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Proceedings Papers

FCC-NG: The AREVA Safe Fresh Fuel Shipping Cask to Deliver the Future EPR™ Reactors

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M. Doucet, P. Faye, Ch. Faignet, R. Babut, M. Landrieu, F. Marvaud, G. Romanet
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 451-455, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29436
https://doi.org/10.1115/ICONE18-29436
View Paper titled, FCC-NG: The AREVA Safe Fresh Fuel Shipping Cask to Deliver the Future EPR™ Reactors
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Topics: Fuels
Proceedings Papers

Scenarios for the Transmutation of Actinides in CANDU Reactors

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Bronwyn Hyland, Brian Gihm
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 533-543, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30123
https://doi.org/10.1115/ICONE18-30123
View Paper titled, Scenarios for the Transmutation of Actinides in CANDU Reactors
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Topics: Design, Fuels, Heat, Heavy water reactors, Isotopes, Manufacturing, Neutron flux, Nuclear environmental management, Nuclear fuels, Separation (Technology)
Proceedings Papers

Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?

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Renaud Liberge, Marc Arslan
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 457-463, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29574
https://doi.org/10.1115/ICONE18-29574
View Paper titled, Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?
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Topics: Nuclear fuel cycle, Fuels, Recycling, Uranium, Nuclear power, Nuclear environmental management, Nuclear fuels, Sustainable development, Waste management
Proceedings Papers

New Composite Materials for Decreasing of Radioactive Molecular Iodine in the Water Coolant on the Working and New Developed NPPS

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S. A. Kulyukhin, L. V. Mizina, A. A. Tishina
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 383-386, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29006
https://doi.org/10.1115/ICONE18-29006
View Paper titled, New Composite Materials for Decreasing of Radioactive Molecular Iodine in the Water Coolant on the Working and New Developed NPPS
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Topics: Composite materials, Coolants, Nuclear power stations, Water, Resins, Absorption, Sorption
Proceedings Papers

The Study on Pyrolytic Carbon Powder in the Coating Process of Fuel Particle for High-Temperature Gas-Cooled Reactor

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Malin Liu, Bing Liu, Youlin Shao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 545-549, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30137
https://doi.org/10.1115/ICONE18-30137
View Paper titled, The Study on Pyrolytic Carbon Powder in the Coating Process of Fuel Particle for High-Temperature Gas-Cooled Reactor
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Topics: Carbon, Coating processes, Fuels, Particulate matter, Very high temperature reactors, Carbon black pigments, Drops, Electron microscopy, Lasers, Nanoparticles
Proceedings Papers

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

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Guang Jun Chen, Yu Lin Cui, Guo Guo Zhang, Hong Jun Yao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 465-468, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29632
https://doi.org/10.1115/ICONE18-29632
View Paper titled, The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle
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Topics: Innovation, Nuclear fuel cycle, Spent nuclear fuels, Nuclear fission, Separation (Technology), Uranium, Nuclear power stations, China, Combustion, Cycles
Proceedings Papers

Application of Formohydroxamic Acid in Nuclear Processing: Synthesis and Complexation With Technetium-99

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Patricia Paviet-Hartmann, Amber Wright, Edward Mausolf, Keri Campbell, Frederic Poineau
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 387-391, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29028
https://doi.org/10.1115/ICONE18-29028
View Paper titled, Application of Formohydroxamic Acid in Nuclear Processing: Synthesis and Complexation With Technetium-99
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Topics: Crystals, Diluents, Infrared spectroscopy, Nuclear fuel cycle, Nuclear magnetic resonance, Recycling, Resins, Ultraviolet-visible spectrophotometry, Uranium, Uranium mining
Proceedings Papers

Synthesis of Results Obtained With Laser Cutting, a Promising Dismantling Tool

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Guy Pilot
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 469-475, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29751
https://doi.org/10.1115/ICONE18-29751
View Paper titled, Synthesis of Results Obtained With Laser Cutting, a Promising Dismantling Tool
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Topics: Aerosols, Cutting, Cutting tools, Gases, Generators, Laser cutting, Lasers, Nd-YAG lasers, Optical fiber, Plates (structures)
Proceedings Papers

Development of Superfine Spherical Silica Grout as an Alternative Grouting Material for the Geological Disposal of Long-Lived Radioactive Waste

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Morimasa Naito, Hirokazu Kishi, Naomi Fukuoka, Tsutomu Yamada, Hideaki Ishida
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 551-557, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30141
https://doi.org/10.1115/ICONE18-30141
View Paper titled, Development of Superfine Spherical Silica Grout as an Alternative Grouting Material for the Geological Disposal of Long-Lived Radioactive Waste
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Topics: Grouting, Radioactive wastes, Calcium hydroxide, Cements (Building materials), Binders (Materials), Particle size, Superplasticizers, Water, Workability
Proceedings Papers

Researches on the In-Core Reload Design for TianWan Nuclear Power Station

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Hongxia Wang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 393-397, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29057
https://doi.org/10.1115/ICONE18-29057
View Paper titled, Researches on the In-Core Reload Design for TianWan Nuclear Power Station
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Topics: Design, Nuclear power stations, Cycles, Leakage, China, Computation, Fuel rods, Gadolinium, Nuclear engineering, Nuclear fuel cycle
Proceedings Papers

Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive Borate Liquid Waste

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Qina Sun, Junfeng Li, Jianlong Wang, Shixi Ouyang, Qiang Li, Minghui Wu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 559-564, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30154
https://doi.org/10.1115/ICONE18-30154
View Paper titled, Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive Borate Liquid Waste
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Topics: Cements (Adhesives), Solidification, Compressive strength, Water, Engineering standards, Freezing, Irradiation (Radiation exposure), Fibers, Isotopes, Nuclides
Proceedings Papers

Transport of MOX Fuel: A Continuous Challenge

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Je´roˆme Galtier
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 477-482, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29875
https://doi.org/10.1115/ICONE18-29875
View Paper titled, Transport of MOX Fuel: A Continuous Challenge
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Topics: Fuels, Transportation systems, Nuclear power stations, Radioactive substances, Spent nuclear fuels, Boiling water reactors, Cooling, Nuclear fuel cycle, Nuclear industry, Pressurized water reactors
Proceedings Papers

Simulation and Analysis: The Dose Distribution of KBS-3 Spent Nuclear Fuel Canister by MCNP

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Bo Yang, He-xi Wu, Yi-bao Liu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 399-403, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29058
https://doi.org/10.1115/ICONE18-29058
View Paper titled, Simulation and Analysis: The Dose Distribution of KBS-3 Spent Nuclear Fuel Canister by MCNP
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Topics: Simulation, Spent nuclear fuels, Copper, Groundwater, Nodular iron, Nuclear industry, Nuclear power stations, Radioactive wastes, Corrosion, Health and safety
Proceedings Papers

The Application of Uniform Design Table in Cement Solidification of Nuclear Waste Resin

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Minghui Wu, Qiang Li, Shixi Ouyang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 565-570, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30164
https://doi.org/10.1115/ICONE18-30164
View Paper titled, The Application of Uniform Design Table in Cement Solidification of Nuclear Waste Resin
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Topics: Cements (Adhesives), Design, Radioactive wastes, Resins, Solidification, Raw materials
Proceedings Papers

Poolside Examination Techniques Applied for Development of an Advanced PWR Fuel, PLUS7™

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Jung-Cheol Shin, Jae-Ik Kim, Jung-Tack Kwon
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 483-488, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29889
https://doi.org/10.1115/ICONE18-29889
View Paper titled, Poolside Examination Techniques Applied for Development of an Advanced PWR Fuel, PLUS7™
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Topics: Fuels, Pressurized water reactors, Fuel rods, Manufacturing, Design, Cycles, Irradiation (Radiation exposure), Optical quality control, Rods
Proceedings Papers

Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement

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Yuko Onishi, Satoru Kawasaki, Masami Kato
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 571-575, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30166
https://doi.org/10.1115/ICONE18-30166
View Paper titled, Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement
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Topics: Calibration, Certainty, Clearances (Engineering), Computer software, Concretes, Density, Metals, Nuclear power stations, Radiation sources, Radioisotopes
Proceedings Papers

Acid Stimulation Used in In-Situ Leaching Uranium

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Wen-sheng Liao, Li-min Wang, Yi-xuan Yao, Guo-ping Jiang, Hai-jun Zhao, Xin Huang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 405-411, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29066
https://doi.org/10.1115/ICONE18-29066
View Paper titled, Acid Stimulation Used in In-Situ Leaching Uranium
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Topics: In situ processing (Mining), Uranium, Permeability, Damage, Flow (Dynamics), Fluids, Minerals, Precipitation, Risk, Wells
Proceedings Papers

Extraction of Actinides and Lanthanides by Supercritical Fluid

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Liyang Zhu, Wuhua Duan, Jingming Xu, Yongjun Zhu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 489-499, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29914
https://doi.org/10.1115/ICONE18-29914
View Paper titled, Extraction of Actinides and Lanthanides by Supercritical Fluid
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Topics: Supercritical fluids, Radioactive wastes, Supercritical fluid extraction, Nuclear fuels, Chemical engineering, Nuclear environmental management, Nuclear power, Radioactivity, Sustainable development
Proceedings Papers

Recent GEH Criticality Safety Activities in Support of the Nuclear Fuel Cycle

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Lon Paulson, John Zino, Qi Ao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 577-580, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30227
https://doi.org/10.1115/ICONE18-30227
View Paper titled, Recent GEH Criticality Safety Activities in Support of the Nuclear Fuel Cycle
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Topics: Nuclear fuel cycle, Safety, Licensing, Packaging, Boiling water reactors, Computational methods, Design, Fuels, Manufacturing, Nuclear power
Proceedings Papers

Plutonium Rock-Like Oxide Fuel (ROXf) System: Their Once-Through Burning and Usage

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Ashraf Elsayed Mohamed Mohamed
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 581-583, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30336
https://doi.org/10.1115/ICONE18-30336
View Paper titled, Plutonium Rock-Like Oxide Fuel (ROXf) System: Their Once-Through Burning and Usage
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Topics: Combustion, Fuels, Rocks, Light water reactors, Zirconium, Cooling, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Safety