"]
[{"$nulls":4},"Ceramic engineering"]
[null,null,"Lingua di pubblicazione",null,"Inglese"]
[null,null,"Formato",null,"Materiale a stampa"]
[null,null,null,"Livello bibliografico","Monografia"]
[null,null,null,"Note generali","Description based upon print version of record."]
[null,null,null,"Nota di bibliografia","Includes bibliographical references and index."]
[null,null,"Nota di contenuto",null,"6th Forum on New Materials - Part B; Preface; Table of Contents; Chapter 1: Materials for Nuclear Fission and Fusion Technologies; Indian Test Blanket Module in ITER - Development of RAFM Steel and Fabrication Technology; Study on the Creep and Fatigue Properties of CLAM Steel; Behavior at High Temperature of Metallic Liners (Ta, Nb) Used in the Sandwich Cladding Material of the GFR; Utilization Research and Development of Hydride Materials in Fast Reactors; Depleted Uranium as Hydrogen Storage Material; Characterization of SiC Ceramic Tube Prepared by the Combined CVI and CVD Process"]
[{"$nulls":4},"Status 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 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"]
[{"$nulls":4},"Behavior of Fuel and Structural Materials in Severely Damaged ReactorsA New Matrix for Conditioning Chloride Salt Wastes from the Electrorefining of Spent Nuclear Fuel; Adsorption Materials Development for the Separation of Actinides and Specific Fission Products from High Level Waste; Progress at ANSTO on a Synroc Plant for Intermediate-Level Waste from Reactor Production of 99Mo; Review of the Development of the Proposed Yucca Mountain Geologic Repository; RADON Operational Experience in High-Temperature Treatment of Radioactive Wastes"]
[{"$nulls":4},"Leaching Behavior of Salt Wastes Conditioned with Sodalite Blended with Two Different Glass PowdersKeywords Index; Authors Index"]
[null,null,null,"Sommario/riassunto","Collection of selected, peer reviewed papers from the 6 th Forum on New Materials, part of CIMTEC 2014-13th International Ceramics Congress and 6 th 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."]