Materials Research Society Symposium Proceedings Volume 807 Scientific Basis for Nuclear Waste Management XXVII Editors: Virginia M. Oversby, Lars O. Werme Purchase this Volume: Order Online | Download Order Form

Sections

• Siting Issues
• Spent Fuel and Actinide Studies
• Glass Waste Forms
• Ceramic Waste Forms
• Cement and Special Waste Forms
• Radiation Effects
• Canisters and Canister Corrosion Issues
• Geologic Characterization and Modeling
• Uranium Disequilibria Studies
• Solubility and Radionuclide Transport
• Colloids and Sorption
• Gas Migration
• Clay Mineral Studies
• Modeling of Groundwater Flow and Chemistry
• Microbial Effects
• Field Tests and Natural Analogs
• Performance Assessment
• Alternative Concepts

 

Siting Issues POSIVA's Site Investigations Programme Veijo Ryhänen Site Investigations of Potential Repository Sites in Sweden Peter Wikberg, Kaj Ahlbom, and Olle Olsson Development of Siting Factors and Commencement of Open Solicitation for Preliminary Investigation Areas of HLW Disposal in Japan Hiroyuki Tsuchi, Masanori Kobayashi, Hirofumi Kondo, Akihisa Koike, Hiroki Hatamoto, and Toshihiro Seo Study on a Decision Making Methodology With Uncertantities in the Selection Process of Preliminary Investigation Areas Hiroyuki Tsuchi, Toshihiro Seo, Richard Metcalfe, Kenji Kawano, Hiroyasu Takase, Andrew Bowden, Yasuhiro Suyama, Masaru Toida, Mitsuaki Furuichi, Atsushi Matsumura, and Miyoshi Yoshimura

 

Spent Fuel and Actinide Studies Key Scientific Issues Related to the Evolution of Spent Nuclear Fuel in Long Term Dry Storage and Geological Disposal Christophe Poinssot, Cécile Ferry, and Jean-Marie Gras Quantitative Assessment of the Instant Release Fraction (IRF) for Fission Gases and Volatile Elements as a Function of Burnup and Time Under Geological Disposal Conditions Cécile Ferry, Patrick Lovera, Christophe Poinssot, and Lawrence Johnson Behavior of Uranium Dioxide: Chemistry and Catalysis in the UO 2 -Water System Jérôme Devoy, John Haschke, Daqing Cui, and Kastriot Spahiu Measurement of Dissolution Rates of UO 2 Matrix With the Isotope Dilution Method K. Ollila and V. Oversby Corrosion Behavior of Pre-Oxidized High Burnup Spent Fuel in Salt Brine Andreas Loida, Bernhard Kienzler, and Horst Geckeis Static Dissolution of a-Doped UO 2 in Boom Clay Conditions: Preliminary Results C. Cachoir and K. Lemmens A New Modeling of the Kinetics of Uranium Dioxide Oxidation in Air L. Desgranges and C. Poinssot Surface Site Densities of Uranium Oxides: UO2 , U3O8 F. Clarens, J. de Pablo, I. Casas, J. Giménez, and M. Rovira Dissolution of UO2 by One- and Two-Electron Oxidants Mats Jonsson, Ella Ekeroth, and Olivia Roth The Oxidative Dissolution Mechanism of Uranium Dioxide: The Effect of pH and Oxygen Partial Pressure Joan de Pablo, Ignasi Casas, Javier Giménez, Frederic Clarens, Lara Duro, and Jordi Bruno Spent Fuel Leaching Under Anoxic Conditions and the Effect of Canister Materials Daqing Cui, Jeanett Low, Max Lundström, and Kastriot Spahiu Leaching Behavior of Unirradiated High Temperature Reactor (HTR) UO 2 -ThO 2 Mixed Oxides Fuel Particles Catherine Landesman, Sandra Delaunay, and Bernd Grambow Microgravimetric Corrosion Studies on UO2 Detlef H. Wegen, T. Gouder, M. Eckle, T. Wiss, and J.-P. Glatz Thermodynamic Properties of Pu-O-H Compunds and Alloys From Density Functional Theory P.A. Korzhavyi, L. Vitos, and B. Johansson Resonant Inelastic Soft X-ray Scattering Studies of U(VI) Reduction on Iron Surfaces S.M. Butorin, D.K. Shuh, K. Kvashnina, I.L. Soroka, K. Ollila, K.E. Roberts, J.-H. Guo, L. Werme, and J. Nordgren

 

Glass Waste Forms Microstructure and Chemistry of an Aluminophosphate Glass Waste Form Under Electron Beam Irradiation K. Sun, L.M. Wang, and R.C. Ewing | Affinity Rate Law Failure to Describe Sodium Borosilicate Glass Alteration Kinetics P. Frugier, S. Gin, and C. Jégou Nuclear Glass Alteration in Clay: Assessment of the Effect of Direct Contact Between the Materials Through Experimental and Modeling Approach S. Gin, F. Thierry, and Y. Minet Secondary Phases on the Surface of Real Vitrified Radioactive Waste Disposed in a Loamy Soil Natalie V. Ojovan, Irene V. Sartceva, Alexander S. Barinov, Andrew V. Mokhov, Michael I. Ojovan, and Günter Möbus Chemical Durability Studies of Waste-Simulant Doped Borosilicate Glasses Adam Duddridge, Moinul Islam, Diane Holland, and Charlie R. Scales Interactions of Simulated High Level Waste (HLW) Calcine With Alkali Borosilicate Glass S. Morgan, R.J. Hand, N.C. Hyatt, and W.E. Lee Structural Characterizations of Rare Earth-Rich Glasses for Nuclear Waste Immobilization I. Bardez, D. Caurant, F. Ribot, P. Loiseau, J.L. Dussossoy, F. Villain, N. Baffier, and C. Fillet Using Acoustic Emission in Quality Control of Glass and Ceramics for Radioactive Waste Immobilization V.Z. Belov and A.S. Aloy An Investigation Into the Oxidation State of Molybdenum in Simplified High Level Nuclear Waste Glass Compositions R.J. Short, R.J. Hand, and N.C. Hyatt Effect of Gamma and Alpha Irradiation on the Corrosion of the French Borosilicate Glass SON 68 Abdesselam Abdelouas, Karine Ferrand, Bernd Grambow, Thierry Mennecart, Massoud Fattahi, Gilbert Blondiaux, and Chantal Houée-Lévin Vapor Phase Hydration of Blended Oxide—Magnox Waste Glasses Neil C. Hyatt, William E. Lee, Russell J. Hand, Paul K. Abraitis, and Charlie R. Scales Iron-Phosphate Glass (IPG) Waste Forms Produced Using Induction Melter With Cold Crucible A.S. Aloy, R.A. Soshnikov, A.V. Trofimenko, D. Gombert, D. Day, and C.W. Kim The Role of Water Diffusion in the Corrosion of the French Nuclear Waste Glass SON 68 Under Solution Saturation Conditions Karine Ferrand, Abdesselam Abdelouas, Bernd Grambow, and Jean-Louis Crovisier A Study of Magnox Waste Glass Under Conditions of High Temperature, Very Deep, Geological Disposal Neil C. Hyatt, Kathleen J. Taylor, Fergus G.F. Gibb, and William E. Lee

 

Ceramic Waste Forms Ceramics for the Immobilization of Plutonium and Americium: Current Progress of R&D of the V.G. Khlopin Radium Institute Evgeniy B. Anderson and Boris E. Burakov Behavior of 238 Pu-Doped Cubic Zirconia Under Self-Irradiation Boris E. Burakov, Maria A. Yagovkina, Maria V. Zamoryanskaya, Alexander A. Kitsay, Vladimir M. Garbuzov, Evgeniy B. Anderson, and Alexey S. Pankov Aqueous Dissolution and Surface Alteration Studies of Nd-Bearing Zirconolite in 0.001M Citric Acid at 90°C Peter J. McGlinn, Terry McLeod, Gilles Leturcq, Zaynab Aly, Mark G. Blackford, Zhaoming Zhang, Huijun Li, and Gregory R. Lumpkin Radiation Effects in Murataite Ceramics J. Lian, L.M. Wang, R.C. Ewing, S.V. Yudintsev, and S.V. Stefanovsky Ceramic Wasteforms for the Conditioning of Spent MO x Fuel Wastes E.R. Maddrell and P.K. Abraitis Synthesis of Actinide-Doped Ceramics: From Laboratory Experiments to Industrial Scale Technology Alexander A. Kitsay, Vladimir M. Garbuzov, and Boris E. Burakov Examination of Synthetic Murataite Structure Using Data of Mössbauer Spectroscopy Vadim S. Urusov, Vyacheslav S. Rusakov, Sergey V. Yudintsev, and Sergey V. Stefanovsky Hollandite-Rich Ceramic Melts for the Immobilization of Cs M.L. Carter, E.R. Vance, and H . Li Development of a Glass-Encapsulated Ceramic Wasteform for the Immobilization of Chloride-Containing ILW Brian L. Metcalfe, Shirley K. Fong, and Ian W. Donald A Comparison of Wasteforms and Processes for the Immobilization of Iodine-129 E.R. Maddrell and P.K. Abraitis Fabrication of 239/238 Pu-Zirconolite Ceramic Pellets by Natural Sintering T. Advocat, F. Jorion, T. Marcillat, G. Leturcq, X. Deschanels, J.M. Boubals, L. Bojat, P. Nivet, and S. Peuget Study of Pyrochlore and Garnet-Based Matrices for Actinide Wastes Produced by a Self-Propagating High-Temperature Synthesis Sergey V. Yudintsev, Tatiana S. Ioudintseva, Andrey V. Mokhov, Boris S. Nikonov, Eduard E. Konovalov, Sergey A. Perevalov, Sergey V. Stefanovsky, Alexander G. Ptashkin, Eduard M. Glagovsky, and Alexander V. Kouprine Effects of pH and Uranium Valence State on the Aqueous Dissolution of Brannerite Y. Zhang, E. Loi, M. Blackford, T. McLeod, H. Li, and B. Begg Study of the Effects of Potential Impurities From Actinide Flux on the Zirconolite Microstructure G. Leturcq and B. Auzemerie Investigation of Valence State of U, Pu, and Am in Crystalline Host-Phases Using In Situ Cathodoluminescence Spectroscopy Maria V. Zamoryanskaya, Boris E. Burakov, and Vladimir M. Garbuzov Thermochemical Investigations of Zirconolite, Pyrochlore and Brannerite: Candidate Materials for the Immobilization of Plutonium K.B. Helean, A. Navrotsky, J. Lian, and R.C. Ewing The Immobilization of Cesium and Strontium in Ceramic Materials Derived From Tungstate Sorbents Vittorio Luca, Elizabeth Drabarek, Christopher S. Griffith, Harriet Chronis, and James Foy Cs + and Sr 2+ Ion-Exchange Properties of Microporous Tungstates Vittorio Luca, Christopher S. Griffith, Harriet Chronis, Jonathan Widjaja, Huijun Li, and Nicholas Scales Synthesis, Characterization and Study of the Radiation Effects on Hollandite Ceramics Developed for Cesium Immobilization Virginie Aubin, Daniel Caurant, Didier Gourier, Noël Baffier, Thierry Advocat, Florence Bart, Gilles Leturcq, and Jean M. Costantini Titanate Ceramic Matrices for Alumina-Rich Wastes Bruce D. Begg, Eric R. Vance, Huijun Li, Terry McLeod, Nicholas Scales, and Mugdha Bhati Phase Relations and Chemical Durability of Ceramics in the Pseudo-Binary System: CaZrTi2O7-GdAlO3 N.P. Mikhailenko, A.V. Ochkin, S.V. Stefanovsky, and O.I. Kirjanova Competition Between Internal and Surface Crystallization in Glass-Ceramics Developed for Actinides Immobilization Pascal Loiseau, Daniel Caurant, Odile Majerus, Noël Baffier, and Catherine Fillet Structural Studies of Hollandite-Based Radioactive Waste Forms K.R. Whittle, S.E. Ashbrook, S.A.T. Redfern, G.R. Lumpkin, J.P. Attfield, M. Dove, and I. Farnan Effect of Synthesis Conditions and Actinide Contents on Phase Composition of Actinide Bearing Ceramics A.G. Ptashkin, S.V. Stefanovsky, S.V. Yudintsev, and S.A. Perevalov

 

Cement and Special Waste Forms Incorporation of AlCl3 and As2O3 in Composite Cement Systems J. Hill and J.H. Sharp Zeolite-Salt Occlusion: A Potential Route for the Immobilization of Iodine-129? Neil C. Hyatt, Joseph A. Hriljac, Alia Choudhry, Laura Malpass, Gareth P. Sheppard, and Ewan R. Maddrell A Generic Procedure for the Assessment of the Effect of Concrete Admixtures on the Sorption of Radionuclides on Cement: Concept and Selected Results M.A. Glaus, A. Laube, and L.R. Van Loon Effects of Technical Adsorbents and Cleaning Agents in a Cement Matrix—A Case Study Mårten Dario, Mireia Molera, and Bert Allard Modeling of Water Uptake and Salt Leaching in Bituminized Radioactive Waste: Comparison Between Numerical, Analytical and Experimental Results J. Sercombe, F. Adenot, C. Tiffreau, B. Gwinner, and I. Felines

 

Radiation Effects Modeling of the Effects of Radiolysis on UO 2 -Dissolution Employing Recent Experimental Data Mats Jonsson, Fredrik Nielsen, Ella Ekeroth, and Trygve E. Eriksen Effects of alpha and gamma Radiolysis of Water on Alteration of the Spent UO 2 Nuclear Fuel Matrix C. Jégou, V. Broudic, A. Poulesquen, and J.M. Bart Modeling Experimental Results on Radiolytic Processes at the Spent Fuel Water Interface: I. Radiolysis Products and U Release J. Bruno, E. Cera , T.E. Eriksen, M. Grivé, and S. Ripoll Effect of Alpha Radiolysis on UO 2 Dissolution Under Reducing Conditions T. Mennecart, B. Grambow, M. Fattahi, G. Blondiaux, and Z. Andriambololona Modeling of the (U1-y238 Puy )O2+x Leaching Behavior in Deionized Water Under Anoxic Conditions J. Quiñones, J. Cobos, P. Diaz-Arocas, and V.V. Rondinella

 

Canisters and Canister Corrosion Issues KBS-TR-90 Twenty-Five Years On—Progress in the Understanding of the Long-Term Corrosion Behavior of Copper Canisters Lars Werme, Fraser King, Lasse Ahonen, Claes Taxén, and Ulla Vuorinen Atmospheric Corrosion of Copper 450 Meters Underground: Results From Three Years Exposure in the Äspö HRL Claes Taxén Application of an On-Line Corrosion Probe and a Reference Electrode for Copper Corrosion Studies in Repository Conditions Iva Betova, Jussi Heinonen, Petri Kinnunen, Christina Lilja, Esko Ruokola, and Timo Saario Evaluation of Corrosion Processes Affecting the Performance of Alloy 22 as a Proposed Waste Package Material Gustavo A. Cragnolino, Darrell S. Dunn, and Yi-Ming Pan Anaerobic Corrosion of Steel in Bentonite Nicholas R. Smart, Andrew P. Rance, and Lars O. Werme Development of a Used Fuel Container for Nuclear Fuel Waste Peter Maak Effects of the Environmental Pressure in the Corrosion Potential of the Copper that Will be Used as Container of High Level Radioactive Waste I. Escobar, E. Silva, C. Lamas, C. Silva, and L. Werme Corrosion of Copper in 1 M NaCl Under Strictly Anoxic Conditions Martin Bojinov, Timo Laitinen, Kari Mäkelä, Margit Snellman, and Lars Werme Investigations of Resistance Variations in Electrically Heated Canisters for Deep Repository Baohua Zhu, Hans-Peter Hermansson, Rolf Sjöblom, and Gunnar Ramqvist The Impact of Cementitious Materials on the Corrosion of Copper Canisters Fraser King and Lars Werme A Weld That Lasts for 100,000 Years: Friction Stir Welding of Copper Canisters Lars Cederqvist Microstructure Development in Copper Welded by the FSW-Process Therese Källgren and Rolf Sandström The Corrosion Rate of Copper in a Test Parcel at the Äspö Hard Rock Laboratory Bo Rosborg, David Eden, Ola Karnland, Jinshan Pan, and Lars Werme Pitting Studies Under Anoxic Conditions on Candidate Container Materials AISI 316L hMo and UHB 904L for the Disposal of HLW in Argillaceous Formations Bruno Kursten and Frank Druyts

 

Geologic Characterization and Modeling Groundwater Flow and Transport Modeling at Äspö for a Glaciation Period O. Jaquet, P. Siegel, W. Klemenz, and J.O. Selroos Geophysical Applications for Deep Geological Repository Studies in Plutonic Rocks of Canada Ganpat S. Lodha, Mulugeta H. Serzu, Ed T. Kozak, Richard A. Everitt, Dzintars K. Tomsons, and John G. Hayles Excavation Damage Zone in the Experimental Deposition Holes at Äspö and Comparison to Existing Data Jorma Autio, Hanna Malmlund, Thomas Hjerpe, Maarit Kelokaski, and Marja Siitari-Kauppi Earthquake Induced Rock Shear Through a Deposition Hole: Effect on the Canister and Buffer L. Börgesson, L.-E. Johannesson, and J. Hernelind Advances in Classifications for Structural Modeling of the Olkiluoto Site Tiina Vaittinen, Henry Ahokas, Pirjo Hellä, and Pauli Saksa Representation of Fracture Zone Interpretation Uncertainty in 3D Geological Models of the Mizunami Underground Research Laboratory, Japan Matthew J. White and Hiromitsu Saegusa Assessment of Redox Conditions in the Near Field of Nuclear Waste Repositories: Application to the Swiss High-Level and Intermediate Level Waste Disposal Concept Paul Wersin, Lawrence H. Johnson, and Bernhard Schwyn On Pressure Pulse Techniques for Testing Low Permeability Geological Materials and Formations M. Zhang and M. Takeda Harmonization of Site Characterization and Performance Assessment Modeling—The Relative Importance of Surface Sorption and Matrix Interaction Phenomena James Crawford, Luis Moreno, and Ivars Neretnieks Mineralogical Characterization of Sediments at the Drigg Low Level Radioactive Waste Disposal Site and the Influence on Groundwater Chemistry M.G. Randall, D.P. Trivedi, J. Graham, J.S. Small, and C. Hughes

 

Uranium Disequilibria Studies The Feasibility of USD Method in Tracking Past Hydrogeochemical Changes in the Fennoscandian Shield Kari Rasilainen, Juhani Suksi, Timo Ruskeeniemi, and Petteri Pitkänen The Use of Natural Uranium Decay Series Studies in Support of Understanding Redox Conditions at Potential Radioactive Waste Disposal Sites Eva-Lena Tullborg, John A.T. Smellie, and Angus B. MacKenzie Monitoring Disturbances in the Repository System During Construction Process: Experiences From Natural Decay Series Studies at the Pyhäsalmi Mine (Central Finland) N. Marcos, J. Suksi, K. Rasilainen, and J. Antikainen

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