Ceramics in nuclear applications [[electronic resource] ] : a collection of papers presented at the 33rd International Conference on Advanced Ceramics and Composites, January 18-23, 2009, Daytona Beach, Florida / / edited by Yutai Katoh, Alex Cozzi; volume editors, Dileep Singh, Jonathan Salem

• Pubblicazione: Hoboken, NJ, : Wiley, c2010
• Descrizione fisica: 1 online resource (218 p.)
• Disciplina: 620.19304
• Soggetto topico: Ceramic materials; Nuclear engineering - Materials
• Altri autori: KatohYutai CozziAlex SinghDilīp SalemJ. A <1960-> (Jonathan A.)
• Note generali: Description based upon print version of record.
• Nota di bibliografia: Includes bibliographical references and index.
• Nota di contenuto: Ceramics in Nuclear Applications; Contents; Preface; Introduction; SILICON CARBIDE AND CARBON COMPOSITES; Single- and Multi-Layered Interphases in SiC/SiC Composites Exposed to Severe Conditions: An Overview; Research and Developments on C/C Composite for Very High Temperature Reactor (VHTR) Application; X-Ray Tomographic Characterization of the Macroscopic Porosity of CVI SiC/SiC Composites-Effects on the Elastic Behavior; Mechanical Strength of CTP Triplex Sic Fuel Clad Tubes after Irradiation in MIT Research Reactor under PWR Coolant Conditions; MECHANICAL PROPERTIES ; Behaviors of SiC Fibers at High TemperatureFracture Resistance of Silicon Carbide Composites Using Various Notched Specimens; Optimization of an lnterphase Thickness in Hot-Pressed SiCf/SiC Composites; Validation of Ring-on-Ring Flexural Test for Nuclear Ceramics Using Miniaturized Specimens; MATERIAL AND COMPONENT PROCESSING; Design, Fabrication, and Testing of Silicon Infiltrated Ceramic Plate-Type Heat Exchangers; Microstructural Studies of Hot Pressed Silicon Carbide Ceramic; Diffusion Bonding of Silicon Carbide to Ferritic Steel; CERAMICS FOR FUEL COATING ; Fracture Properties of SiC Layer in TRISO-Coated Fuel ParticlesOptimization of Fracture Strength Tests for the Sic Layer of Coated Fuel Particles by Finite Element Analysis; Laser Melting of Spark Plasma Sintered Zirconium Carbide: Thermophysical Properties of a Generation IV Very High Temperature Reactor Material; NUCLEAR FUELS AND WASTES; Development and Testing of a Cement Waste Form for TRU Effluent from the Savannah River Site Mixed Oxide Fuel Fabrication Facility; Frit Optimization for Sludge Batch Processing at the Defense Waste Processing Facility ; Ceramic Coated Particles for Safe Operation in HTRs and in Long-Term StorageAuthor Index
• Sommario/riassunto: Provides a useful one-stop resource for understanding the most valuable aspects of ceramics in nuclear applications.
• Titolo autorizzato: Ceramics in nuclear applications
• ISBN: 1-282-45640-7; 9786612456404; 0-470-58400-9; 0-470-58399-1
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910841336703321
• Lo trovi qui: Univ. Federico II
• Serie: Ceramic engineering and science proceedings ; ; v. 30, no. 10.