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Proceedings Papers

Modelling of the Waste Form Behaviour in a Wet Near-Surface Repository Site Over Extended Time Periods

Michael I. Ojovan, Natalia V. Ojóvan, Irene V. Startceva, Zoja I. Golubeva, Alexander S. Barinov

Proc. ASME. ICEM2001, Volume 3: Hazardous Waste; Engineered/Geological Barriers in Disposal Systems; L/ILW; Radioactive Waste From Research/Industries; Spent Fuel/HLW Disposal; Public Involvement; Remediation of Uranium Mining/Milling; LL/ILW; Clearance/Exemption Levels; Mgmt. of Fissile Material; HLW; Dismantling; Reversible/Irreversible Disposal; Waste Avoidance/Minimization; Decontamination; Liquid Waste; Radioactive Waste Processing; Transport of Spent Fuel/HLW; Solid HLW Confinement; QA/QC, 1647-1650, September 30–October 4, 2001

Paper No: ICEM2001-1291

DOI: https://doi.org/10.1115/ICEM2001-1291

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Topics: Modeling, Asphalt, Bituminous materials, Pitch (Bituminous material), Radioactivity, Glass, Radioisotopes, Diffusion (Physics), Groundwater, Borosilicate glasses

Proceedings Papers

Dissolution and Growth of Spinel Crystals in a High-Level Waste Glass

Pavel Hrma, Jesse Alton

Paper No: ICEM2001-1323

DOI: https://doi.org/10.1115/ICEM2001-1323

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Topics: Crystals, Glass, Crystal growth, Nucleation (Physics), Particulate matter, Temperature, Diffusion (Physics), Magnetite, Mass transfer, Metals

Proceedings Papers

The Effect of Temperature and Composition on Spinel Concentration and Crystal Size in High-Level Waste Glass

Martin Mika, Milan Patek, Jaroslav Maixner, Simona Randakova, Pavel Hrma

Paper No: ICEM2001-1324

DOI: https://doi.org/10.1115/ICEM2001-1324

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Topics: Crystals, Glass, Temperature, Crystallization, Diffraction, Equilibrium (Physics), Modeling, Optical microscopy, Radioactive wastes, Temperature effects

Proceedings Papers

Measurement of Glass Corrosion in Boom Clay Disposal Conditions

Karel Lemmens, Marc Aertsens, Véra Pirlet, Hélène Serra, Elie Valcke, Pierre De Cannière, Pierre Van Iseghem

Paper No: ICEM2001-1286

DOI: https://doi.org/10.1115/ICEM2001-1286

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Topics: Corrosion, Glass, Modeling, Sorption, Temperature, Uncertainty, Water, Diffusion (Physics), Interpolation, Radioisotopes

Proceedings Papers

Near Field Radionuclide Concentrations: Sorption or Solubility Constrained?

Bernhard Kienzler, Peter Vejmelka, Volker Metz

Paper No: ICEM2001-1236

DOI: https://doi.org/10.1115/ICEM2001-1236

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Topics: Radioisotopes, Sorption, Cements (Adhesives), Precipitation, Solids, Coal, Fly ash, Glass, Modeling, Radioactive waste repositories

Proceedings Papers

Micro-Structural Studies of Leached SON-68-Type Glasses

N. Ollier, G. Panczer, B. Champagnon, P. Jollivet

Paper No: ICEM2001-1287

DOI: https://doi.org/10.1115/ICEM2001-1287

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Topics: Glass, Borosilicate glasses, Cathodoluminescence, Photoluminescence, Scanning electron microscopes, Uranium

Proceedings Papers

Experience of Glass Melter Operation in Tokai Vitrification Facility

Jiro Nakayama, Masahiro Yoshioka

Paper No: ICEM2001-1276

DOI: https://doi.org/10.1115/ICEM2001-1276

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Topics: Glass, Vitrification, Borosilicate glasses, Cohesion, Countermeasures, Dust, Exhaust systems, Heat resistant glass, Metals, Underground injection

Proceedings Papers

Effect of Canister Filling by Multiple Pouring Batches on Quality Properties of HLW Glass Product

G. Roth, S. Weisenburger, W. Grünewald, Y. Gauthier

Paper No: ICEM2001-1277

DOI: https://doi.org/10.1115/ICEM2001-1277

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Topics: Glass products, Glass, Ceramics, Computers, Engineering prototypes, Test facilities, Vitrification

Proceedings Papers

Effects of Composition Variations on the Alteration Kinetics of the UOX1 “Light Water” Borosilicate Containment Glass

P. Frugier, I. Ribet, T. Advocat

Paper No: ICEM2001-1289

DOI: https://doi.org/10.1115/ICEM2001-1289

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Topics: Borosilicate glasses, Containment, Glass, Water, Durability, Nuclear fission, Accounting, Industrial research, Particulate matter, Stability

Proceedings Papers

CORA Project: Vitrification of Intermediate Level Liquid Radioactive Wastes in Saluggia ENEA Research Centre

Carlos A. Calle, Alfredo Luce

Paper No: ICEM2001-1318

DOI: https://doi.org/10.1115/ICEM2001-1318

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Topics: Radioactive wastes, Vitrification, Glass, Design, Solidification, Storage, Waste management

Proceedings Papers

The HRA/Solarium Project: Processing of Widely Varying High- and Medium-Level Waste

M. Willems, L. Krieckemans, P. Luycx, A. Meeus

Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 1155-1161, September 30–October 4, 2001

Paper No: ICEM2001-1209

DOI: https://doi.org/10.1115/ICEM2001-1209

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Topics: Acceptance criteria, Cables, Calibration, Cements (Adhesives), Concretes, Construction, Containers, Contamination, Decontamination, Emissions

Proceedings Papers

Oxidation and Direct Conditioning of Contaminated Metallic Sodium

B. Petitfour, A. Rahier, J. Seghers, R. Vandevoorde

Proc. ASME. ICEM2001, Volume 1: Posters; Natl./Intl. Programs; Environmental Remediation and D&D Management/Tools; Fuel Cladding Evolution; LL/ILW; Disposal Site Selection/URLs; Fuel Pellets; Low/Interm. Level Waste; Worker Protection Policies; Release/Clearance Standards; Transmutation; Solid Waste; Contaminant Migration; Remediation of Uranium Mining/Milling Sites, 433-437, September 30–October 4, 2001

Paper No: ICEM2001-1075

DOI: https://doi.org/10.1115/ICEM2001-1075

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Topics: Acceptance criteria, Alkali metals, Breeder reactors, Carbon dioxide, Circuits, Contamination, Coolants, Explosions, Fire risk, Fluidized beds

Proceedings Papers

Preparing the Spent Nuclear Fuel for Long-Term Storage and Final Disposal by Encapsulating It Into Glass-Ceramic Waste Forms

Sergey Yu. Sayenko, G. A. Kholomeyev, B. A. Shilyaev, A. V. Pilipenko, E. P. Shevyakova, R. V. Tarasov, S. V. Gabelkov

Paper No: ICEM2001-1212

DOI: https://doi.org/10.1115/ICEM2001-1212

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Topics: Ceramics, Glass, Spent nuclear fuels, Storage, Radioisotopes, Containers, Manufacturing, Porosity, Radiation (Physics), Water

Proceedings Papers

Development of the Induction Heating Melting System With Active Insulator for Low-Level Radioactive Solid Waste

Ryo Chishiro, Ichiro Kawaguchi, Motohiko Nishimura, Kazuki Kanai, Seiichiro Yamazaki

Paper No: ICEM2001-1076

DOI: https://doi.org/10.1115/ICEM2001-1076

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Topics: Electromagnetic induction, Heating, Melting, Solid wastes, Ceramics, Concretes, Flow (Dynamics), Glass, Graphite, Heat

Proceedings Papers

Characterization of Borosilicate Compositions for Immobilization of Pu-Containing Sludges

A. S. Aloy, O. A. Iskhakova, A. V. Trofimenko, V. S. Belov, S. I. Rovnyi, G. M. Medvedev, L. J. Jardine

Paper No: ICEM2001-1087

DOI: https://doi.org/10.1115/ICEM2001-1087

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Topics: Borosilicate glasses, Glass, Sodium, Uranium, Boron, Corrosion, Electrons, Flow (Dynamics), Iron, Probes

Proceedings Papers

HUP Immobilization of Uranium and Plutonium From Surrogate Liquid Radioactive Solutions Using Porous Molded Glass Crystalline Blocks (Gubka)

A. S. Aloy, N. V. Sapozhnikova, A. G. Anshits, O. M. Sharonova, A. A. Tretyakov, D. A. Knecht, T. J. Tranter, J. Macheret

Paper No: ICEM2001-1214

DOI: https://doi.org/10.1115/ICEM2001-1214

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Topics: Glass, Uranium, Ceramics, Cycles, Drying, Electron microscopy, Porous materials, Roasting (Metallurgy), X-ray diffraction

Proceedings Papers

Production of an Impermeable Composite of Irradiated Graphite and Glass by Hot Isostatic Pressing as a Long Term Leach Resistant Waste Form

Johannes Fachinger, Walter Müller, Eric Marsat, Karl-Heinz Grosse, Richard Seemann, Charlie Scales, Anthony Banford, Michael Mark Easton

Proc. ASME. ICEM2013, Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, V001T01A041, September 8–12, 2013

Paper No: ICEM2013-96228

DOI: https://doi.org/10.1115/ICEM2013-96228

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Topics: Composite materials, Glass, Graphite, Hot pressing, Radioisotopes, Containers, Grouting, Packing (Shipments), Packings (Cushioning), Vacuum

Proceedings Papers

Applicability of Iron Phosphate Glass Medium for Loading NaCl Originated From Seawater Used for Cooling the Stricken Power Reactors

Hidekazu Kobayashi, Ippei Amamoto, Takuma Yokozawa, Teruo Yamashita, Takayuki Nagai, Naoto Kitamura, Hiromichi Takebe, Naoki Mitamura, Tatsuya Tsuzuki

Paper No: ICEM2013-96108

DOI: https://doi.org/10.1115/ICEM2013-96108

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Topics: Cooling, Durability, Glass, Iron, Seawater, Vitrification

Proceedings Papers

Enhanced HLW Glass Formulations for the Waste Treatment and Immobilization Plant

Albert A. Kruger

Paper No: ICEM2013-96028

DOI: https://doi.org/10.1115/ICEM2013-96028

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Topics: Glass, Waste treatment, Aluminum, Ceramics, Iron, Joules, Sulfur compounds, Testing, Zirconium

Proceedings Papers

Treatment of Spent Solutions Containing Tributilphosphate

Ella A. Barinova, Mikhail N. Diordiy, Olga K. Karlina

Paper No: ICEM2013-96111

DOI: https://doi.org/10.1115/ICEM2013-96111

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Topics: Glass, Radioactive wastes, Sodium

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NARROW

Modelling of the Waste Form Behaviour in a Wet Near-Surface Repository Site Over Extended Time Periods

Dissolution and Growth of Spinel Crystals in a High-Level Waste Glass

The Effect of Temperature and Composition on Spinel Concentration and Crystal Size in High-Level Waste Glass

Measurement of Glass Corrosion in Boom Clay Disposal Conditions

Near Field Radionuclide Concentrations: Sorption or Solubility Constrained?

Micro-Structural Studies of Leached SON-68-Type Glasses

Experience of Glass Melter Operation in Tokai Vitrification Facility

Effect of Canister Filling by Multiple Pouring Batches on Quality Properties of HLW Glass Product

Effects of Composition Variations on the Alteration Kinetics of the UOX1 “Light Water” Borosilicate Containment Glass

CORA Project: Vitrification of Intermediate Level Liquid Radioactive Wastes in Saluggia ENEA Research Centre

The HRA/Solarium Project: Processing of Widely Varying High- and Medium-Level Waste

Oxidation and Direct Conditioning of Contaminated Metallic Sodium

Preparing the Spent Nuclear Fuel for Long-Term Storage and Final Disposal by Encapsulating It Into Glass-Ceramic Waste Forms

Development of the Induction Heating Melting System With Active Insulator for Low-Level Radioactive Solid Waste

Characterization of Borosilicate Compositions for Immobilization of Pu-Containing Sludges

HUP Immobilization of Uranium and Plutonium From Surrogate Liquid Radioactive Solutions Using Porous Molded Glass Crystalline Blocks (Gubka)

Production of an Impermeable Composite of Irradiated Graphite and Glass by Hot Isostatic Pressing as a Long Term Leach Resistant Waste Form

Applicability of Iron Phosphate Glass Medium for Loading NaCl Originated From Seawater Used for Cooling the Stricken Power Reactors

Enhanced HLW Glass Formulations for the Waste Treatment and Immobilization Plant

Treatment of Spent Solutions Containing Tributilphosphate

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