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Scientific Basis for Nuclear Waste Management

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Cover of 'Scientific Basis for Nuclear Waste Management'

Table of Contents

  1. Altmetric Badge
    Book Overview
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    Chapter 1 Remarks About Department of Energy Policy on High-Level Nuclear Waste Management
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    Chapter 2 Regulation of Geologic Repositories for the Disposal of High-Level Radioactive Wastes
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    Chapter 3 Survey of High-Level Radioactive Waste Forms and Their Role in Waste Management
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    Chapter 4 Radioactive Waste Disposal in Geological Formations: Research Activities of the Commission of the European Communities
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    Chapter 5 Development of Solid Radionuclide Waste Forms in the United States
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    Chapter 6 The Environmental Effects Associated with the Transportation of Radioactive Material
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    Chapter 7 The Perspective of Waste Isolation Research Issues and Assessment of Consequences for Radionuclide Release
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    Chapter 8 Status Report on Studies to Assess the Feasibility of Storing Nuclear Waste in Columbia Plateau Basalts
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    Chapter 9 General Criteria for Radioactive Waste Disposal
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    Chapter 10 Characterization of Weathered Glass by Analyzing Ancient Artifacts
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    Chapter 11 An Investigation on the Valency State of Molybdenum in Glasses with and without Fission Products
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    Chapter 12 Resistance of High-Level Waste Materials to Dissolution in Aqueous Media
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    Chapter 13 Chemical Stability of a Phosphate Glass under Hydrothermal Conditions
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    Chapter 14 The Behavior of Actinides in α- Doped Glasses as Regards to the Long Term Disposal of High Level Radioactive Materials
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    Chapter 15 Atomic Displacements and Radiation Damage in Glasses Incorporating HLW
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    Chapter 16 A Microscopic Approach for the Simulation of Radioactive Waste Storage in Glass
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    Chapter 17 Devitrification of Nuclear Waste Glasses
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    Chapter 18 High-Level Waste Vitrification Product Characterization
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    Chapter 19 Long-Term Extrapolation of Laboratory Glass Leaching Data for the Prediction of Fission Product Release Under Actual Groundwater Conditions
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    Chapter 20 Leaching Characteristics of Actinides from Simulated Reactor Waste, Part 2
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    Chapter 21 Statistically Designed Study of a Nuclear Waste Glass System
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    Chapter 22 Dissolution of Borosilicate Glasses under Repository Conditions of Pressure and Temperature
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    Chapter 23 Mechanism for Elevated Temperature Leaching
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    Chapter 24 Brine Chemistry Effects on the Durability of a Simulated Nuclear Waste Glass
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    Chapter 25 Hydrothermal Interaction of Simulated Nuclear Waste Glass in the Presence of Basalts
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    Chapter 26 Vitrification of High-Level Alumina Nuclear Waste
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    Chapter 27 Improved Glass Compositions for Immobilization of SRP Waste
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    Chapter 28 Multibarrier Storage of Savannah River Plant Waste
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    Chapter 29 Temperature Dependence for Hydrothermal Reactions of Waste Glasses and Ceramics
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    Chapter 30 Microstructural Characterization of Glass and Ceramic Simulated Waste Forms
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    Chapter 31 Alternative Waste Forms — A Comparative Study
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    Chapter 32 Immobilization of U.S. Defense Nuclear Wastes Using the Synroc Process
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    Chapter 33 The Effects of Radiation Damage on Synroc
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    Chapter 34 Uranium and Thorium Minerals: Natural Analogues for Radioactive Waste Forms
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    Chapter 35 Monazite and Other Lanthanide Orthophosphates as Alternate Actinide Waste Forms
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    Chapter 36 Crystal Chemistry and Phase Relations in the Synthetic Minerals of Ceramic Waste Forms: I. Fluorite and Monazite Structure Phases
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    Chapter 37 Characterization of Impact Fracture of Brittle Solid Waste Forms
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    Chapter 38 Development and Characterization of Cermet Forms for Radioactive Waste
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    Chapter 39 Long-Term Leaching of Irradiated Spent Fuel
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    Chapter 40 Leaching of Irradiated Candu UO 2 Fuel
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    Chapter 41 Low Temperature Ceramic Waste Form: Characterization of Monazite Cement Composites
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    Chapter 42 Structure and Stability of Incinerated α-Waste Products
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    Chapter 43 Krypton-85 Storage in Solid Matrices
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    Chapter 44 Technical Feasibility of Krypton-85 Storage in Sodalite
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    Chapter 45 Corrosion-Resistant Metallic Canisters for Nuclear Waste Isolation
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    Chapter 46 Corrosion of Materials in a Clay Environment
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    Chapter 47 Canister Compatibility with Carlsbad Salt
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    Chapter 48 The Backfill as an Engineered Barrier for Nuclear Waste Management
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    Chapter 49 Superoverpack: Tailor-Made Mixtures of Zeolites and Clays
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    Chapter 50 Solution Interaction of Nuclear Waste Anions with Selected Geological Materials
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    Chapter 51 Clay Minerals Suitable for Overpack in Waste Repositories: Evidence From Uranium Deposits
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    Chapter 52 Comparison of Tailored Cement Formulations for Borehole Plugging in Crystalline Silicate Rocks and Evaporite Mineral Sequences
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    Chapter 53 Clay Mineral-Brine Interactions During Evaporite Diagenesis: Lanthanide Distribution in WIPP Samples
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    Chapter 54 Thermal Gradient Migration of Fluid Inclusions in Single Crystals of Salt from the Waste Isolation Pilot Plant Site (WIPP)
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    Chapter 55 The Application of the Physicochemical Properties of Boiling Bitterns to the Interpretation of Brine Migration Experiments Related to Salt Repositories
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    Chapter 56 Modeling of Brine Migration in Halite
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    Chapter 57 Long-Term Stability of Evaporite Minerals: Geochronological Evidence
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    Chapter 58 Tracer Tests Performed in the Field for WIPP in Southeastern New Mexico
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    Chapter 59 In Situ Experiments to Support Development of the Waste Isolation Pilot Plant (WIPP)
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    Chapter 60 Shale Rocks as Nuclear Waste Repositories: Hydrothermal Reactions with Glass, Ceramic and Spent Fuel Waste Forms
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    Chapter 61 Hydrogeologic Characteristics of Fractured Rocks for Waste Isolation — The Stripa Experience
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    Chapter 62 The Role of Large-Scale Permeability Measurements in Fractured Rock and their Application at Stripa
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    Chapter 63 Characterization of Discontinuities in the Stripa Granite
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    Chapter 64 Rock Instrumentation Problems Experienced during in Situ Heater Tests
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    Chapter 65 Geochemistry, Origin and Age of Groundwaters in the Stripa (Sweden) Test Mine
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    Chapter 66 Recent Studies on Radiation Damage Formation in Synthetic NaCl and Natural Rock Salt for Radioactive Waste Disposal Applications
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    Chapter 67 Physico-Chemical Processes in Rock Salt under Irradiation
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    Chapter 68 Gas Generation from Transuranic Waste Degradation
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    Chapter 69 The Reaction of Hydrogen and Oxygen in the Presence of Concretes Incorporating Simulated Radioactive Waste
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    Chapter 70 Radiolytic Gas Generation in Concrete Made with Incinerator Ash Containing Transuranium Nuclides
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    Chapter 71 Influence of Ionizing Irradiation on the Properties of Alumosilicate Mineral Rock Repositories of Radioactive Wastes
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    Chapter 72 99 Tc, Pb and Ru Migration Around the Oklo Natural Fission Reactors
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    Chapter 73 Parameters Affecting Radionuclide Migration in Geologic Media
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    Chapter 74 Radionuclide Transport in a Dolomite Aquifer
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    Chapter 75 Chemical Reactions in the Bedrock-Groundwater System of Importance for the Sorption of Actinides
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    Chapter 76 Interaction of Radionuclides with Geomedia from the Nevada Test Site
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    Chapter 77 Radionuclide Sorption Studies on Abyssal Red Clays
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    Chapter 78 Measurement of Penetration Depths of Plutonium and Americium in Sediment from the Ocean Floor
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    Chapter 79 The Radiolytic Oxidation and Reduction of Plutonium
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    Chapter 80 Transport through Deep Aquifers of Transuranic Nuclides Leached from Vitrified High-Level Wastes
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    Chapter 81 Possible Retention of Iodine in the Ground
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    Chapter 82 Asphalt Emulsion Sealing of Uranium Mill Tailings
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    Chapter 83 Waste Isolation Performance Assessment — A Status Report
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    Chapter 84 Ion Migration in Ocean Sediments: Subseafloor Radioactive Waste Disposal
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    Chapter 85 Radioactive Waste Disposal into a Plastic Clay Formation: Probabilistic Assessment of the Geological Containment
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    Chapter 86 Finite Medium Green’s Function Solutions to Nuclide Transport in Porous Material
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    Chapter 87 Preliminary Rate Expressions for Analysis of Radionuclide Migration Resulting from Fluid Flow Through Jointed Media
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    Chapter 88 The Complex Relationship between Groundwater Velocity and Concentration of Radioactive Contaminants
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    Chapter 89 Kinetic Effects on Radionuclide Transport of Groundwater
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    Chapter 90 The Effect of Variations in Parameter Values on the Predicted Radiological Consequences of Geologic Disposal of High-Level Waste
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    Chapter 91 Sensitivity Studies of the Swift Radionuclide Transport Model
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    Chapter 92 Development of Scenarios for the Long-Term Release of Radionuclides from the Proposed Waste Isolation Pilot Plant in Southeastern New Mexico
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    Chapter 93 A Stochastic Model of Radionuclide Migration from Natural and Engineered Repositories
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    Chapter 94 An Application of Geometric Probability to the Existence of Faults in Anisotropic Media
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    Chapter 95 Geologic Waste Disposal and a Model for the Surface Movement of Radionuclides
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    Chapter 96 Regional Thermohydrological Effects of an Underground Repository for Nuclear Wastes in Hard Rock
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    Chapter 97 Environmental Effects from Disposal of Defense High-Level Radioactive Wastes in a Generic Geologic Repository
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    Chapter 98 Far Field Thermal Calculations for the WIPP Site in Southeastern New Mexico (SENM)
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    Chapter 99 Temperatures Generated by Underground Storage of Defense Waste Canisters
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    Chapter 100 Calculated Hydrogeologic Pressures and Temperatures Resulting from Radioactive Waste in the Eleana Argillite
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    Chapter 101 A Systematic Approach for Assessment of Alternative Nuclear Waste Management Strategies
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    Chapter 102 A Review of the Environmental Impact of Mining and Milling of Uranium Ores
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    Chapter 103 Processing of High-Temperature Simulated Waste Glass in a Continuous Ceramic Melter
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    Chapter 104 Fixation of Medium-Level Wastes in Titanates and Zeolites:Progress Towards a System for Transfer of Nuclear Reactor Activities from Spent Organic to Inorganic Ion Exchangers
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    Chapter 105 Development of an Ion-Exchange Process for Removing Cesium from High-Level Radioactive Liquid Wastes
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    Chapter 106 Actinide Separation from HLLW
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    Chapter 107 Methods For Separating Actinides From Reprocessing And Refabrication Plant Wastes
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    Chapter 108 Ruthenium Volatility Behaviour during HLLW-Vitrification in a Liquid-Fed Ceramic Waste Melter
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    Chapter 109 Effect of Denitration on Ruthenium Volatilization
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    Chapter 110 Advances in the Fluorocarbon Process for Decontamination of Nuclear Facility Off-Gases
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Title
Scientific Basis for Nuclear Waste Management
Published by
Springer US, December 2013
DOI 10.1007/978-1-4684-3839-0
ISBNs
978-1-4684-3841-3, 978-1-4684-3839-0
Editors

Northrup, Clyde J. M.

Mendeley readers

Mendeley readers

The data shown below were compiled from readership statistics for 2 Mendeley readers of this research output. Click here to see the associated Mendeley record.

Geographical breakdown

Country Count As %
Finland 1 50%
Unknown 1 50%

Demographic breakdown

Readers by professional status Count As %
Student > Ph. D. Student 1 50%
Librarian 1 50%
Readers by discipline Count As %
Social Sciences 1 50%
Materials Science 1 50%