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Scientific Basis for Nuclear Waster Management Xxxi

, by Grimes, R. W.; Roberts, J. W.; Hyatt, N. C.; Lee, W. E.

Scientific Basis for Nuclear Waster Management Xxxi by Grimes, R. W.; Roberts, J. W.; Hyatt, N. C.; Lee, W. E., 9781605110790

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ISBN: 9781605110790 | 1605110795
Cover: Hardcover
Copyright: 6/26/2008

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Summary

Table of Contents

Supplemental Materials

This volume, the most recent in a popular and longstanding proceedings series, offers an overview of the status of the UK's clean-up program and reviews international research programs including those in Europe and the United States.

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.

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