Environmental issues and waste management technologies in the ceramic and nuclear industries IX [[electronic resource] ] : proceedings of the Science and Technology in Addressing Environmental Issues in the Ceramic Industry and Ceramic Science and Technology for the Nuclear Industry symposia at the American Ceramic Society 105th annual meeting & exposition held April 27-30, 2003 in Nashville, Tennessee / / edited by John D. Vienna, Dane R. Spearing |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2004 |
Descrizione fisica | 1 online resource (400 p.) |
Disciplina |
666.0286
666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
SpearingDane Robert |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
Soggetto genere / forma | Electronic books. |
ISBN |
1-280-67490-3
9786613651839 1-118-40700-8 1-118-40702-4 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX; Contents; Preface; Ceramics for Waste or Nuclear Applications; Uranium Valences in Perovskite, CaTiO3; Iron-Substituted Barium Hollandite Ceramics for Cesium Immobilization; Hollandite-RichTitanate Ceramics Prepared by Melting in Air; Hyperfine Interaction Study of Short Range Order in Zircon; Scale-Up of Lithium Aluminate Pellet Manufacturing with a Flowable Powder; Melter Processing and Process Monitoring; Laboratory Measurement of Glass Melting Rate; Analysis of Feed Melting Processes
Electron Equivalents Redox Model for High Level Waste VitrificationSulfate Retention During Waste Glass Melting; The Characterization and Dissolution of High Level Waste Calcine in Alkali Borosilicate Glass; Summary of Results from 786-A Minimelter Run with Marcobatch 3 (Sludge Batch 2) Baseline Feed Using Frit 320; Numerical Models of Waste Glass Melters Part I - Lumped Parameter Analyses of DWPF; Numerical Models of Waste Glass Melters Part II - Computational Modeling of DWPF Tailored Electrical Driving as a Means of Controlling Heat Distribution and Convection Patterns in Joule-Heated Waste Glass MeltersEffects of Poly(Acrylic Acid) on the Rheological Properties of Aqueous Melter Feed Slurries for Nuclear Waste Vitrification; Frequency Modulated Continuous Wave Monitoring of Refractory Walls; Combustion Control Experimentations at a Pilot Scale Glass Furnace; Waste Vitrification Programs; Completion of the Vitrification Campaign at the West Valley Demonstration Project; Review of the French Vitrification Program Examination of DWPF Melter Materials After 8 Years of ServiceTesting to Demonstrate Regulatory Compliance of Glass Waste Forms for Immobilization of Radioactive Wastes at the Hanford Site; Cold Crucible Induction-Heated MelterTest Results with Surrogate DOE High-Level Wastes; Crucible-Scale Vitrification Studies with Hanford Tank AZ-102 High Sulfate-Containing Low Activity Waste; Glass Formulation and Property Models; Preliminary Glass Development and Testing for In-Container Vitrification of Hanford Low-Activity Waste; Evaluation of Melt Rate Through Higher Waste Loading Spinel Crystallization in HLW Glass Melts: Cation Exchange Systematics and the Role of Rh203 in Spinel FormationComposition Effects on the Vapor Hydration of Waste Glasses; Glass Composition-TCLP Response Model for Waste Glasses; Alternate Waste Forms and Processes; Iron Phosphate Glass for Immobilization of Hanford LAW; Characterization and Performance of Fluidized Bed Steam Reforming (FBSR) Product as a Final Waste Form; Microstructure of Emulsion-Based Polymeric Waste Forms for Encapsulating Low-Level, Radioactive and Toxic Metal Wastes Leach Resistance of Encapsulated Salts in Polymeric Waste Forms Fabricated Using an Aqueous-Based Route |
Record Nr. | UNINA-9910141264003321 |
Westerville, Ohio, : American Ceramic Society, c2004 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries IX [[electronic resource] ] : proceedings of the Science and Technology in Addressing Environmental Issues in the Ceramic Industry and Ceramic Science and Technology for the Nuclear Industry symposia at the American Ceramic Society 105th annual meeting & exposition held April 27-30, 2003 in Nashville, Tennessee / / edited by John D. Vienna, Dane R. Spearing |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2004 |
Descrizione fisica | 1 online resource (400 p.) |
Disciplina |
666.0286
666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
SpearingDane Robert |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
ISBN |
1-280-67490-3
9786613651839 1-118-40700-8 1-118-40702-4 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX; Contents; Preface; Ceramics for Waste or Nuclear Applications; Uranium Valences in Perovskite, CaTiO3; Iron-Substituted Barium Hollandite Ceramics for Cesium Immobilization; Hollandite-RichTitanate Ceramics Prepared by Melting in Air; Hyperfine Interaction Study of Short Range Order in Zircon; Scale-Up of Lithium Aluminate Pellet Manufacturing with a Flowable Powder; Melter Processing and Process Monitoring; Laboratory Measurement of Glass Melting Rate; Analysis of Feed Melting Processes
Electron Equivalents Redox Model for High Level Waste VitrificationSulfate Retention During Waste Glass Melting; The Characterization and Dissolution of High Level Waste Calcine in Alkali Borosilicate Glass; Summary of Results from 786-A Minimelter Run with Marcobatch 3 (Sludge Batch 2) Baseline Feed Using Frit 320; Numerical Models of Waste Glass Melters Part I - Lumped Parameter Analyses of DWPF; Numerical Models of Waste Glass Melters Part II - Computational Modeling of DWPF Tailored Electrical Driving as a Means of Controlling Heat Distribution and Convection Patterns in Joule-Heated Waste Glass MeltersEffects of Poly(Acrylic Acid) on the Rheological Properties of Aqueous Melter Feed Slurries for Nuclear Waste Vitrification; Frequency Modulated Continuous Wave Monitoring of Refractory Walls; Combustion Control Experimentations at a Pilot Scale Glass Furnace; Waste Vitrification Programs; Completion of the Vitrification Campaign at the West Valley Demonstration Project; Review of the French Vitrification Program Examination of DWPF Melter Materials After 8 Years of ServiceTesting to Demonstrate Regulatory Compliance of Glass Waste Forms for Immobilization of Radioactive Wastes at the Hanford Site; Cold Crucible Induction-Heated MelterTest Results with Surrogate DOE High-Level Wastes; Crucible-Scale Vitrification Studies with Hanford Tank AZ-102 High Sulfate-Containing Low Activity Waste; Glass Formulation and Property Models; Preliminary Glass Development and Testing for In-Container Vitrification of Hanford Low-Activity Waste; Evaluation of Melt Rate Through Higher Waste Loading Spinel Crystallization in HLW Glass Melts: Cation Exchange Systematics and the Role of Rh203 in Spinel FormationComposition Effects on the Vapor Hydration of Waste Glasses; Glass Composition-TCLP Response Model for Waste Glasses; Alternate Waste Forms and Processes; Iron Phosphate Glass for Immobilization of Hanford LAW; Characterization and Performance of Fluidized Bed Steam Reforming (FBSR) Product as a Final Waste Form; Microstructure of Emulsion-Based Polymeric Waste Forms for Encapsulating Low-Level, Radioactive and Toxic Metal Wastes Leach Resistance of Encapsulated Salts in Polymeric Waste Forms Fabricated Using an Aqueous-Based Route |
Record Nr. | UNISA-996212909103316 |
Westerville, Ohio, : American Ceramic Society, c2004 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. di Salerno | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries IX [[electronic resource] ] : proceedings of the Science and Technology in Addressing Environmental Issues in the Ceramic Industry and Ceramic Science and Technology for the Nuclear Industry symposia at the American Ceramic Society 105th annual meeting & exposition held April 27-30, 2003 in Nashville, Tennessee / / edited by John D. Vienna, Dane R. Spearing |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2004 |
Descrizione fisica | 1 online resource (400 p.) |
Disciplina |
666.0286
666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
SpearingDane Robert |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
ISBN |
1-280-67490-3
9786613651839 1-118-40700-8 1-118-40702-4 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX; Contents; Preface; Ceramics for Waste or Nuclear Applications; Uranium Valences in Perovskite, CaTiO3; Iron-Substituted Barium Hollandite Ceramics for Cesium Immobilization; Hollandite-RichTitanate Ceramics Prepared by Melting in Air; Hyperfine Interaction Study of Short Range Order in Zircon; Scale-Up of Lithium Aluminate Pellet Manufacturing with a Flowable Powder; Melter Processing and Process Monitoring; Laboratory Measurement of Glass Melting Rate; Analysis of Feed Melting Processes
Electron Equivalents Redox Model for High Level Waste VitrificationSulfate Retention During Waste Glass Melting; The Characterization and Dissolution of High Level Waste Calcine in Alkali Borosilicate Glass; Summary of Results from 786-A Minimelter Run with Marcobatch 3 (Sludge Batch 2) Baseline Feed Using Frit 320; Numerical Models of Waste Glass Melters Part I - Lumped Parameter Analyses of DWPF; Numerical Models of Waste Glass Melters Part II - Computational Modeling of DWPF Tailored Electrical Driving as a Means of Controlling Heat Distribution and Convection Patterns in Joule-Heated Waste Glass MeltersEffects of Poly(Acrylic Acid) on the Rheological Properties of Aqueous Melter Feed Slurries for Nuclear Waste Vitrification; Frequency Modulated Continuous Wave Monitoring of Refractory Walls; Combustion Control Experimentations at a Pilot Scale Glass Furnace; Waste Vitrification Programs; Completion of the Vitrification Campaign at the West Valley Demonstration Project; Review of the French Vitrification Program Examination of DWPF Melter Materials After 8 Years of ServiceTesting to Demonstrate Regulatory Compliance of Glass Waste Forms for Immobilization of Radioactive Wastes at the Hanford Site; Cold Crucible Induction-Heated MelterTest Results with Surrogate DOE High-Level Wastes; Crucible-Scale Vitrification Studies with Hanford Tank AZ-102 High Sulfate-Containing Low Activity Waste; Glass Formulation and Property Models; Preliminary Glass Development and Testing for In-Container Vitrification of Hanford Low-Activity Waste; Evaluation of Melt Rate Through Higher Waste Loading Spinel Crystallization in HLW Glass Melts: Cation Exchange Systematics and the Role of Rh203 in Spinel FormationComposition Effects on the Vapor Hydration of Waste Glasses; Glass Composition-TCLP Response Model for Waste Glasses; Alternate Waste Forms and Processes; Iron Phosphate Glass for Immobilization of Hanford LAW; Characterization and Performance of Fluidized Bed Steam Reforming (FBSR) Product as a Final Waste Form; Microstructure of Emulsion-Based Polymeric Waste Forms for Encapsulating Low-Level, Radioactive and Toxic Metal Wastes Leach Resistance of Encapsulated Salts in Polymeric Waste Forms Fabricated Using an Aqueous-Based Route |
Record Nr. | UNINA-9910830434803321 |
Westerville, Ohio, : American Ceramic Society, c2004 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries IX : proceedings of the Science and Technology in Addressing Environmental Issues in the Ceramic Industry and Ceramic Science and Technology for the Nuclear Industry symposia at the American Ceramic Society 105th annual meeting & exposition held April 27-30, 2003 in Nashville, Tennessee / / edited by John D. Vienna, Dane R. Spearing |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2004 |
Descrizione fisica | 1 online resource (400 p.) |
Disciplina | 666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
SpearingDane Robert |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
ISBN |
1-280-67490-3
9786613651839 1-118-40700-8 1-118-40702-4 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX; Contents; Preface; Ceramics for Waste or Nuclear Applications; Uranium Valences in Perovskite, CaTiO3; Iron-Substituted Barium Hollandite Ceramics for Cesium Immobilization; Hollandite-RichTitanate Ceramics Prepared by Melting in Air; Hyperfine Interaction Study of Short Range Order in Zircon; Scale-Up of Lithium Aluminate Pellet Manufacturing with a Flowable Powder; Melter Processing and Process Monitoring; Laboratory Measurement of Glass Melting Rate; Analysis of Feed Melting Processes
Electron Equivalents Redox Model for High Level Waste VitrificationSulfate Retention During Waste Glass Melting; The Characterization and Dissolution of High Level Waste Calcine in Alkali Borosilicate Glass; Summary of Results from 786-A Minimelter Run with Marcobatch 3 (Sludge Batch 2) Baseline Feed Using Frit 320; Numerical Models of Waste Glass Melters Part I - Lumped Parameter Analyses of DWPF; Numerical Models of Waste Glass Melters Part II - Computational Modeling of DWPF Tailored Electrical Driving as a Means of Controlling Heat Distribution and Convection Patterns in Joule-Heated Waste Glass MeltersEffects of Poly(Acrylic Acid) on the Rheological Properties of Aqueous Melter Feed Slurries for Nuclear Waste Vitrification; Frequency Modulated Continuous Wave Monitoring of Refractory Walls; Combustion Control Experimentations at a Pilot Scale Glass Furnace; Waste Vitrification Programs; Completion of the Vitrification Campaign at the West Valley Demonstration Project; Review of the French Vitrification Program Examination of DWPF Melter Materials After 8 Years of ServiceTesting to Demonstrate Regulatory Compliance of Glass Waste Forms for Immobilization of Radioactive Wastes at the Hanford Site; Cold Crucible Induction-Heated MelterTest Results with Surrogate DOE High-Level Wastes; Crucible-Scale Vitrification Studies with Hanford Tank AZ-102 High Sulfate-Containing Low Activity Waste; Glass Formulation and Property Models; Preliminary Glass Development and Testing for In-Container Vitrification of Hanford Low-Activity Waste; Evaluation of Melt Rate Through Higher Waste Loading Spinel Crystallization in HLW Glass Melts: Cation Exchange Systematics and the Role of Rh203 in Spinel FormationComposition Effects on the Vapor Hydration of Waste Glasses; Glass Composition-TCLP Response Model for Waste Glasses; Alternate Waste Forms and Processes; Iron Phosphate Glass for Immobilization of Hanford LAW; Characterization and Performance of Fluidized Bed Steam Reforming (FBSR) Product as a Final Waste Form; Microstructure of Emulsion-Based Polymeric Waste Forms for Encapsulating Low-Level, Radioactive and Toxic Metal Wastes Leach Resistance of Encapsulated Salts in Polymeric Waste Forms Fabricated Using an Aqueous-Based Route |
Altri titoli varianti |
Environmental issues and waste management technologies in the ceramic and nuclear industries nine
Environmental issues and waste management technologies in the ceramic and nuclear industries 9 |
Record Nr. | UNINA-9910877183903321 |
Westerville, Ohio, : American Ceramic Society, c2004 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries X [[electronic resource] ] : proceedings of the 106th Annual Meeting of the American Ceramic Society : Indianapolis, Indiana, USA (2004) / / editors, John Vienna, Connie Herman, Sharon Marra |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2005 |
Descrizione fisica | 1 online resource (282 p.) |
Disciplina |
666.0286
666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
HermanConnie MarraSharon |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
Soggetto genere / forma | Electronic books. |
ISBN |
1-280-67540-3
9786613652331 1-118-40843-8 1-118-40844-6 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries X; Contents; Preface; Nuclear and Hazardous Waste Forms and Fuels- Processing and Technology; Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant; Bubbling as a Means to Enhance Joule Heated Ceramic Melter Production Rates for Vitrifying Radioactive Wastes; High Level Waste Processing Experience with Increased Waste Loadings; DWPF Glass Air-Lift Pump Life Cycle Testing and Plant Implementation
Corrosion Resistance of Metal Electrodes in an Iron Phosphate MeltFluidized Bed Steam Reforming (FBSR) of Organic and Nitrate Containing Salt Supernate; Steam Reformation of Sodium Bearing Waste: Pros & Cons; ANSTO's Waste Form Research and Development Capabilities; Stabilization of Arsenic-Bearing Iron Hydroxide Solid Wastes in Polymeric Matrices; Effect of Thermal Treatment Conditions on Microstructure and Composition of High Temperature Reactor Fuel Kernel; Glass Waste Forms-Modelling, Properties, and Testing Predicting Phase Equilibria of Spinel-Forming Constituents in Waste Glass SystemsLiquidus Temperature and One Percent Crystal Content Models for Initial Hanford HLW Glasses; Dependency of Sulfate Solubility on Melt Composition and Melt Polymerization; Evaluation of Glass from The DWPF Melter; Redox Activity of Rhenium in Silicate Glasses; Analysis of Defense Waste Processing Facility Products with Laser Induced Breakdown Spectroscopy; The Structural Chemistry of Molybdenum in Model High Level Nuclear Waste Glasses, Investigated by MO K-Edge X-Ray Absorption Spectroscopy Ceramic Waste Forms-Formulation and TestingAlpha Decay Damage in Ceramic Waste Forms-Microstructural Aspect; Charge Compensation in Ca(La)TiO3 Solid Solutions; Hollandite Ceramics: Effect of Composition on Melting Temperature; Chemical Durability of Iron-Substituted Hollandite Ceramics for Cesium Immobilization; Titanate Ceramics for Immobilization of U-Rich Wastes; Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams; Solidification of Sodium Bearing Waste Using Hydroceramic and Portland Cement Binders Grout Formulations For Closing Hanford High-Level Waste Tanks- Bench-Scale StudyChemical Solution Deposition of CaCu3Ti4O12 Thin Films; Author Index; Keyword Index |
Record Nr. | UNINA-9910141450403321 |
Westerville, Ohio, : American Ceramic Society, c2005 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries X [[electronic resource] ] : proceedings of the 106th Annual Meeting of the American Ceramic Society : Indianapolis, Indiana, USA (2004) / / editors, John Vienna, Connie Herman, Sharon Marra |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2005 |
Descrizione fisica | 1 online resource (282 p.) |
Disciplina |
666.0286
666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
HermanConnie MarraSharon |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
ISBN |
1-280-67540-3
9786613652331 1-118-40843-8 1-118-40844-6 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries X; Contents; Preface; Nuclear and Hazardous Waste Forms and Fuels- Processing and Technology; Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant; Bubbling as a Means to Enhance Joule Heated Ceramic Melter Production Rates for Vitrifying Radioactive Wastes; High Level Waste Processing Experience with Increased Waste Loadings; DWPF Glass Air-Lift Pump Life Cycle Testing and Plant Implementation
Corrosion Resistance of Metal Electrodes in an Iron Phosphate MeltFluidized Bed Steam Reforming (FBSR) of Organic and Nitrate Containing Salt Supernate; Steam Reformation of Sodium Bearing Waste: Pros & Cons; ANSTO's Waste Form Research and Development Capabilities; Stabilization of Arsenic-Bearing Iron Hydroxide Solid Wastes in Polymeric Matrices; Effect of Thermal Treatment Conditions on Microstructure and Composition of High Temperature Reactor Fuel Kernel; Glass Waste Forms-Modelling, Properties, and Testing Predicting Phase Equilibria of Spinel-Forming Constituents in Waste Glass SystemsLiquidus Temperature and One Percent Crystal Content Models for Initial Hanford HLW Glasses; Dependency of Sulfate Solubility on Melt Composition and Melt Polymerization; Evaluation of Glass from The DWPF Melter; Redox Activity of Rhenium in Silicate Glasses; Analysis of Defense Waste Processing Facility Products with Laser Induced Breakdown Spectroscopy; The Structural Chemistry of Molybdenum in Model High Level Nuclear Waste Glasses, Investigated by MO K-Edge X-Ray Absorption Spectroscopy Ceramic Waste Forms-Formulation and TestingAlpha Decay Damage in Ceramic Waste Forms-Microstructural Aspect; Charge Compensation in Ca(La)TiO3 Solid Solutions; Hollandite Ceramics: Effect of Composition on Melting Temperature; Chemical Durability of Iron-Substituted Hollandite Ceramics for Cesium Immobilization; Titanate Ceramics for Immobilization of U-Rich Wastes; Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams; Solidification of Sodium Bearing Waste Using Hydroceramic and Portland Cement Binders Grout Formulations For Closing Hanford High-Level Waste Tanks- Bench-Scale StudyChemical Solution Deposition of CaCu3Ti4O12 Thin Films; Author Index; Keyword Index |
Record Nr. | UNISA-996212928803316 |
Westerville, Ohio, : American Ceramic Society, c2005 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. di Salerno | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries X [[electronic resource] ] : proceedings of the 106th Annual Meeting of the American Ceramic Society : Indianapolis, Indiana, USA (2004) / / editors, John Vienna, Connie Herman, Sharon Marra |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2005 |
Descrizione fisica | 1 online resource (282 p.) |
Disciplina |
666.0286
666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
HermanConnie MarraSharon |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
ISBN |
1-280-67540-3
9786613652331 1-118-40843-8 1-118-40844-6 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries X; Contents; Preface; Nuclear and Hazardous Waste Forms and Fuels- Processing and Technology; Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant; Bubbling as a Means to Enhance Joule Heated Ceramic Melter Production Rates for Vitrifying Radioactive Wastes; High Level Waste Processing Experience with Increased Waste Loadings; DWPF Glass Air-Lift Pump Life Cycle Testing and Plant Implementation
Corrosion Resistance of Metal Electrodes in an Iron Phosphate MeltFluidized Bed Steam Reforming (FBSR) of Organic and Nitrate Containing Salt Supernate; Steam Reformation of Sodium Bearing Waste: Pros & Cons; ANSTO's Waste Form Research and Development Capabilities; Stabilization of Arsenic-Bearing Iron Hydroxide Solid Wastes in Polymeric Matrices; Effect of Thermal Treatment Conditions on Microstructure and Composition of High Temperature Reactor Fuel Kernel; Glass Waste Forms-Modelling, Properties, and Testing Predicting Phase Equilibria of Spinel-Forming Constituents in Waste Glass SystemsLiquidus Temperature and One Percent Crystal Content Models for Initial Hanford HLW Glasses; Dependency of Sulfate Solubility on Melt Composition and Melt Polymerization; Evaluation of Glass from The DWPF Melter; Redox Activity of Rhenium in Silicate Glasses; Analysis of Defense Waste Processing Facility Products with Laser Induced Breakdown Spectroscopy; The Structural Chemistry of Molybdenum in Model High Level Nuclear Waste Glasses, Investigated by MO K-Edge X-Ray Absorption Spectroscopy Ceramic Waste Forms-Formulation and TestingAlpha Decay Damage in Ceramic Waste Forms-Microstructural Aspect; Charge Compensation in Ca(La)TiO3 Solid Solutions; Hollandite Ceramics: Effect of Composition on Melting Temperature; Chemical Durability of Iron-Substituted Hollandite Ceramics for Cesium Immobilization; Titanate Ceramics for Immobilization of U-Rich Wastes; Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams; Solidification of Sodium Bearing Waste Using Hydroceramic and Portland Cement Binders Grout Formulations For Closing Hanford High-Level Waste Tanks- Bench-Scale StudyChemical Solution Deposition of CaCu3Ti4O12 Thin Films; Author Index; Keyword Index |
Record Nr. | UNINA-9910830296503321 |
Westerville, Ohio, : American Ceramic Society, c2005 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
Environmental issues and waste management technologies in the ceramic and nuclear industries X : proceedings of the 106th Annual Meeting of the American Ceramic Society : Indianapolis, Indiana, USA (2004) / / editors, John Vienna, Connie Herman, Sharon Marra |
Pubbl/distr/stampa | Westerville, Ohio, : American Ceramic Society, c2005 |
Descrizione fisica | 1 online resource (282 p.) |
Disciplina | 666/.028/6 |
Altri autori (Persone) |
ViennaJohn David
HermanConnie MarraSharon |
Collana | Ceramic transactions |
Soggetto topico |
Ceramic industries - Environmental aspects
Nuclear facilities - Environmental aspects Ceramic industries - Waste disposal Ceramic materials - Environmental aspects Radioactive waste disposal |
ISBN |
1-280-67540-3
9786613652331 1-118-40843-8 1-118-40844-6 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries X; Contents; Preface; Nuclear and Hazardous Waste Forms and Fuels- Processing and Technology; Vitrification Testing and Demonstration for the Hanford Waste Treatment and Immobilization Plant; Bubbling as a Means to Enhance Joule Heated Ceramic Melter Production Rates for Vitrifying Radioactive Wastes; High Level Waste Processing Experience with Increased Waste Loadings; DWPF Glass Air-Lift Pump Life Cycle Testing and Plant Implementation
Corrosion Resistance of Metal Electrodes in an Iron Phosphate MeltFluidized Bed Steam Reforming (FBSR) of Organic and Nitrate Containing Salt Supernate; Steam Reformation of Sodium Bearing Waste: Pros & Cons; ANSTO's Waste Form Research and Development Capabilities; Stabilization of Arsenic-Bearing Iron Hydroxide Solid Wastes in Polymeric Matrices; Effect of Thermal Treatment Conditions on Microstructure and Composition of High Temperature Reactor Fuel Kernel; Glass Waste Forms-Modelling, Properties, and Testing Predicting Phase Equilibria of Spinel-Forming Constituents in Waste Glass SystemsLiquidus Temperature and One Percent Crystal Content Models for Initial Hanford HLW Glasses; Dependency of Sulfate Solubility on Melt Composition and Melt Polymerization; Evaluation of Glass from The DWPF Melter; Redox Activity of Rhenium in Silicate Glasses; Analysis of Defense Waste Processing Facility Products with Laser Induced Breakdown Spectroscopy; The Structural Chemistry of Molybdenum in Model High Level Nuclear Waste Glasses, Investigated by MO K-Edge X-Ray Absorption Spectroscopy Ceramic Waste Forms-Formulation and TestingAlpha Decay Damage in Ceramic Waste Forms-Microstructural Aspect; Charge Compensation in Ca(La)TiO3 Solid Solutions; Hollandite Ceramics: Effect of Composition on Melting Temperature; Chemical Durability of Iron-Substituted Hollandite Ceramics for Cesium Immobilization; Titanate Ceramics for Immobilization of U-Rich Wastes; Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams; Solidification of Sodium Bearing Waste Using Hydroceramic and Portland Cement Binders Grout Formulations For Closing Hanford High-Level Waste Tanks- Bench-Scale StudyChemical Solution Deposition of CaCu3Ti4O12 Thin Films; Author Index; Keyword Index |
Altri titoli varianti |
Environmental issues and waste management technologies in the ceramic and nuclear industries ten
Environmental issues and waste management technologies in the ceramic and nuclear industries 10 |
Record Nr. | UNINA-9910876758503321 |
Westerville, Ohio, : American Ceramic Society, c2005 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|