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Proceedings Papers

Transport of MOX Fuel: A Continuous Challenge

Je´roˆme Galtier

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 477-482, May 17–21, 2010

Paper No: ICONE18-29875

DOI: https://doi.org/10.1115/ICONE18-29875

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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

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

Paper No: ICONE18-29058

DOI: https://doi.org/10.1115/ICONE18-29058

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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

Minghui Wu, Qiang Li, Shixi Ouyang

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 565-570, May 17–21, 2010

Paper No: ICONE18-30164

DOI: https://doi.org/10.1115/ICONE18-30164

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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™

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

Paper No: ICONE18-29889

DOI: https://doi.org/10.1115/ICONE18-29889

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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

Yuko Onishi, Satoru Kawasaki, Masami Kato

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 571-575, May 17–21, 2010

Paper No: ICONE18-30166

DOI: https://doi.org/10.1115/ICONE18-30166

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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

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

Paper No: ICONE18-29066

DOI: https://doi.org/10.1115/ICONE18-29066

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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

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

Paper No: ICONE18-29914

DOI: https://doi.org/10.1115/ICONE18-29914

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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

Lon Paulson, John Zino, Qi Ao

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 577-580, May 17–21, 2010

Paper No: ICONE18-30227

DOI: https://doi.org/10.1115/ICONE18-30227

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Topics: Nuclear fuel cycle, Safety, Licensing, Packaging, Boiling water reactors, Computational methods, Design, Fuels, Manufacturing, Nuclear power

Proceedings Papers

The Implementation of Radiological Characterization for Reactor Decommissioning

Junxian Deng, Huasong Zhao, Xin Li, Feng Deng

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 413-417, May 17–21, 2010

Paper No: ICONE18-29075

DOI: https://doi.org/10.1115/ICONE18-29075

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Topics: Nuclear decommissioning, Radiological characterization, Density, Nuclear power, Radioactivity, Radioisotopes, Statistics

Proceedings Papers

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

Ashraf Elsayed Mohamed Mohamed

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 581-583, May 17–21, 2010

Paper No: ICONE18-30336

DOI: https://doi.org/10.1115/ICONE18-30336

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Topics: Combustion, Fuels, Rocks, Light water reactors, Zirconium, Cooling, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Safety

Proceedings Papers

Treatment and Disposal of the Radioactive Graphite Waste

Lifang Tian, Mingfen Wen, Jing Chen

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 501-509, May 17–21, 2010

Paper No: ICONE18-29985

DOI: https://doi.org/10.1115/ICONE18-29985

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Topics: Graphite, Carbon, Contamination, Radioactive wastes, Carbon dioxide, Chemical processes, Decontamination, Gases, Nuclear fuels, Nuclear reactors

Proceedings Papers

Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate Microcapsules

Hitoshi Mimura, Yan Wu, Yufei Wang, Yuichi Niibori, Isao Yamagishi, Masaki Ozawa, Takashi Ohnishi, Shinichi Koyama

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 419-427, May 17–21, 2010

Paper No: ICONE18-29091

DOI: https://doi.org/10.1115/ICONE18-29091

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Topics: Separation (Technology), Crystals, Flow (Dynamics), Biopolymers, Ion exchange, Metals, Zirconium

Proceedings Papers

Development of Integrated Treatment System to Minimize LLLW From Purex Reprocessing Plant

Yasuhiro Suzuki, Yasutomi Morimoto, Hikari Egami, Takashi Kato, Mamoru Numata, Mitsuaki Kumazawa, Shekar Balagopal

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 511-515, May 17–21, 2010

Paper No: ICONE18-30008

DOI: https://doi.org/10.1115/ICONE18-30008

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Topics: Radioactive waste processing, Radioactive wastes, Separation (Technology), Spent nuclear fuels

Proceedings Papers

Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear Power Plant Operation

Xuesong Li

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 517-521, May 17–21, 2010

Paper No: ICONE18-30041

DOI: https://doi.org/10.1115/ICONE18-30041

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Topics: Design, Nuclear power plant operations, Leakage, Safety, Cycles, Stress, Economic analysis, Equilibrium (Physics), Fuel management, Fuels

Proceedings Papers

Testing of TRANSURANUS Code for RIA Analysis: The FK-1 NSRR Case

R. Calabrese, F. Vettraino

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 429-436, May 17–21, 2010

Paper No: ICONE18-29098

DOI: https://doi.org/10.1115/ICONE18-29098

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Topics: Accidents, Boiling water reactors, Cladding systems (Building), Control systems, Coolants, Damage, Design, Electricity (Physics), Enthalpy, Failure

Proceedings Papers

Radioactive Waste Water Treatment by Inorganic Membrane System

Junfeng Li, Fujuan Han, Jianlong Wang

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 523-527, May 17–21, 2010

Paper No: ICONE18-30092

DOI: https://doi.org/10.1115/ICONE18-30092

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Topics: Membranes, Radioactive wastes, Water treatment

Proceedings Papers

Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements by Gamma Spectroscopy

Bing Xia, Fu Li, Zongxin Wu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 437-444, May 17–21, 2010

Paper No: ICONE18-29300

DOI: https://doi.org/10.1115/ICONE18-29300

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Topics: Calibration, Error analysis, Fuels, Gamma ray spectrometry, Errors, Measurement systems, Graphite, Very high temperature reactors, Absorption, Alpha decay

Proceedings Papers

Based on 200L Barrels of Low-Level Solid Waste Encapsulates Device Design

Aiguo Shang, Jin Qin, Changjie Lu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 529-532, May 17–21, 2010

Paper No: ICONE18-30110

DOI: https://doi.org/10.1115/ICONE18-30110

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Topics: Design, Solid wastes, Paper products, Plastic products, Rubber

Proceedings Papers

N,N,N ′ ,N ′ -Tetra-Methyl-3-Oxy-Pentane-1,5-Diamide (TMPDA): A Promising Back Extractant for Ln(III) and Zr(IV)

Meng Wei, Qian’ge He, Xuegang Liu, Jing Chen

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 445-450, May 17–21, 2010

Paper No: ICONE18-29358

DOI: https://doi.org/10.1115/ICONE18-29358

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Topics: Zirconium, Crystal structure, Equilibrium (Physics), Melting point, Temperature, Water

Proceedings Papers

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

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

Paper No: ICONE18-29436

DOI: https://doi.org/10.1115/ICONE18-29436

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Topics: Fuels

NARROW

Transport of MOX Fuel: A Continuous Challenge

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

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

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

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

Acid Stimulation Used in In-Situ Leaching Uranium

Extraction of Actinides and Lanthanides by Supercritical Fluid

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

The Implementation of Radiological Characterization for Reactor Decommissioning

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

Treatment and Disposal of the Radioactive Graphite Waste

Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate Microcapsules

Development of Integrated Treatment System to Minimize LLLW From Purex Reprocessing Plant

Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear Power Plant Operation

Testing of TRANSURANUS Code for RIA Analysis: The FK-1 NSRR Case

Radioactive Waste Water Treatment by Inorganic Membrane System

Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements by Gamma Spectroscopy

Based on 200L Barrels of Low-Level Solid Waste Encapsulates Device Design

N,N,N ′ ,N ′ -Tetra-Methyl-3-Oxy-Pentane-1,5-Diamide (TMPDA): A Promising Back Extractant for Ln(III) and Zr(IV)

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

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