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
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| Titolo: |
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
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| Pubblicazione: | Faenza, Italy : , : TTP, , [2014] |
| ©2014 | |
| Descrizione fisica: | 1 online resource (147 p.) |
| Disciplina: | 620.14 |
| Soggetto topico: | Ceramics |
| Ceramic materials | |
| Ceramic engineering | |
| Persona (resp. second.): | VincenziniP. <1939-> |
| LinHua-Tay | |
| FoxKevin | |
| Note generali: | Description based upon print version of record. |
| Nota di bibliografia: | Includes bibliographical references and index. |
| Nota di contenuto: | 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 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 | |
| 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 | |
| Leaching Behavior of Salt Wastes Conditioned with Sodalite Blended with Two Different Glass PowdersKeywords Index; Authors Index | |
| 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. |
| Titolo autorizzato: | 6th Forum on New Materials |
| ISBN: | 3-03826-691-4 |
| Formato: | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione: | Inglese |
| Record Nr.: | 9910787245503321 |
| Lo trovi qui: | Univ. Federico II |
| Opac: | Controlla la disponibilità qui |
Serie:
Advances in science and technology ; ; v. 94.