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Journal of Nuclear Fuel Cycle and Waste Technology
| Journal of Nuclear Fuel Cycle and Waste Technology |
| Pubbl/distr/stampa | Daejeon, Korea : , : Korean Radioactive Waste Society, , 2013- |
| Descrizione fisica | 1 online resource |
| Soggetto topico |
Radioactive waste disposal
Radioactive wastes |
| Soggetto genere / forma | Periodicals. |
| ISSN | 2288-5471 |
| Formato | Materiale a stampa  |
| Livello bibliografico | Periodico |
| Lingua di pubblicazione | eng |
| Record Nr. | UNISA-996321214203316 |
| Daejeon, Korea : , : Korean Radioactive Waste Society, , 2013- | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. di Salerno | ||
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Logistikqualifikation und Mobile Learning : Das Anwendungsbeispiel der Learning-App MARTINA / / Matthias Klumpp (herusgegeber)
| Logistikqualifikation und Mobile Learning : Das Anwendungsbeispiel der Learning-App MARTINA / / Matthias Klumpp (herusgegeber) |
| Pubbl/distr/stampa | Berlin : , : Logos Verlag, , [2018] |
| Descrizione fisica | 1 online resource (486 pages) |
| Disciplina | 621.4838 |
| Collana | Dienstleistungsmanagement in Theorie und Praxis |
| Soggetto topico |
Radioactive waste disposal
Radioactive wastes |
| ISBN | 3-8325-9070-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | ger |
| Record Nr. | UNINA-9910793139903321 |
| Berlin : , : Logos Verlag, , [2018] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Logistikqualifikation und Mobile Learning : Das Anwendungsbeispiel der Learning-App MARTINA / / Matthias Klumpp (herusgegeber)
| Logistikqualifikation und Mobile Learning : Das Anwendungsbeispiel der Learning-App MARTINA / / Matthias Klumpp (herusgegeber) |
| Pubbl/distr/stampa | Berlin : , : Logos Verlag, , [2018] |
| Descrizione fisica | 1 online resource (486 pages) |
| Disciplina | 621.4838 |
| Collana | Dienstleistungsmanagement in Theorie und Praxis |
| Soggetto topico |
Radioactive waste disposal
Radioactive wastes |
| ISBN | 3-8325-9070-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | ger |
| Record Nr. | UNINA-9910812543703321 |
| Berlin : , : Logos Verlag, , [2018] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Low-level radioactive waste classification, characterization, and assessment [[microform] ] : waste streams and neutron-activated metals / / prepared by D.E. Robertson ... [and others]
| Low-level radioactive waste classification, characterization, and assessment [[microform] ] : waste streams and neutron-activated metals / / prepared by D.E. Robertson ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2000 |
| Descrizione fisica | xvii, 82 pages : digital, PDF file |
| Altri autori (Persone) | RobertsonD. E (David E.) |
| Soggetto topico |
Nuclear power plants - Waste disposal - United States
Radioactive waste disposal - United States Radioactive wastes |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Low-level radioactive waste classification, characterization, and assessment |
| Record Nr. | UNINA-9910697392203321 |
| Washington, DC : , : Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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NRC volume reduction policy
| NRC volume reduction policy |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1981 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Radioactive wastes
Low level radioactive waste disposal facilities |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715906803321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Nuclear materials [[electronic resource] /] / Michael P. Hemsworth, editor
| Nuclear materials [[electronic resource] /] / Michael P. Hemsworth, editor |
| Pubbl/distr/stampa | Hauppauge, N.Y., : Nova Science Publishers, 2011 |
| Descrizione fisica | 1 online resource (238 p.) |
| Disciplina | 621.48/33 |
| Altri autori (Persone) | HemsworthMichael P |
| Collana |
Physics research and technology
Materials science and technologies |
| Soggetto topico |
Nuclear reactors - Materials
Nuclear chemistry Radioactive wastes |
| Soggetto genere / forma | Electronic books. |
| ISBN | 1-62081-968-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910453210403321 |
| Hauppauge, N.Y., : Nova Science Publishers, 2011 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Nuclear materials [[electronic resource] /] / Michael P. Hemsworth, editor
| Nuclear materials [[electronic resource] /] / Michael P. Hemsworth, editor |
| Pubbl/distr/stampa | Hauppauge, N.Y., : Nova Science Publishers, 2011 |
| Descrizione fisica | 1 online resource (238 p.) |
| Disciplina | 621.48/33 |
| Altri autori (Persone) | HemsworthMichael P |
| Collana |
Physics research and technology
Materials science and technologies |
| Soggetto topico |
Nuclear reactors - Materials
Nuclear chemistry Radioactive wastes |
| ISBN | 1-62081-968-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910779603203321 |
| Hauppauge, N.Y., : Nova Science Publishers, 2011 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Nuclear materials [[electronic resource] /] / Michael P. Hemsworth, editor
| Nuclear materials [[electronic resource] /] / Michael P. Hemsworth, editor |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | Hauppauge, N.Y., : Nova Science Publishers, 2011 |
| Descrizione fisica | 1 online resource (238 p.) |
| Disciplina | 621.48/33 |
| Altri autori (Persone) | HemsworthMichael P |
| Collana |
Physics research and technology
Materials science and technologies |
| Soggetto topico |
Nuclear reactors - Materials
Nuclear chemistry Radioactive wastes |
| ISBN | 1-62081-968-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Intro -- NUCLEAR MATERIALS -- NUCLEAR MATERIALS -- Contents -- Preface -- Co-Precipitation Model Coupled with Prediction Model for the Removal of Arsenic from Ground and Surface Waters Using Lanthanides -- Abstract -- 1. Introduction -- 1.1. Sources of Arsenic in Ground Water -- 1.2. Removal of Arsenic through Adsorption on Solid Surfaces -- 1.3. Objectives of This Chapter -- 2. Background -- 2.1. Factors Influencing Arsenic Migration in Natural Waters -- Inorganic Carbon Concentration -- Phosphate and Silicate Concentration -- Organic Matter Content -- 2.2. Aqueous Speciation of Arsenic -- 2.3. Surface Speciation of Arsenic -- 2.4. Surface Complexation Models for Arsenic Adsorption -- 2.5. Solubility of Rare Earth Arsenates Compared to Arsenates of Other Ions -- Suitability of Calcium and Magnesium Arsenates -- Suitability of Iron (III) Arsenates -- Suitability of Lead Arsenates -- Suitability of Arsenates of Lanthanides and Actinides -- 3. Methods -- 3.1. Predictive Model for Arsenic Removal from Soil -- 3.1.1. Integrity of Data Used for Developing and Testing the Predictive Model -- 3.1.2. Integrity of Data Used in Model Fitting -- 3.1.3. Predictive Model Fitting -- 3.1.4. Measured Adsorption Surfaces as a Function of Soils Parameters -- 3.1.5. Adsorption Contours of Arsenic as a Function of Soil Parameters -- 3.1.6. Adsorption Envelops of Arsenic -- 3.2. Surface Precipitation Model for Arsenic Adsorption -- 3.2.1. Linear Free Energy Model -- 3.2.2. Model Adaptation for Surface Precipitation of Arsenic -- 3.2.3. Surface Precipitation Reactions -- 3.2.4. Calculating Equilibrium Surface Precipitation Constants -- 4. Results and Discussion -- 4.1. Fitted Predictive Model for Arsenic Adsorption -- 4.1.1. Validation of Prediction Model -- 4.2. Surface Precipitation of Arsenic onto Hydrated Oxides of Lanthanides and Actinides -- 5. Conclusions.
References -- Experimental Studies and First Principles Calculations in Nuclear Fuel Alloys for Research Reactors -- Abstract -- 1. Introduction -- 1.1. Role of Interaction Energies in U(Mo) Phase Stability -- 1.2. Interaction Layer between the U(Mo) Fuel and the Aluminum Matrix -- 1.2.1. The Pseudo-Binary Phase Diagram USi3-UAl3 as a Basis for the Characterization of The Reaction Layer in U-Mo/Al-Si Alloys Diffusion Couples -- 1.2.2. Low Silicon U(Al,Si)3 Stabilization by Zr Addition -- 1.2.3. UAl3-Al Interaction Layer Growth -- 1.3. U-Al System and UAl4 Stability -- 1.4. Monolithic Fuel -- 2. Modeling Tools -- 2.1. First-Principles Calculations of Thermodynamic Properties of Ordered Solids -- 2.2. First-Principles Calculations of Thermodynamics of Disordered Solids. The Cluster Expansion Formalism -- 2.3. CALPHAD Modeling of Thermodynamics -- 2.4. CALPHAD Modeling of Atomic Mobility -- 3. Results and Discussion -- 3.1. Cluster Expansion in the Bcc U-Mo System. U(Mo) Phase Stability -- 3.2. UAl3 Stabilization by Si Addition. UAl3-USi3 Pseudobinary System Ground State -- 3.3. Low Silicon U(Al,Si)3 Stabilization by Zr Addition. Experimental Results -- 3.4. Kinetics of Interaction Layer Growth in an UAl3/Al Diffusion Couple -- 3.5. U-Al System and UAl4 Stability -- 3.6. Elastic Constants of (U(Mo) Alloys -- Conclusion -- Acknowledgments -- References -- Radiation Damage and Recovery of Crystals: Frenkel vs. Schottky Defect Production -- Abstract -- 1. Introduction -- 2. Irradiation Creep -- 2.1. SIPA and SIPE Mechanisms of Creep -- 2.2. Radiation-Induced Emission of Vacancies from Extended Defects -- 2.2.1. Unstable Frenkel Pairs -- 2.2.2. Focusons -- 2.2.3. Quodons -- 2.3. Creep Due to Radiation and Stress Induced Preference in Emission (RSIPE) -- 2.4. SIPE vs. SIPA Summary -- 3. Irradiation Swelling. 3.1. Experimental Observations of the Radiation-Induced Void Annealing -- 3.1.1. Irradiation of Nickel with Cr Ions -- 3.1.2. Irradiation of Nickel with Protons -- 3.1.3. Irradiation of Copper with Protons -- 3.2. Quodon Model of the Radiation-Induced Void Annealing -- 4. Void Lattice Formation -- 5. Conclusion -- Acknowledgments -- References -- Fuel Restructuring and Actinide Radial Redistributions in Americium-Containing Uranium-Plutonium Mixed Oxide Fuels Irradiated in a Fast Reactor -- Abstract -- 1. Introduction -- 2. Experimental -- 2.1. Fuel Fabrication -- 2.2. Irradiation Conditions -- 2.4. Post-Irradiation Examinations (PIEs) -- 3. Results and Discussion -- 3.1. NDES for B14 Test -- 3.1.1. Nondestructive Observation by X-Ray CT -- 3.2. Destructive Examinations -- 3.2.1. Observation of Fuel Microstructure -- 3.2.2. Axial Distribution of Central Void Diameter -- 3.2.3. Dependence of Linear Heating Rate on Fuel Restructuring -- 3.2.4. Radial Redistribution of Fuel Constituents -- 4. Summary -- References -- Microstructural Characterization of Structural Materials of Pressurized Heavy Water Reactor -- Abstract -- Introduction -- 2. Experimental Details -- 2.1. Specimen Preparation -- 2.1.1. Powdered and Cold Worked Samples -- 2.1.2. Irradiation of Zircaloy-2, Zr-1%Nb-1%Sn-0.1Fe, Zr-1Nb, using Light Ion (Proton) and Heavy Ions (O5+ or Ne6+) -- 2.2. Data Collection for XRD Analysis -- 3. Method of Analysis -- 3.1. Warren Averbach Technique -- 3.1. Williamson-Hall Technique -- 3.2. Modified Rietveld Technique -- 3.3. Simplified Breadth Method -- 3.4. Double Voigt Technique -- 3.5. MarqX Method -- 3.6. Evaluation of Dislocation Density in a Material -- 4. Results and Discussion -- 4.1. Analysis of Deformed Powdered Sample -- 4.2. Analysis of Cold Rolled Sample -- 4.3. Analysis of Irradiated Samples -- 5. Conclusion -- References. Current Trends in Mathematical Modeling and Simulation of Fission Product Transport from Fuel to Primary Coolant of PWRs -- Abstract -- Glossary -- 1. Introduction -- 2. Experimental Efforts -- 2.1. In-Pile Tests -- 2.2. Out-of-Pile Tests -- 3. Review of Fission Product Activity Simulation Codes -- 4. Kinetic Modeling -- 4.1. Computational Scheme -- 4.2. Steady State Analysis -- 4.3. Power Perturbations -- 4.4. Flow-Rate Transients -- 5. Stochastic Modeling -- 6. Conclusions -- References -- Recent Advances in Molecular Dynamics Modelling of Radiation Effects in -Zr -- Abstract -- 1. Introduction -- 2. Simulation Technique -- 2.1. MD Method -- 2.2. Modelling the Cascade Ballistic Stage -- 2.3. Identification of Point Defects and Point Defect Clusters -- 3. Number of Frenkel Pairs -- 4. Fraction of Point Defects in Point Defect Clusters -- 5. Typical Point Defect Clusters Found in Displacement Cascades -- 5.1. SIA Clusters -- 5.2. Vacancy Clusters -- 6. Atomic-Scale Modelling of Edge -- Dislocations in α-Zirconium -- 6.1. Simulation Technique and Identification of Dislocation Core -- 6.2. Atomic Displacement and Structure of Dislocation Core -- 6.3. Peierls Stress and Dislocation Core Energy -- 7. Interaction of 1/3< -- 112‾0> -- (0001) Edge Dislocations with Point Defect Clusters Created in Displacement -- Cascades in α-Zr -- 7.1. Interaction with Triangular SIA Cluster in Basal Plane -- 7.2. Interaction with Irregular 3D SIA Cluster -- 7.3. Interaction with Prismatic Vacancy Loop -- 7.4. Interaction with Pyramid Vacancy Cluster -- 8. Interaction of 1/3< -- [112‾0](11‾00)} Edge Dislocations with Point Defect Clusters Found in Collision -- Cascades in α-Zirconium -- 8.1. Interaction with Triangular SIA Cluster in Basal Plane -- 8.2. Interaction with Irregular 3D SIA Point Defect Cluster -- 8.3. Interaction with SIA Dislocation Loops. 9. Summary -- References -- Index. |
| Record Nr. | UNINA-9910812520903321 |
| Hauppauge, N.Y., : Nova Science Publishers, 2011 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Oceanography : joint hearing before the Military Research and Development Subcommittee of the Committee on National Security and the Fisheries, Wildlife, and Oceans Subcommittee of the Committee on Resources, House of Representatives, One Hundred Fourth Congress, first session, hearing held December 6, 1995
| Oceanography : joint hearing before the Military Research and Development Subcommittee of the Committee on National Security and the Fisheries, Wildlife, and Oceans Subcommittee of the Committee on Resources, House of Representatives, One Hundred Fourth Congress, first session, hearing held December 6, 1995 |
| Pubbl/distr/stampa | Washington : , : U.S. Government Printing Office, , 1996 |
| Descrizione fisica | 1 online resource (vi, 187 pages) : illustrations |
| Soggetto topico |
Radioactive wastes
Radioactive waste disposal in the ocean Oceanography - Research - United States |
| Soggetto genere / forma | Legislative hearings. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Oceanography |
| Record Nr. | UNINA-9910714383903321 |
| Washington : , : U.S. Government Printing Office, , 1996 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Permeability of covers over low-level radioactive-waste burial trenches, West Valley, Cattaraugus County, New York / / by David E. Prudic
| Permeability of covers over low-level radioactive-waste burial trenches, West Valley, Cattaraugus County, New York / / by David E. Prudic |
| Autore | Prudic David E. |
| Pubbl/distr/stampa | Albany, New York : , : U.S. Geological Survey, , 1980 |
| Descrizione fisica | 1 online resource (v, 35 pages) : illustrations, 1 map |
| Collana | Water-resources investigations |
| Soggetto topico |
Radioactive waste disposal in the ground - New York (State) - Cattaraugus County
Radioactive wastes - New York (State) - Cattaraugus County Soil permeability Radioactive waste disposal in the ground Radioactive wastes |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715138803321 |
Prudic David E.
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| Albany, New York : , : U.S. Geological Survey, , 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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