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 |
Pubbl/distr/stampa | Faenza, Italy : , : TTP, , [2014] |
Descrizione fisica | 1 online resource (147 p.) |
Disciplina | 620.14 |
Collana | Advances in science and technology |
Soggetto topico |
Ceramics
Ceramic materials Ceramic engineering |
Soggetto genere / forma | Electronic books. |
ISBN | 3-03826-691-4 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
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 |
Record Nr. | UNINA-9910460048303321 |
Faenza, Italy : , : TTP, , [2014] | ||
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Lo trovi qui: Univ. Federico II | ||
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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 |
Pubbl/distr/stampa | Faenza, Italy : , : TTP, , [2014] |
Descrizione fisica | 1 online resource (147 p.) |
Disciplina | 620.14 |
Collana | Advances in science and technology |
Soggetto topico |
Ceramics
Ceramic materials Ceramic engineering |
ISBN | 3-03826-691-4 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
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 |
Record Nr. | UNINA-9910787245503321 |
Faenza, Italy : , : TTP, , [2014] | ||
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Lo trovi qui: Univ. Federico II | ||
|
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 |
Pubbl/distr/stampa | Faenza, Italy : , : TTP, , [2014] |
Descrizione fisica | 1 online resource (147 p.) |
Disciplina | 620.14 |
Collana | Advances in science and technology |
Soggetto topico |
Ceramics
Ceramic materials Ceramic engineering |
ISBN | 3-03826-691-4 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
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 |
Record Nr. | UNINA-9910824371203321 |
Faenza, Italy : , : TTP, , [2014] | ||
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Lo trovi qui: Univ. Federico II | ||
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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 | ||
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Lo trovi qui: Univ. Federico II | ||
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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 | ||
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Lo trovi qui: Univ. Federico II | ||
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Advances in materials science for environmental and nuclear technology / / 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-9910877099903321 |
Hoboken, N.J., : Wiley, 2010 | ||
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Lo trovi qui: Univ. Federico II | ||
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Ceramic materials for energy applications II [[electronic resource] ] : a collection of papers presented at the 36th International Conference on Advanced Ceramics and Composites, January 22-27, 2012, Daytona Beach, Florida / / edited by Kevin Fox ... [et al.] ; volume editors, Michael Halbig, Sanjay Mathur |
Pubbl/distr/stampa | Hoboken, N.J., : Wiley, 2013 |
Descrizione fisica | 1 online resource (195 p.) |
Disciplina | 666 |
Altri autori (Persone) |
FoxKevin
HalbigMichael MathurSanjay |
Collana |
Ceramic Engineering and Science Proceedings
Ceramic engineering and science proceedings |
Soggetto topico | Ceramic materials |
Soggetto genere / forma | Electronic books. |
ISBN |
1-118-21753-5
1-283-86958-6 1-118-53038-1 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Ceramic Materials for Energy Applications II; Contents; Preface; Introduction; Analytical Techniques for Li-S Batteries; Three New Approaches using Silicon in Three Valuable Energy Applications; Processing of Inert SiC Matrix with TRISO Coated Fuel by Liquid Phase Sintering; SiC-Coated HTR Fuel Particle Performance; Study of the Silicon Carbide Matrix Elaboration by Film Boiling Process; Processing of Ultrafine Beta-Silicon Carbide Powder by Silicon-Carbon Reaction; Characterization of Failure Behavior of Silicon Carbide Composites by Acoustic Emission
Recession of Silicon Carbide in Steam under Nuclear Plant LOCA Conditions up to 1400 °C The Effect of Temperature and Uniaxial Pressure on the Densification Behavior of Silica Aerogel Granules; Microstructural Analysis of Nuclear Grade Graphite Materials; A Model for Simulation of Coupled Microstructural and Compositional Evolution; Characterisation of Corrosion of Nuclear Metal Wastes Encapsulated in Magnesium Silicate Hydrate (MSH) Cement; Impact of Uranium and Thorium on High TiO2 Concentration Nuclear Waste Glasses; Author Index |
Record Nr. | UNINA-9910141357103321 |
Hoboken, N.J., : Wiley, 2013 | ||
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Lo trovi qui: Univ. Federico II | ||
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Ceramic materials for energy applications II [[electronic resource] ] : a collection of papers presented at the 36th International Conference on Advanced Ceramics and Composites, January 22-27, 2012, Daytona Beach, Florida / / edited by Kevin Fox ... [et al.] ; volume editors, Michael Halbig, Sanjay Mathur |
Pubbl/distr/stampa | Hoboken, N.J., : Wiley, 2013 |
Descrizione fisica | 1 online resource (195 p.) |
Disciplina | 666 |
Altri autori (Persone) |
FoxKevin
HalbigMichael MathurSanjay |
Collana |
Ceramic Engineering and Science Proceedings
Ceramic engineering and science proceedings |
Soggetto topico | Ceramic materials |
ISBN |
1-118-21753-5
1-283-86958-6 1-118-53038-1 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Ceramic Materials for Energy Applications II; Contents; Preface; Introduction; Analytical Techniques for Li-S Batteries; Three New Approaches using Silicon in Three Valuable Energy Applications; Processing of Inert SiC Matrix with TRISO Coated Fuel by Liquid Phase Sintering; SiC-Coated HTR Fuel Particle Performance; Study of the Silicon Carbide Matrix Elaboration by Film Boiling Process; Processing of Ultrafine Beta-Silicon Carbide Powder by Silicon-Carbon Reaction; Characterization of Failure Behavior of Silicon Carbide Composites by Acoustic Emission
Recession of Silicon Carbide in Steam under Nuclear Plant LOCA Conditions up to 1400 °C The Effect of Temperature and Uniaxial Pressure on the Densification Behavior of Silica Aerogel Granules; Microstructural Analysis of Nuclear Grade Graphite Materials; A Model for Simulation of Coupled Microstructural and Compositional Evolution; Characterisation of Corrosion of Nuclear Metal Wastes Encapsulated in Magnesium Silicate Hydrate (MSH) Cement; Impact of Uranium and Thorium on High TiO2 Concentration Nuclear Waste Glasses; Author Index |
Record Nr. | UNINA-9910830266403321 |
Hoboken, N.J., : Wiley, 2013 | ||
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Lo trovi qui: Univ. Federico II | ||
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Ceramic materials for energy applications II : a collection of papers presented at the 36th International Conference on Advanced Ceramics and Composites, January 22-27, 2012, Daytona Beach, Florida / / edited by Kevin Fox ... [et al.] ; volume editors, Michael Halbig, Sanjay Mathur |
Pubbl/distr/stampa | Hoboken, N.J., : Wiley, 2013 |
Descrizione fisica | 1 online resource (195 p.) |
Disciplina | 666 |
Altri autori (Persone) |
FoxKevin
HalbigMichael MathurSanjay |
Collana | Ceramic engineering and science proceedings |
Soggetto topico | Ceramic materials |
ISBN |
1-118-21753-5
1-283-86958-6 1-118-53038-1 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Ceramic Materials for Energy Applications II; Contents; Preface; Introduction; Analytical Techniques for Li-S Batteries; Three New Approaches using Silicon in Three Valuable Energy Applications; Processing of Inert SiC Matrix with TRISO Coated Fuel by Liquid Phase Sintering; SiC-Coated HTR Fuel Particle Performance; Study of the Silicon Carbide Matrix Elaboration by Film Boiling Process; Processing of Ultrafine Beta-Silicon Carbide Powder by Silicon-Carbon Reaction; Characterization of Failure Behavior of Silicon Carbide Composites by Acoustic Emission
Recession of Silicon Carbide in Steam under Nuclear Plant LOCA Conditions up to 1400 °C The Effect of Temperature and Uniaxial Pressure on the Densification Behavior of Silica Aerogel Granules; Microstructural Analysis of Nuclear Grade Graphite Materials; A Model for Simulation of Coupled Microstructural and Compositional Evolution; Characterisation of Corrosion of Nuclear Metal Wastes Encapsulated in Magnesium Silicate Hydrate (MSH) Cement; Impact of Uranium and Thorium on High TiO2 Concentration Nuclear Waste Glasses; Author Index |
Record Nr. | UNINA-9910877279303321 |
Hoboken, N.J., : Wiley, 2013 | ||
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Lo trovi qui: Univ. Federico II | ||
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Updating small generator interconnection procedures for new market conditions [[electronic resource] /] / Kevin Fox ... [and others] |
Pubbl/distr/stampa | Golden, Colo. : , : National Renewable Energy Laboratory, , [2012] |
Descrizione fisica | 1 online resource (iv, 49 pages) |
Altri autori (Persone) | FoxKevin |
Collana | NREL/TP |
Soggetto topico |
Electric power distribution - United States
Distributed generation of electric power - United States Interconnected electric utility systems - Law and legislation - United States |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910702457403321 |
Golden, Colo. : , : National Renewable Energy Laboratory, , [2012] | ||
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Lo trovi qui: Univ. Federico II | ||
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