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Proceedings Papers

Stress Concentration Factor Calculation for the Hooks in Lifting Appliance of Spent Fuel Well Cover

Xiang Liu, Yue Li, Jinhua Wang, Bin Wu
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A002, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30272
https://doi.org/10.1115/ICONE22-30272
View Paper titled, Stress Concentration Factor Calculation for the Hooks in Lifting Appliance of Spent Fuel Well Cover
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Topics: Spent nuclear fuels, Stress concentration, Corners (Structural elements), Fatigue life, Finite element methods, High temperature, Numerical analysis, Saint-Venant's principle, Wells
Proceedings Papers

A Double Porosity Model to Describe Both Permeability Change and Dissolution Processes

Yuichi Niibori, Hideo Usui, Taiji Chida, Hitoshi Mimura
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30481
https://doi.org/10.1115/ICONE22-30481
View Paper titled, A Double Porosity Model to Describe Both Permeability Change and Dissolution Processes
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Topics: Permeability, Porosity, Particulate matter, Diffusion (Physics), Ions, Cements (Adhesives), Diffusion processes, Fittings, Flow (Dynamics), Groundwater
Proceedings Papers

Spent Fuel Canister Criticality Safety Calculation in Groundwater Immersion Accident

Siyuan Wu, Bo Yang, Hexi Wu, Qianglin Wei, Yibao Liu
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30978
https://doi.org/10.1115/ICONE22-30978
View Paper titled, Spent Fuel Canister Criticality Safety Calculation in Groundwater Immersion Accident
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Topics: Accidents, Groundwater, Safety, Spent nuclear fuels, Computer software, Computers, Isotopes, Pressurized water reactors
Proceedings Papers

Shipment of Spent Nuclear Fuel From the Czech Republic for Reprocessing

Josef Podlaha
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A017, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31003
https://doi.org/10.1115/ICONE22-31003
View Paper titled, Shipment of Spent Nuclear Fuel From the Czech Republic for Reprocessing
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Topics: Spent nuclear fuels, Nuclear fuels, Nuclear power, Radioactive wastes, Sealing (Process), Transport packages
Proceedings Papers

Safety Requirements for Engineering Scale Pyroprocess Demonstration Facility

Seong-In Moon, Won-Myung Chong, Gil-Sung You, Jeong-Hoe Ku, Ho-Dong Kim
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A009, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30637
https://doi.org/10.1115/ICONE22-30637
View Paper titled, Safety Requirements for Engineering Scale Pyroprocess Demonstration Facility
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Topics: Safety, Hazards, Accidents, Design, Conceptual design, Nuclear fuel cycle, Nuclear power, Risk, Spent nuclear fuels
Proceedings Papers

Development of Glass Melter Technology for HLLW Vitrification in Japan

Akira Sakai, Hajime Koikegami, Nobuyuki Miura, Eiji Ochi
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A011, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30693
https://doi.org/10.1115/ICONE22-30693
View Paper titled, Development of Glass Melter Technology for HLLW Vitrification in Japan
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Topics: Glass, Vitrification, Metals, Design, Testing, Ceramics, Glassmaking, Joules, Precipitation, Process design
Proceedings Papers

Optimization of Chemical Composition in the Iron Phosphate Glass as the Matrix of High Level Waste Generated From Pyroprocessing

Hirohide Kofuji, Tetsuji Yano, Munetaka Myochin, Kanae Matsuyama, Takeshi Okita, Shinya Miyamoto
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30688
https://doi.org/10.1115/ICONE22-30688
View Paper titled, Optimization of Chemical Composition in the Iron Phosphate Glass as the Matrix of High Level Waste Generated From Pyroprocessing
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Topics: Glass, Iron, Optimization, Durability, Electrolytes, Industrial research, Radioactive waste disposal, Radioactive wastes, Transition metals
Proceedings Papers

Scenario Analysis on the Benefits of Multi-National Cooperation for the Development of a Common Nuclear Energy System Based on PWR and LFR Fleets

Marco Ciotti, Jorge L. Manzano, Vladimir Kuznetsov, Galina Fesenko, Luisa Ferroni, Fabio Giannetti
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A019, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31012
https://doi.org/10.1115/ICONE22-31012
View Paper titled, Scenario Analysis on the Benefits of Multi-National Cooperation for the Development of a Common Nuclear Energy System Based on PWR and LFR Fleets
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Topics: Nuclear power, Pressurized water reactors, Nuclear power stations, Nuclear fuel cycle, Stress, Uranium, Carbon, Carbon dioxide, Cycles, Dimensions
Proceedings Papers

Modeling of Cladding Thermal Evolution Along Cask Storage

Jaime E. Penalva, Francisco Feria, Luis E. Herranz
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A012, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30758
https://doi.org/10.1115/ICONE22-30758
View Paper titled, Modeling of Cladding Thermal Evolution Along Cask Storage
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Topics: Cladding systems (Building), Modeling, Storage, Temperature, Fuel rods, Equipment performance, Thermal characterization, Arches, Creep, Embrittlement
Proceedings Papers

Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.

Milan Tous, Josef Podlaha
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A021, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31155
https://doi.org/10.1115/ICONE22-31155
View Paper titled, Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.
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Topics: Nuclear decommissioning, Nuclear power stations, Blasting, Decontamination, Ice, Nuclear research, Radioactive wastes, Water
Proceedings Papers

Decreasing Waste of Laser Cutting by Metal Fume Capturing With Water

Itaru Chida, Katsunori Shiihara, Kota Nomura, Rie Sumiya, Naotaka Suganuma
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A004, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30337
https://doi.org/10.1115/ICONE22-30337
View Paper titled, Decreasing Waste of Laser Cutting by Metal Fume Capturing With Water
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Topics: Laser cutting, Metals, Water, Cutting, Stainless steel, Lasers, Machining, Nuclear decommissioning, Nuclear reactors, Radioactive wastes
Proceedings Papers

Feasibility Study on Direct Waste Salt Disposition Through Measurement and Analysis of Salt Bead Dissolutions in Aqueous Solvents

Michael Shaltry, Supathorn Phongikaroon
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A013, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30841
https://doi.org/10.1115/ICONE22-30841
View Paper titled, Feasibility Study on Direct Waste Salt Disposition Through Measurement and Analysis of Salt Bead Dissolutions in Aqueous Solvents
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Topics: Ceramics, Modeling, Water
Proceedings Papers

ÚJV Řež, a.s. Research Programme Supporting Development of Deep Geological Repository in the Czech Republic

Václava Havlová
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A022, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31177
https://doi.org/10.1115/ICONE22-31177
View Paper titled, ÚJV Řež, a.s. Research Programme Supporting Development of Deep Geological Repository in the Czech Republic
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Topics: Heat, Radioactive wastes, Rocks, Safety
Proceedings Papers

Application of Ultrasonic Technique for Precipitate Detection and Viscosity Measurement of Molten Glass at Elevated Temperature

Midori Uchiyama, Arisa Yanagihara, Hajime Koikegami, Hiroaki Hatanaka, Tadashi Maruyama
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A005, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30360
https://doi.org/10.1115/ICONE22-30360
View Paper titled, Application of Ultrasonic Technique for Precipitate Detection and Viscosity Measurement of Molten Glass at Elevated Temperature
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Topics: Glass, Temperature, Viscosity measurement, Waveguides, Alloys, Corrosion, Density, Graphite, Nickel, Ultrasound
Proceedings Papers

Decommissioning Combustible Waste Treatment Using Oxygen-Enriched Incinerator

Byung Youn Min, Yoon Ji Lee, Gyoung Su Yun, Ki Won Lee, Jae Kwon Moon
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A014, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30855
https://doi.org/10.1115/ICONE22-30855
View Paper titled, Decommissioning Combustible Waste Treatment Using Oxygen-Enriched Incinerator
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Topics: Incinerators, Nuclear decommissioning, Oxygen, Waste treatment, Carbon dioxide, Clearances (Engineering), Nitrogen oxides, Pressure, Temperature
Proceedings Papers

The Treatment of Low-Level Radioactive Wastewater by the Nuclear Weapons Using Ultrasonic Standing Wave Methods

Suxia Hou, Jijun Luo, Bin He, Jun Xu, Rusong Li
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30532
https://doi.org/10.1115/ICONE22-30532
View Paper titled, The Treatment of Low-Level Radioactive Wastewater by the Nuclear Weapons Using Ultrasonic Standing Wave Methods
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Topics: Nuclear weapons, Sewage, Standing waves, Particulate matter, Decontamination, Radioactive wastes, Ultrasound, Contamination, Hazards, Radiation (Physics)
Proceedings Papers

Modelling of RBMK Spent Nuclear Fuel Characteristics

Arturas Smaizys, Povilas Poskas, Ernestas Narkunas
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31005
https://doi.org/10.1115/ICONE22-31005
View Paper titled, Modelling of RBMK Spent Nuclear Fuel Characteristics
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Topics: Modeling, Spent nuclear fuels, Fuels, Radioisotopes, Evaluation methods, Heat, Neutron sources, Nuclear fission, Nuclear power stations, Safety
Proceedings Papers

Interim Storage of Spent Nuclear Fuel in the UAE Nuclear Power Plants

Sara Al Saadi, Yongsun Yi
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A001, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30081
https://doi.org/10.1115/ICONE22-30081
View Paper titled, Interim Storage of Spent Nuclear Fuel in the UAE Nuclear Power Plants
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Topics: Nuclear power stations, Spent nuclear fuels, Storage, Cooling, Construction, Cycles, Natural convection, Safety, Stress corrosion cracking, Temperature
Proceedings Papers

Ageing Management of Dry Storage Systems for Long-Term Storage

Justo Garcia, Hervé Issard
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A020, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31118
https://doi.org/10.1115/ICONE22-31118
View Paper titled, Ageing Management of Dry Storage Systems for Long-Term Storage
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Topics: Storage, Nuclear fuels, Safety, Nuclear reactors, Accidents, Containers, Delays, Feedback, Nuclear fuel cycle, Transportation systems
Proceedings Papers

Adsorption Properties of Sr(II) on Zeolite Type Adsorbents and Their Irradiation Stabilities

Hitoshi Mimura, Shunsuke Susa, Yoshiyuki Ito, Yasuo Saito, Minoru Matsukura
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A003, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30329
https://doi.org/10.1115/ICONE22-30329
View Paper titled, Adsorption Properties of Sr(II) on Zeolite Type Adsorbents and Their Irradiation Stabilities
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Topics: Irradiation (Radiation exposure), Flow (Dynamics), Radioactive wastes, Equilibrium (Physics), Ions, Optimization, Particle size, Sodium