04170nam 2200673Ia 450 991013947740332120170809152937.01-282-45640-797866124564040-470-58400-90-470-58399-1(CKB)2550000000005927(EBL)477736(OCoLC)647848882(SSID)ssj0000353945(PQKBManifestationID)11233149(PQKBTitleCode)TC0000353945(PQKBWorkID)10302174(PQKB)11734937(MiAaPQ)EBC477736(EXLCZ)99255000000000592720100115d2010 uy 0engur|n|---|||||txtccrCeramics 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 SalemHoboken, NJ Wileyc20101 online resource (218 p.)Ceramic engineering and science proceedings ;30/10Description based upon print version of record.0-470-45760-0 Includes bibliographical references and index.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 PROPERTIESBehaviors 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 COATINGFracture 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 FacilityCeramic Coated Particles for Safe Operation in HTRs and in Long-Term StorageAuthor IndexProvides a useful one-stop resource for understanding the most valuable aspects of ceramics in nuclear applications. Ceramic engineering and science proceedings ;v. 30, no. 10.Ceramic materialsCongressesNuclear engineeringMaterialsCongressesElectronic books.Ceramic materialsNuclear engineeringMaterials620.19304Katoh Yutai944445Cozzi Alex944446Singh Dilì„p928898Salem J. A(Jonathan A.),1960-889316American Ceramic Society.International Conference on Advanced Ceramics and CompositesMiAaPQMiAaPQMiAaPQBOOK9910139477403321Ceramics in nuclear applications2131973UNINA