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Scientific Basis for Nuclear Waste Management : Volume 1 Proceedings of the Symposium on “Science Underlying Radioactive Waste Management,” Materials Research Society Annual Meeting, Boston, Massachusetts, November 28–December 1, 1978
The Disposal of Iodine-129
other
Author(s):
M. T. Morgan
,
J. G. Moore
,
H. E. Devaney
,
G. C. Rogers
,
C. Williams
,
E. Newman
Publication date
(Print):
1979
Publisher:
Springer US
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The Isolation of Radioiodine with Portland Cement. Part I: Scoping Leach Studies
Walter E. Clark
,
W. G. Clark
(1977)
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Ornl/Nureg/ TM-4
W. Jr
(1976)
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Annual Meeting, New York, N
CD Hollister
(1977)
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Book Chapter
Publication date (Print):
1979
Pages
: 453-459
DOI:
10.1007/978-1-4615-9107-8_58
SO-VID:
ea9422bf-2572-443a-a8d3-bf1f33bcfb1a
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Book chapters
pp. 1
Science Underlying Radioactive Waste Management: Status and Needs
pp. 21
Techniques for High Level Waste Solidification in Europe
pp. 31
Development of Glass Compositions for Immobilization of Savannah River Plant Waste
pp. 37
Preparation and Characterization of an Improved High Level Radioactive Waste (HAW) Borosilicate Glass
pp. 43
Vitrification of High Sodium-Aluminum Wastes: Composition Ranges and Properties
pp. 51
Non-Radioactive Operation Experience with a Joule Heated Ceramic Melter for Vitrification of High-Level Liquid Waste
pp. 57
Natural Glasses: Analogues for Radioactive Waste Forms
pp. 69
Characterization of Glass and Glass Ceramic Nuclear Waste Forms
pp. 83
Microstructural Characterization of Solidified Simulated Reactor Wasteforms
pp. 97
Bonding of Metal Oxides in Sodium Silicate Glass
pp. 109
Helium Formation from α-Decay and its Significance for Radioactive Waste Glasses
pp. 117
Thermal, Chemical and Radiation Stability of Vitreous Radioactive Wastes
pp. 123
Chemistry of Nuclear Waste Glass Reactions: Problems and Potential of Prediction
pp. 131
Characterization of Leached Surface Layers on Simulated High-Level Waste Glasses by Sputter-Induced Optical Emission
pp. 141
Leaching Characteristics of Actinides from Simulated Reactor Waste Glass
pp. 149
Leach Rate Characterization of Solid Radioactive Waste Forms
pp. 157
Long-Term Elevated Temperature Leaching of Solid Waste Forms
pp. 161
Calculations of Radioactivity Release Due to Leaching of Vitrified High Level Waste
pp. 169
Development of Multibarrier Nuclear Waste Forms
pp. 181
Metal Encapsulation of Ceramic Nuclear Waste
pp. 191
Cermets for High Level Waste Containment
pp. 195
Clay-Phosphate Ceramics and Vitromets: Alternatives to Monolithic High Level Waste Glass Products
pp. 201
Synthetic Rutile Microencapsulation: A Radioactive Waste Solidification System Resulting in an Extremely Stable Product
pp. 207
Hot Isostatic Pressing for the Consolidation and Containment of Radioactive Waste
pp. 211
Characterization of a Titanate Based Ceramic for High Level Nuclear Waste Solidification
pp. 219
Raman Spectra of Cesium Aluminosilicate Waste Forms
pp. 227
Investigations of the Volatility of Cesium from Aluminosilicates by Mass Spectrometry
pp. 231
Pollucite and its Alteration in Geological Occurrences and in Deep-Burial Radioactive Waste Disposal
pp. 237
The Scientific Basis For, and Experience With, Underground Storage of Liquid Radioactive Wastes in the USSR
pp. 249
Influence of Radiation on the System Liquid Radioactive Wastes-Geologic Formation
pp. 257
Waste Disposal by Shale Fracturing at ORNL
pp. 261
The Rock-Melt Approach to Nuclear Waste Disposal in Geological Media
pp. 265
Interaction of a Glass-Based Nuclear Waste Simulant and Natural Rock
pp. 271
Corrosion Resistance of Canisters for Final Disposal of Spent Nuclear Fuel
pp. 283
Corrosion Considerations for Nuclear Waste Isolation Canisters
pp. 289
Preliminary Corrosion Test of a Glass-Ceramic Candidate for a Nuclear Waste Canister
pp. 297
Application of Physical Chemistry of Fluids in Rock Salt at Elevated Temperature and Presssure to Repositories for Radioactive Waste
pp. 313
Application of Studies of Fluid Inclusions in Permian Salado Salt, New Mexico, to Problems of Siting the Waste Isolation Pilot Plant
pp. 323
P-T-X Relations of Anhydrite and Brine and their Implications for the Suitability of Anhydrite as a Nuclear Waste Repository Medium
pp. 329
Hydrothermal Reactivity of Simulated Nuclear Waste Forms and Water-Catalysed Waste-Rock Interactions
pp. 341
Hydrothermal Glass Reactions in Salt Brine
pp. 345
Long Term Geochemical Interactions of High Active Waste with Crystalline Rock Repository Media
pp. 349
Radiation Damage Studies on Natural and Synthetic Rock Salt for Waste Disposal Applications
pp. 355
Thermodynamic Considerations Underlying the Migration of Radionuclides in Geomedia: Oklo and Other Examples
pp. 367
Measurements of Parameters Essential to Predicting Nuclide Migration
pp. 379
Interaction of Waste Radionuclides with Geomedia: Program Approach and Progress
pp. 395
Radionuclide Migration Studies Associated with the WIPP Site in Southern New Mexico
pp. 399
Migration of Cesium in Dolomite from the Rustler Formation in the Los Medanos Area in Southeastern New Mexico
pp. 403
Nuclide Transport by Groundwater in Swedish Bedrock
pp. 411
Analysis of Some Tracer Runs in Granite Rock Using a Fissure Model
pp. 417
Chemistry of Tc-99 and Np-237 in Contact with Unweathered Igneous Rocks
pp. 419
Interactions of Simulated Waste Radionuclides and Rocks
pp. 423
Sorption and Migration of Radionuclides in Geologic Media
pp. 427
Analysis of Pu-Release Consequences on the Environmental Geochemistry
pp. 435
Variables Affecting Sorption and Transport of Radionuclides in Hanford Subsoils
pp. 439
The Effect of Retardation Factors on Radionuclide Migration
pp. 443
Studies of Concrete as a Host for Savannah River Plant Radioactive Waste
pp. 453
The Disposal of Iodine-129
pp. 461
Role of Admixtures in Preparing Dense Cements for Radioactive Waste Isolation
pp. 467
Immobilization of Strontium and Cesium in Intermediate-Level Liquid Wastes by Solidification in Cements
pp. 471
Permeability Measurements on Cementitious Materials for Nuclear Waste Isolation
pp. 479
The Development of Process and Storage Materials Suitable for Krypton-85 Waste Management
pp. 487
Confinement of Volatilized Ruthenium Oxides
pp. 491
Technical Challenges in the Immobilization of Hanford Defense Waste
pp. 495
Physicochemical Characterization of Solidification Agents Used and Products Formed with Radioactive Wastes at LWR Nuclear Power Plants
pp. 499
Low-Level Solidified Waste Characterization: The Scientific Basis for Physical and Chemical Testing
pp. 501
An Analysis of the Geological Stability of a Hypothetical Radioactive Waste Repository in a Bedded Salt Formation
pp. 513
Preliminary Safety Assessment of the WIPP Facility
pp. 521
Computer Enhanced “Release Scenario” Analysis for a Nuclear Waste Repository
pp. 533
Methodology for Estimating Accidental Radioactive Releases in Nuclear Waste Management
pp. 541
Release of Radionuclides from High-Level Waste during Transportation Fires
pp. 549
Comparison of Some Geologic and Ocean Disposal Concepts Regarding Realistic Modeling that Allows Objective Risk Assessment to be Made
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