Top
Note: Supplemental materials are not guaranteed with Rental or Used book purchases.
Purchase Benefits
Free Shipping On Orders Over $35!
Get Rewarded for Ordering Your Textbooks! Enroll Now
Customer Reviews Read Reviews
Write a Review
What is included with this book?
| National and International Programs | |
| The UK National Nuclear Laboratory and Waste Management R&D | p. 3 |
| Opportunities for Research in the UK for Decommissioning and Disposal | p. 15 |
| t Overview of the CEA French Research Program on Nuclear Waste | p. 21 |
| Disposal Concepts | |
| Disposability of the UK's Intermediate Level Wastes | p. 35 |
| Experience in Progressing the Planning Application for New LLW Disposal Facilities for Dounreay | p. 43 |
| Deep Borehole Disposal of Plutonium | p. 51 |
| Stability of Cubic Zirconia in a Granitic System Under High Pressure and Temperature | p. 59 |
| Inner Material Requirements and Candidates Screening for Spent Fuel Disposal Canister | p. 67 |
| Characterization of Partial Melting and Solidification of Granite E93/7 by the Acoustic Emission Technique | p. 75 |
| A Model for Predicting the Temperature Distribution Around Radioactive Waste Containers in Very Deep Geological Boreholes | p. 83 |
| ILW Wasteforms | |
| The Use of Activated Slags as Immobilization Matrices for ILW | p. 93 |
| Durability of a Cementitious Wasteform for Intermediate Level Waste | p. 101 |
| Thermodynamic Simulation and Experimental Study of Irradiated Reactor Graphite Waste Processing with REE Oxides | p. 109 |
| The Role and Management of Free Water in the Production of Durable Radioactive Waste Products Using Hydraulic Cements | p. 117 |
| Evaluation of Durability of Mortars and Concretes Used in Ancient Structures | p. 127 |
| The Immobilization of Clinoptilolite within Cementitious Systems | p. 135 |
| Investigation on the Immobilization of Carbon in OPC-BFS and OPC-PFA Systems | p. 143 |
| Processes Related to the Water Uptake by EUROBITUM Bituminized Radioactive Waste: Theoretical Considerations and First Experimental Results | p. 151 |
| What Will We Do with the Low Level Waste From Reactor Decommissioning? | p. 161 |
| Cement Based Encapsulation Trials for Low-Level Radioactive Effluent Containing Nitrate Salts | p. 173 |
| Glasses and Glass Composite Materials | |
| High Level Waste (HLW) Vitrification Experience in the U.S.A.: Application of Glass Product/Process Control to Other HLW and Hazardous Wastes | p. 183 |
| Nuclear Waste Immobilization by Vitrification in a Cold Crucible Melter: 3D Magnetic Model of a Melter | p. 191 |
| NMR Investigation of Cation Distribution in HLW Wasteform Glass | p. 199 |
| Changes to Alkali Ion Content Adjacent to Crystal- Glass Interfaces | p. 207 |
| A Mossbauer Study of Iron in Vitrified Wastes | p. 215 |
| In Situ Characterization of Model UK Nuclear Waste Glasses by X-ray Absorption Spectroscopy Under Process Conditions | p. 223 |
| Glass Formulation Development in Support of Melter Testing to Demonstrate Enhanced High Level Waste Throughput 231 | |
| Electron Irradiation and Electron Tomography Studies of Glasses and Glass Nanocomposites | p. 239 |
| Glass Composite Materials for Nuclear and Hazardous Waste Immobilization | p. 245 |
| Waste Loading of Actinide Chloride Surrogates in an Iron Phosphate Glass | p. 253 |
| Devitrified and Phase Separated Material Found in Simulated High Level Nuclear Waste Glasses Containing Ca and Zn Additions | p. 261 |
| Cold Crucible Vitrification of Uranium-Bearing High Level Waste Surrogate | p. 269 |
| Leaching | |
| Immobilization of Radioactive Iodine Using AgI Vitrification Technique for the TRU Wastes Disposal: Evaluation of Leaching and Surface Properties | p. 279 |
| Determination of the Forward Rate of Dissolution for SON68 and PAMELA Glasses in Contact with Alkaline Solutions | p. 287 |
| Single Idealized Cracks: A Tool for Understanding Fractured Glass Block Leaching | p. 295 |
| Accelerated Weathering of Composite Cements Used for Immobilization | p. 305 |
| Mechanistic Investigation of Internal Corrosion in Nuclear Waste Containers Over Extended Time Periods | p. 313 |
| Ceramic Wasteforms | |
| BIPed Tailored Ceramic Waste Forms for the Immobilization of Cs and Sr | p. 323 |
| Neutron and Resonant X-ray Diffraction Studies of Zirconolite-2M | p. 331 |
| Effect of Gallium Oxide on Phase Assemblage in Apatite and Whitlockite Hosts for Waste Immobilization | p. 339 |
| High Temperature Behavior of Polyoxometalates Containing Lanthanides | p. 347 |
| Immobilization of Liquid Radioactive Waste in Mineral-Like Matrices Derived From Inorganic Cenosphere-Based Sorbents as Precursors | p. 355 |
| Synthesis and Characterization of Ln[subscript 2]TiO[subscript 5] Compounds | p. 365 |
| Radiation Effects in Ceramics | |
| Characterization of 20 Year Old Pu[superscript 238]-Doped Synroc C | p. 373 |
| Self-Irradiation of Ceramics and Single Crystals Doped with Pu-238: Summary of 5 Years of Research of the V. G. Khlopin Radium Institute | p. 381 |
| Alpha-Decay Damage in Muratalte-Based Ceramics | p. 389 |
| Plutonium Wasteforms | |
| Plutonium Feed Impurity Testing in Lanthanide Borosilicate (LaBS) Glass | p. 397 |
| Development of Borosilicate Glass Compositions for the Immobilization of the UK's Separated Plutonium Stocks | p. 405 |
| Towards a Single Host Phase Ceramic Formulation for UK Plutonium Disposition | p. 413 |
| The Use of Surrogates in Waste Immobilization Studies: A Case Study of Plutonium | p. 421 |
| Durability of Borosilicate Glass Compositions for the Immobilization of the UK's Separated Plutonium Stocks | p. 429 |
| Spent Nuclear Fuel | |
| RN Fractional Release of High Burn-Up Fuel: Effect of HBS and Estimation of Accessible Grain Boundary | p. 439 |
| Radionuclides Release From the Spent Fuel Under Disposal Conditions: Re-Evaluation of the Instant Release Fraction | p. 447 |
| Np-Incorporation Into K-Boltwoodite | p. 455 |
| Engineered Barrier Systems I: Backfill and Buffer | |
| Uranium(VI) Uptake by Synthetic Calcium Silicate Hydrates | p. 467 |
| PHREEQC Modeling of Leaching of Major Elements and Heavy Metals From Cementitious Waste Forms | p. 475 |
| Changes on the Mineralogical and Physical Properties of FEBEX Bentonite Due to Its Contact with Hyperalkaline Pore Fluids in Infiltration Tests | p. 483 |
| A New Natural Analog Study of the Interaction of Low-Alkali Cement Leachates and the Bentonite Buffer of a Radioactive Waste Repository | p. 493 |
| Migration Behavior of Ferrous Ion in Compacted Bentonite Under Reducing Conditions Controlled with Potentiostat | p. 501 |
| Engineered Barrier Systems II: Containers | |
| Effect of Weak Acid Additions on the General and Localized Corrosion Susceptibility of Alloy 22 in Chloride Solutions | p. 511 |
| Waste Package Corrosion Studies Using Small Mockup Experiments | p. 519 |
| Repassivation Potential of Alloy 22 in Sodium and Calcium Chloride Brines | p. 527 |
| Apparent Inversion of the Effect of Alloyed Molybdenum for Corrosion of Ordinary and Enhanced 316L Stainless Steel in Sulfuric Acid | p. 537 |
| Mobilization, Migration and Retention | |
| Grimsel Test Site - Phase VI: Review of Accomplishments and Next Generation of In Situ Experiments Under Repository Relevant Boundary Conditions | p. 547 |
| Molecular Characterization of Dissolved Organic Matter (DOM) in Groundwaters From the Aspo Underground Research Laboratory, Sweden: A Novel "Finger Printing" Tool for Palaeohydrological Assessment | p. 557 |
| Modeling of Radionuclide Migration Through Fractured Rock in a HLW Respository with Multiple Canisters | p. 567 |
| A New Method for Real-Time Monitoring of Grout Spread Through Fractured Rocks | p. 577 |
| Observation of Diffusion Behavior of Trace Elements in Hardened Cement Pastes by LA-ICP-MS | p. 585 |
| Magnetite Sorption Capacity for Strontium as a Function of pH | p. 593 |
| Kinetics of UO[subscript 2](s) Dissolution in the Presence of Hypochlorite, Chlorite, and Chlorate Solutions | p. 599 |
| Long-Term Predictions of the Concentration of [alpha]-isosaccharlnlc Acid in Cement Pore Water | p. 605 |
| Release Behavior of Sr-90 From Hydraulically Retrieved ILW Sludge | p. 613 |
| Radionuclide Retardation in Granitic Rocks by Matrix Diffusion and Sorption | p. 621 |
| Modeling Transport of [superscript 14]C-Labeled Natural Organic Matter (NOM) in Boom Clay | p. 629 |
| Release of U, REE and Th From Palmottu Granite | p. 637 |
| Comparative Analysis of Results From Deterministic Calculations of the Release of Radioactivity From Geological Disposal of Spent Fuel in Crystalline Rocks | p. 645 |
| Performance Assessment | |
| Development and Validation of a Model of Uranium Release to Groundwater From Legacy Disposals at the UK Low Level Waste Repository | p. 657 |
| Near-Field Modeling in the Safety Assessment SR-Can | p. 665 |
| Illustration of HLW Repository Performance: Using Alternative Yardsticks to Assess Modeled Radionuclide Fluxes | p. 673 |
| Characterization of Radionuclide Migration and Plant Uptake for Performance Assessment | p. 681 |
| Evaluating Chemical Toxicity of Surface Disposal of LILW-SL in Belgium | p. 689 |
| Author Index | p. 703 |
| Subject Index | p. 709 |
| Table of Contents provided by Blackwell. All Rights Reserved. |
The New copy of this book will include any supplemental materials advertised. Please check the title of the book to determine if it should include any access cards, study guides, lab manuals, CDs, etc.
The Used, Rental and eBook copies of this book are not guaranteed to include any supplemental materials. Typically, only the book itself is included. This is true even if the title states it includes any access cards, study guides, lab manuals, CDs, etc.
Need Help? Copyright © 1999-2024