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Proceedings Papers

Creep As the Governing Mechanism of Spent Fuel in Dry Storage

Joseph Y. R. Rashid, Albert J. Machiels
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, 207-212, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1036
https://doi.org/10.1115/ICEM2001-1036
View Paper titled, Creep As the Governing Mechanism of Spent Fuel in Dry Storage
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Topics: Creep, Spent nuclear fuels, Storage, Damage, Rupture, Cladding systems (Building), Cracking (Materials), Deformation, Fracture (Process), Fuel rods
Proceedings Papers

Estimation of Maximum Permissible Temperatures of Spent RBMK-1000 Fuel in a Metal-Concrete Cask MCC

A. G. Ioltukhovskiy, I. M. Kadarmetov, A. V. Medvedev, A. A. Bochvar
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, 213-216, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1037
https://doi.org/10.1115/ICEM2001-1037
View Paper titled, Estimation of Maximum Permissible Temperatures of Spent RBMK-1000 Fuel in a Metal-Concrete Cask MCC
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Topics: Concretes, Fuels, Metals, Temperature, Storage, Spent nuclear fuels, Cladding systems (Building), Construction, Containers, Cooling
Proceedings Papers

Materials Science Challenges in Long-Term Wet and Dry Storage of RBMK-1000 Spent Nuclear Fuel

M. I. Solonin, A. G. Ioltukhovskiy, V. P. Velioukhanov, I. M. Kadarmetov, L. P. Sinel’nikov, A. N. Timokhin, O. A. Golosov, V. P. Kuznetsov, V. A. Tsykhanov, S. V. Pavlov, D. V. Markov, V. P. Smirnov
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, 217-221, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1038
https://doi.org/10.1115/ICEM2001-1038
View Paper titled, Materials Science Challenges in Long-Term Wet and Dry Storage of RBMK-1000 Spent Nuclear Fuel
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Topics: Materials science, Spent nuclear fuels, Storage, Fuel rods, Corrosion, Cladding systems (Building), Cracking (Materials), Creep, Fracture (Process), Fuels
Proceedings Papers

Long Term Behavior of the Spent Fuel Cladding in Dry Storage Conditions

C. Cappelaere, R. Limon, T. Bredel, P. Herter, D. Gilbon, Pol Bouffioux, Jean-Paul Mardon
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, 195-200, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1034
https://doi.org/10.1115/ICEM2001-1034
View Paper titled, Long Term Behavior of the Spent Fuel Cladding in Dry Storage Conditions
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Topics: Cladding systems (Building), Spent nuclear fuels, Storage, Creep, Microscopy, Modeling, Pressure
Proceedings Papers

Interim Dry Storage of PWR Spent Fuel Assemblies: Development of a Long Term Creep Law to Assess the Fuel Cladding Integrity

Pol Bouffioux, Sylvain Leclercq, Chantal Cappelaere, Thierry Bredel
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, 201-205, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1035
https://doi.org/10.1115/ICEM2001-1035
View Paper titled, Interim Dry Storage of PWR Spent Fuel Assemblies: Development of a Long Term Creep Law to Assess the Fuel Cladding Integrity
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Topics: Cladding systems (Building), Creep, Fuels, Pressurized water reactors, Spent nuclear fuels, Storage, Pressure, Databases, Failure, Fuel rods
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
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, 1175-1180, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1212
https://doi.org/10.1115/ICEM2001-1212
View Paper titled, Preparing the Spent Nuclear Fuel for Long-Term Storage and Final Disposal by Encapsulating It Into Glass-Ceramic Waste Forms
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Topics: Ceramics, Glass, Spent nuclear fuels, Storage, Radioisotopes, Containers, Manufacturing, Porosity, Radiation (Physics), Water
Proceedings Papers

Main Results of Post-Irradiation Examinations of Vibropac Oxide Fuel Pins

A. A. Mayorshin, V. A. Tsykanov, V. N. Golovanov, V. A. Kisly, A. E. Novoselov, V. G. Dvoretsky, O. V. Shishalov
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, 1087-1091, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1193
https://doi.org/10.1115/ICEM2001-1193
View Paper titled, Main Results of Post-Irradiation Examinations of Vibropac Oxide Fuel Pins
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Topics: Fuels, Irradiation (Radiation exposure), Pins (Engineering), Maintainability, Cladding systems (Building), Fast neutron reactors, Nuclear weapons, Thermal reactors, Weapons
Proceedings Papers

Microstructure of Spent MOX Fuel Stored Under Dry Air for 25 Years

A. Leenaers, M. Verwerft, D. Boulanger, N. Itagaki, T. Matsumura
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, 1093-1097, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1194
https://doi.org/10.1115/ICEM2001-1194
View Paper titled, Microstructure of Spent MOX Fuel Stored Under Dry Air for 25 Years
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Topics: Fuels, Fuel rods, Cladding systems (Building), Cohesion, Grain boundaries, Irradiation (Radiation exposure), Oxidation, Rods, Uranium
Proceedings Papers

Effect of Loading Pattern on Thermal and Shielding Performance of a Spent Fuel Cask

Mikal A. McKinnon, Judith M. Cuta, Urban P. Jenquin
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, 1199-1204, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1216
https://doi.org/10.1115/ICEM2001-1216
View Paper titled, Effect of Loading Pattern on Thermal and Shielding Performance of a Spent Fuel Cask
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Topics: Spent nuclear fuels, Fuels, Stress, Heat, Temperature, Cooling, Design, Neutrons, Photons, Cladding systems (Building)
Proceedings Papers

Estimation of Carbon 14 Inventory in Hull and End-Piece Wastes From Japanese Commercial Reprocessing Operation

Tomofumi Sakuragi, Hiromi Tanabe, Emiko Hirose, Akira Sakashita, Tsutomu Nishimura
Proc. ASME. ICEM2013, Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, V001T02A018, September 8–12, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2013-96110
https://doi.org/10.1115/ICEM2013-96110
View Paper titled, Estimation of Carbon 14 Inventory in Hull and End-Piece Wastes From Japanese Commercial Reprocessing Operation
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Topics: Carbon, Hull, Boiling water reactors, Fuels, Pressurized water reactors, Radioisotopes, Safety, Cladding systems (Building), Manufacturing, Stainless steel
Proceedings Papers

Overview of the United States Department of Energy’s Used Fuel Disposition Research and Development Campaign

Mark Nutt, Peter Swift, Jens Birkholzer, William Boyle, Timothy Gunter, Ned Larson, Robert MacKinnon, Kevin McMahon, Ken Sorenson
Proc. ASME. ICEM2013, Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, V001T02A020, September 8–12, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2013-96190
https://doi.org/10.1115/ICEM2013-96190
View Paper titled, Overview of the United States Department of Energy’s Used Fuel Disposition Research and Development Campaign
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Topics: Fuels, Industrial research, Storage, Nuclear fuels, Transportation systems, Rocks, Uncertainty, Cladding systems (Building), Creep, Cycles
Proceedings Papers

Magnox Swarf Storage Silo Liquor Effluent Management: Sellafield Site, Cumbria, UK

Stephen Le Clere
Proc. ASME. ICEM2011, ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B, 67-75, September 25–29, 2011
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2011-59271
https://doi.org/10.1115/ICEM2011-59271
View Paper titled, Magnox Swarf Storage Silo Liquor Effluent Management: Sellafield Site, Cumbria, UK
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Topics: Scrap metals, Storage, Hazards, Cladding systems (Building), Creativity, Metals, Nuclear decommissioning, Sewage treatment
Proceedings Papers

Advanced Surveillance Technologies for Used Fuel Long-Term Storage and Transportation

Hanchung Tsai, Yung Y. Liu, Mark Nutt, James Shuler
Proc. ASME. ICEM2011, ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B, 699-706, September 25–29, 2011
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2011-59032
https://doi.org/10.1115/ICEM2011-59032
View Paper titled, Advanced Surveillance Technologies for Used Fuel Long-Term Storage and Transportation
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Topics: Fuels, Storage, Surveillance, Transportation systems, Sensors, Cladding systems (Building), Fuel rods, Radiation (Physics), Rupture, Corrosion
Proceedings Papers

Study for Radionuclide Transfer Ratio of Aerosols Generated During Heat Cutting

Yukihiro Iguchi, Tsutomu Baba, Hiroto Kawakami, Takashi Kitahara, Atsushi Watanabe, Mitsuhiro Kodama
Proc. ASME. ICEM2007, 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B, 1095-1101, September 2–6, 2007
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2007-7139
https://doi.org/10.1115/ICEM2007-7139
View Paper titled, Study for Radionuclide Transfer Ratio of Aerosols Generated During Heat Cutting
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Topics: Aerosols, Cutting, Heat, Radioisotopes, Filters, Fuels, Melting, Melting point, Metallic elements, Vapor pressure
Proceedings Papers

Studies on Spent Fuel Alterations During Storage and Radiolysis Effects on Corrosion Behaviour Using Alpha-Doped UO 2

V. V. Rondinella, T. Wiss, J.-P. Hiernaut, J. Cobos
Proc. ASME. ICEM2003, 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3, 265-272, September 21–25, 2003
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2003-4593
https://doi.org/10.1115/ICEM2003-4593
View Paper titled, Studies on Spent Fuel Alterations During Storage and Radiolysis Effects on Corrosion Behaviour Using Alpha-Doped UO 2
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Topics: Corrosion, Spent nuclear fuels, Storage, Damage, Annealing, Fuels, Alpha decay, Cladding systems (Building), Cracking (Materials), Dislocations
Proceedings Papers

Cemented Containers Radiological Data From a Disused Uranium Mine Low-Level Waste Repository: A Calculated-Experiment Cross-Check for Data Verification and Validation

D. G. Cepraga, G. Cambi, M. Frisoni, D. Ene
Proc. ASME. ICEM2003, 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3, 461-468, September 21–25, 2003
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2003-4516
https://doi.org/10.1115/ICEM2003-4516
View Paper titled, Cemented Containers Radiological Data From a Disused Uranium Mine Low-Level Waste Repository: A Calculated-Experiment Cross-Check for Data Verification and Validation
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Topics: Containers, Uranium mining, Concretes, Isotopes, Radioactivity, Tin, Approximation, Biomedicine, Calibration, Cements (Adhesives)
Proceedings Papers

Decommissioning of a Shielded αβγ Pie Facility at Harwell

T. N. Chambers
Proc. ASME. ICEM2003, 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3, 1727-1734, September 21–25, 2003
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2003-5022
https://doi.org/10.1115/ICEM2003-5022
View Paper titled, Decommissioning of a Shielded αβγ Pie Facility at Harwell
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Topics: Nuclear decommissioning, Decontamination, Cladding systems (Building), Concretes, Fuels, Irradiation (Radiation exposure), Metallurgy, Nuclear industry, Radioactive substances, Spent nuclear fuels
Proceedings Papers

The Nature of Contamination of the Area in the Nearest Vicinity of Chornobyl NPP Destroyed Unit

M. I. Panasyuk, A. D. Skorbun, V. V. Ronchar, A. V. Zhydkov
Proc. ASME. ICEM2003, 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3, 1559-1562, September 21–25, 2003
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2003-4737
https://doi.org/10.1115/ICEM2003-4737
View Paper titled, The Nature of Contamination of the Area in the Nearest Vicinity of Chornobyl NPP Destroyed Unit
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Topics: Contamination, Nuclear power stations, Soil, Accidents, Concretes, Fuels, Particulate matter, Radioactive substances, Radioisotopes, Cladding systems (Building)