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Advances in materials science for environmental and nuclear technology [[electronic resource] /] / edited by Kevin Fox ... [et al.]
| Advances in materials science for environmental and nuclear technology [[electronic resource] /] / edited by Kevin Fox ... [et al.] |
| Pubbl/distr/stampa | Hoboken, N.J., : Wiley, 2010 |
| Descrizione fisica | 1 online resource (314 p.) |
| Disciplina | 620.11 |
| Altri autori (Persone) | FoxKevin |
| Collana | Ceramic transactions |
| Soggetto topico |
Materials - Environmental aspects
Nuclear engineering - Materials |
| Soggetto genere / forma | Electronic books. |
| ISBN |
0-470-93099-3
1-282-84920-4 9786612849206 0-470-93097-7 |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Advances in Materials Science for Environmental and Nuclear Technology; Contents; Preface; MATERIALS SOLUTIONS FOR THE NUCLEAR RENAISSANCE; Irradiation Effects in Ceramics for Plutonium Disposition; Synthesis and Structures of Gd2 (Zr2-xCex)O7: A Model Ceramic System for Plutonium Disposition; Waste Form Development for SRS MOX Plant Effluent; Flammable Gasses in the Saltstone Process Flowsheet; Development of Crystal-Tolerant Waste Glasses; Phase Stability of Defense Waste Processing Facility (DWPF) Type High Level Nuclear Waste Glasses
Alkali/Akaline-Earth Content Effects on Properties of High-Alumina Nuclear Waste GlassesNepheline Crystallization in Nuclear Waste Glasses; Cold Crucible Vitrification of SRS SB4 HLW Surrogate at High Waste Loadings; An Extraction of Platinum Group Metals and Molybdenum from Molten Borosilicate Glass Using Cu and Cu5Si; Microstructure of Laser-Melted Zirconium Carbide Ceramics; On the Mechanism of Radiation Damage in Zircon by High-Energy Electrons; Anelasticity in Austenitic Steels; Molten Salts for Nuclear Cogeneration; GREEN ENGINEERING AND ENVIRONMENTAL STEWARDSHIP Development of Low-Cost Functional Geopolymeric MaterialsGreen Technology for Extraction of Iron from Ores and Other Materials; Nanotechnology for Uranium Separations and Immobilization; How the Classic Materials Science Stool is being Changed by the Sustainability Stool; Impact of Materials Selection on the Sustainability of Wind Energy; Precipitation Behavior of Chromium in Chromium(III)-Bearing Slag; Improved Energy Efficiency and Environmental Benefits for Calcium Treatment in Steel; NANOTECHNOLOGY FOR ENERGY; Optical Characterization of Chemically Deposited SbCuS Thin Films Examining Defects in Solid Core 2-D Photonic Band-Gap Fibers with High Index InclusionsNanophased Materials in Supercritical CO2: Ceramic Nanopowder Synthesis, Encapsulation and Deposition; Influence of Gas Flow Rate on the Formation of ZnO Nanorods and Their Effects on Photoelectrochemical Response; Nanocoating Enhanced Optical Fiber Sensors; Surface Plasmon Resonant Enhanced Optical Transmission through ZnO/Ag/ZnO Multilayered Films; Controlled Shape Synthesis of BaTiO3-(Mn0.5Zn0.5)Fe2O4 Nanocomposites; Author Index |
| Record Nr. | UNINA-9910140751403321 |
| Hoboken, N.J., : Wiley, 2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Advances in materials science for environmental and nuclear technology [[electronic resource] /] / edited by Kevin Fox ... [et al.]
| Advances in materials science for environmental and nuclear technology [[electronic resource] /] / edited by Kevin Fox ... [et al.] |
| Pubbl/distr/stampa | Hoboken, N.J., : Wiley, 2010 |
| Descrizione fisica | 1 online resource (314 p.) |
| Disciplina | 620.11 |
| Altri autori (Persone) | FoxKevin |
| Collana | Ceramic transactions |
| Soggetto topico |
Materials - Environmental aspects
Nuclear engineering - Materials |
| ISBN |
0-470-93099-3
1-282-84920-4 9786612849206 0-470-93097-7 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Advances in Materials Science for Environmental and Nuclear Technology; Contents; Preface; MATERIALS SOLUTIONS FOR THE NUCLEAR RENAISSANCE; Irradiation Effects in Ceramics for Plutonium Disposition; Synthesis and Structures of Gd2 (Zr2-xCex)O7: A Model Ceramic System for Plutonium Disposition; Waste Form Development for SRS MOX Plant Effluent; Flammable Gasses in the Saltstone Process Flowsheet; Development of Crystal-Tolerant Waste Glasses; Phase Stability of Defense Waste Processing Facility (DWPF) Type High Level Nuclear Waste Glasses
Alkali/Akaline-Earth Content Effects on Properties of High-Alumina Nuclear Waste GlassesNepheline Crystallization in Nuclear Waste Glasses; Cold Crucible Vitrification of SRS SB4 HLW Surrogate at High Waste Loadings; An Extraction of Platinum Group Metals and Molybdenum from Molten Borosilicate Glass Using Cu and Cu5Si; Microstructure of Laser-Melted Zirconium Carbide Ceramics; On the Mechanism of Radiation Damage in Zircon by High-Energy Electrons; Anelasticity in Austenitic Steels; Molten Salts for Nuclear Cogeneration; GREEN ENGINEERING AND ENVIRONMENTAL STEWARDSHIP Development of Low-Cost Functional Geopolymeric MaterialsGreen Technology for Extraction of Iron from Ores and Other Materials; Nanotechnology for Uranium Separations and Immobilization; How the Classic Materials Science Stool is being Changed by the Sustainability Stool; Impact of Materials Selection on the Sustainability of Wind Energy; Precipitation Behavior of Chromium in Chromium(III)-Bearing Slag; Improved Energy Efficiency and Environmental Benefits for Calcium Treatment in Steel; NANOTECHNOLOGY FOR ENERGY; Optical Characterization of Chemically Deposited SbCuS Thin Films Examining Defects in Solid Core 2-D Photonic Band-Gap Fibers with High Index InclusionsNanophased Materials in Supercritical CO2: Ceramic Nanopowder Synthesis, Encapsulation and Deposition; Influence of Gas Flow Rate on the Formation of ZnO Nanorods and Their Effects on Photoelectrochemical Response; Nanocoating Enhanced Optical Fiber Sensors; Surface Plasmon Resonant Enhanced Optical Transmission through ZnO/Ag/ZnO Multilayered Films; Controlled Shape Synthesis of BaTiO3-(Mn0.5Zn0.5)Fe2O4 Nanocomposites; Author Index |
| Record Nr. | UNINA-9910830317503321 |
| Hoboken, N.J., : Wiley, 2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Advances in materials science for environmental and nuclear technology [[electronic resource] /] / edited by Kevin Fox ... [et al.]
| Advances in materials science for environmental and nuclear technology [[electronic resource] /] / edited by Kevin Fox ... [et al.] |
| Pubbl/distr/stampa | Hoboken, N.J., : Wiley, 2010 |
| Descrizione fisica | 1 online resource (314 p.) |
| Disciplina | 620.11 |
| Altri autori (Persone) | FoxKevin |
| Collana | Ceramic transactions |
| Soggetto topico |
Materials - Environmental aspects
Nuclear engineering - Materials |
| ISBN |
0-470-93099-3
1-282-84920-4 9786612849206 0-470-93097-7 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Advances in Materials Science for Environmental and Nuclear Technology; Contents; Preface; MATERIALS SOLUTIONS FOR THE NUCLEAR RENAISSANCE; Irradiation Effects in Ceramics for Plutonium Disposition; Synthesis and Structures of Gd2 (Zr2-xCex)O7: A Model Ceramic System for Plutonium Disposition; Waste Form Development for SRS MOX Plant Effluent; Flammable Gasses in the Saltstone Process Flowsheet; Development of Crystal-Tolerant Waste Glasses; Phase Stability of Defense Waste Processing Facility (DWPF) Type High Level Nuclear Waste Glasses
Alkali/Akaline-Earth Content Effects on Properties of High-Alumina Nuclear Waste GlassesNepheline Crystallization in Nuclear Waste Glasses; Cold Crucible Vitrification of SRS SB4 HLW Surrogate at High Waste Loadings; An Extraction of Platinum Group Metals and Molybdenum from Molten Borosilicate Glass Using Cu and Cu5Si; Microstructure of Laser-Melted Zirconium Carbide Ceramics; On the Mechanism of Radiation Damage in Zircon by High-Energy Electrons; Anelasticity in Austenitic Steels; Molten Salts for Nuclear Cogeneration; GREEN ENGINEERING AND ENVIRONMENTAL STEWARDSHIP Development of Low-Cost Functional Geopolymeric MaterialsGreen Technology for Extraction of Iron from Ores and Other Materials; Nanotechnology for Uranium Separations and Immobilization; How the Classic Materials Science Stool is being Changed by the Sustainability Stool; Impact of Materials Selection on the Sustainability of Wind Energy; Precipitation Behavior of Chromium in Chromium(III)-Bearing Slag; Improved Energy Efficiency and Environmental Benefits for Calcium Treatment in Steel; NANOTECHNOLOGY FOR ENERGY; Optical Characterization of Chemically Deposited SbCuS Thin Films Examining Defects in Solid Core 2-D Photonic Band-Gap Fibers with High Index InclusionsNanophased Materials in Supercritical CO2: Ceramic Nanopowder Synthesis, Encapsulation and Deposition; Influence of Gas Flow Rate on the Formation of ZnO Nanorods and Their Effects on Photoelectrochemical Response; Nanocoating Enhanced Optical Fiber Sensors; Surface Plasmon Resonant Enhanced Optical Transmission through ZnO/Ag/ZnO Multilayered Films; Controlled Shape Synthesis of BaTiO3-(Mn0.5Zn0.5)Fe2O4 Nanocomposites; Author Index |
| Record Nr. | UNINA-9910840611603321 |
| Hoboken, N.J., : Wiley, 2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Annual meeting proceedings
| Annual meeting proceedings |
| Pubbl/distr/stampa | Northbrook, Ill., : Institute of Materials Management |
| Descrizione fisica | 1 online resource |
| Disciplina | 604 |
| Soggetto topico |
Nuclear engineering - Materials
Nuclear reactors - Materials Nuclear reactors - Safety measures |
| Soggetto genere / forma | Conference papers and proceedings. |
| Formato | Materiale a stampa |
| Livello bibliografico | Periodico |
| Lingua di pubblicazione | eng |
| Altri titoli varianti |
Annual meeting proceedings - Institute of Nuclear Materials Management
Nuclear materials management |
| Record Nr. | UNINA-9910324948603321 |
| Northbrook, Ill., : Institute of Materials Management | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques [[electronic resource] /] / Georgy Levanovich Khorasanov, editor
| Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques [[electronic resource] /] / Georgy Levanovich Khorasanov, editor |
| Pubbl/distr/stampa | New York., : Nova Publishers, c2013 |
| Descrizione fisica | 1 online resource (196 p.) |
| Disciplina | 621.48/33 |
| Altri autori (Persone) | KhorasanovGeorgy Levanovich |
| Collana | Nuclear materials and disaster research |
| Soggetto topico |
Nuclear engineering - Materials
Nuclear power plants - Materials Lead - Isotopes |
| Soggetto genere / forma | Electronic books. |
| ISBN | 1-62417-661-5 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910465854703321 |
| New York., : Nova Publishers, c2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques [[electronic resource] /] / Georgy Levanovich Khorasanov, editor
| Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques [[electronic resource] /] / Georgy Levanovich Khorasanov, editor |
| Pubbl/distr/stampa | New York., : Nova Publishers, c2013 |
| Descrizione fisica | 1 online resource (196 p.) |
| Disciplina | 621.48/33 |
| Altri autori (Persone) | KhorasanovGeorgy Levanovich |
| Collana | Nuclear materials and disaster research |
| Soggetto topico |
Nuclear engineering - Materials
Nuclear power plants - Materials Lead - Isotopes |
| ISBN | 1-62417-661-5 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910792009603321 |
| New York., : Nova Publishers, c2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques [[electronic resource] /] / Georgy Levanovich Khorasanov, editor
| Application of stable lead isotope Pb-208 in nuclear power engineering and its acquisition techniques [[electronic resource] /] / Georgy Levanovich Khorasanov, editor |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | New York., : Nova Publishers, c2013 |
| Descrizione fisica | 1 online resource (196 p.) |
| Disciplina | 621.48/33 |
| Altri autori (Persone) | KhorasanovGeorgy Levanovich |
| Collana | Nuclear materials and disaster research |
| Soggetto topico |
Nuclear engineering - Materials
Nuclear power plants - Materials Lead - Isotopes |
| ISBN | 1-62417-661-5 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Intro -- APPLICATION OF STABLE LEAD ISOTOPE PB-208 IN NUCLEAR POWER ENGINEERING AND ITS ACQUISITION TECHNIQUES -- APPLICATION OF STABLE LEAD ISOTOPE PB-208 IN NUCLEAR POWER ENGINEERING AND ITS ACQUISITION TECHNIQUES -- CONTENTS -- PREFACE -- SOME ADVANTAGES IN USING LEAD-208AS COOLANT FOR FAST REACTORS AND ACCELERATOR DRIVEN SYSTEMS -- ABSTRACT -- INTRODUCTION -- 1. SMALL NEUTRON ABSORPTION IN FR AND ADS COOLANT FROM LEAD-208 -- 2. GAIN IN CORE FUEL LOADING DUE TO EXCESS OF NEUTRONS -- 3. INCREASING THE FUEL BREEDING GAIN IN FRS AND ADSS COOLED WITH LEAD-208 -- 4. HARDENING OF ADS AND FR NEUTRON SPECTRA IN USING LEAD-208 INSTEAD OF NATURAL LEAD OR LEAD-BISMUTH -- CONCLUSION -- ACKNOWLEDGMENTS -- REFERENCES -- INTRODUCTIONS OF 208PB COOLANT TO INNOVATIVE FAST REACTORS -- ABSTRACT -- INTRODUCTION -- Requirements Imposed on Nuclear Energy Utilization -- CANDLE Reactor -- How Does CANDLE Reactor Satisfy the Requirements on Nuclear Energy Utilization? -- TECHNIQUES INTRODUCED TO CANDLE REACTOR -- 208PB COOLANT -- Lead and Lead Bismuth -- 208PB COOLANT -- 208PB COOLED CANDEL REACTORS -- Middle Sized Reactor -- POWER FLATTENING -- SMALL LONG-LIFE REACTOR -- REFERENCES -- RADIOGENIC LEAD WITH DOMINANT CONTENT OF 208PB: NEW COOLANT, NEUTRON MODERATOR AND REFLECTOR FOR INNOVATIVE NUCLEAR FACILITIES -- ABSTRACT -- INTRODUCTION -- I. NEUTRON-PHYSICAL PROPERTIES AND ADVANTAGES OF RADIOGENIC LEAD -- II. ADVANTAGES FROM APPLICATIONS OF IN FAST REACTORS 208 PB -- II.A. Improvement of the Reactor Safety. Coolant Temperature Reactivity Coefficient -- II.B. Prompt Neutron Lifetime 20 -- II.B.1. One-Dimentional Axial Model of Reactor -- II.B.2. Reactor Kinetics -- II.B.3. One-Dimentional Axial Model of the Fast Reactor Brest* with Thick Reflector -- II.B.4. Spherical Model of the Fast Reactor Brest* with Thick Reflector.
II.B.5. Impact of Reflector Parameters on Fission Distribution and Neutron Spectrum -- II.C. Models of Neutron Kinetics in the Fast Reactor Brest* with Thick Reflector -- II.C.1. One-Point Model -- II.C.2. Multi-Point Model -- II.C.3. Neutron Kinetics of the Fast Reactor Brest* with Thick Pb Reflector 208 -- III. ENHANCED PROLIFERATION RESISTANCE OF PU-CONTAINING FUEL -- IV. THERMAL-HYDRAULIC ADVANTAGES OF THE REACTOR CORE COOLED BY 208Pb as a coolPB -- V. REPLACEMENT OF NITRIDE BY OXIDE URANIUM-PLUTONIUM FUEL -- VI. POTENTIAL FOR FUEL BREEDING IN AXIAL URANIUM BLANKETS -- VII. ADVANTAGES FROM APPLICATION OF 208PB IN ADS-SYSTEMS -- VII.A. High Neutron Flux in an ADS Blanken -- VII.B. Transmutation in Resonance Range of Neutron Energy -- VII.C. High-Flux ADS with Cooled Transmutation Zone -- VIII. NATURAL RESOURCES OF RADIOGENIC LEAD -- CONCLUSION -- REFERENCES -- PHOTOCHEMICAL LASER SEPARATION OF LEAD ISOTOPES FOR SAFE NUCLEAR POWER REACTORS -- ABSTRACT -- 1. INTRODUCTION -- 2. METHODS OF LASER ISOTOPE SEPARATION -- 3. SELECTIVE EXCITATION OF THE METASTABLE LEVELS OF LEAD -- 4. EXPERIMENTAL AND APPROACH -- 5. RESULTS AND DISCUSSION -- CONCLUSION -- REFERENCES -- ASSESSMENT OF SPECIFIC COST OF HIGHLY ENRICHED LEAD-208 ISOTOPE BY GAS CENTRIFUGES USING VARIOUS RAW MATERIALS -- ABSTRACT -- DESIGNATION -- INTRODUCTION -- THEORETICAL BACKGROUND -- DISCUSSION -- Enrichment from the Natural Lead Isotope Mixture -- Enrichment from the Radiogenic Lead -- CONCLUSION -- REFERENCES -- METHOD FOR OBTAINING ISOTOPICALLY ENRICHED METAL LEAD FROM MONOISOTOPIC TETRAMETHYLLEAD AND ITS PURIFICATION -- ABSTRACT -- 1. INTRODUCTION -- 2. SYNTHESIS OF PB(CH3)4 -- 3. CONVERSION OF ISOTOPE-ENRICHED PBTO METALLIC LEAD 208(CH3)4 -- 4. PURIFICATION OF ISOTOPICALLY ENRICHED METALLIC LEAD -- CONCLUSION -- REFERENCES -- INDEX. |
| Record Nr. | UNINA-9910815789503321 |
| New York., : Nova Publishers, c2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
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
| 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 |
| Pubbl/distr/stampa | Hoboken, NJ, : Wiley, c2010 |
| Descrizione fisica | 1 online resource (218 p.) |
| Disciplina | 620.19304 |
| Altri autori (Persone) |
KatohYutai
CozziAlex SinghDilīp SalemJ. A <1960-> (Jonathan A.) |
| Collana | Ceramic engineering and science proceedings |
| Soggetto topico |
Ceramic materials
Nuclear engineering - Materials |
| Soggetto genere / forma | Electronic books. |
| ISBN |
1-282-45640-7
9786612456404 0-470-58400-9 0-470-58399-1 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| 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 |
| Record Nr. | UNINA-9910139477403321 |
| Hoboken, NJ, : Wiley, c2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
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
| 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 |
| Pubbl/distr/stampa | Hoboken, NJ, : Wiley, c2010 |
| Descrizione fisica | 1 online resource (218 p.) |
| Disciplina | 620.19304 |
| Altri autori (Persone) |
KatohYutai
CozziAlex SinghDilīp SalemJ. A <1960-> (Jonathan A.) |
| Collana | Ceramic engineering and science proceedings |
| Soggetto topico |
Ceramic materials
Nuclear engineering - Materials |
| ISBN |
1-282-45640-7
9786612456404 0-470-58400-9 0-470-58399-1 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| 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 |
| Record Nr. | UNINA-9910831092303321 |
| Hoboken, NJ, : Wiley, c2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
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
| 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 |
| Pubbl/distr/stampa | Hoboken, NJ, : Wiley, c2010 |
| Descrizione fisica | 1 online resource (218 p.) |
| Disciplina | 620.19304 |
| Altri autori (Persone) |
KatohYutai
CozziAlex SinghDilīp SalemJ. A <1960-> (Jonathan A.) |
| Collana | Ceramic engineering and science proceedings |
| Soggetto topico |
Ceramic materials
Nuclear engineering - Materials |
| ISBN |
1-282-45640-7
9786612456404 0-470-58400-9 0-470-58399-1 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| 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 |
| Record Nr. | UNINA-9910841336703321 |
| Hoboken, NJ, : Wiley, c2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
