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Proceedings Papers

An Effect of Bismuth Ion on the Reduction of Terbium Ion in Molten LiCl-KCl Eutectic Salt

Beom Kyu Kim, Byung Gi Park, Hwa Jeong Han, Ji Hye Park, Won Ki Kim
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A022, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82468
https://doi.org/10.1115/ICONE26-82468
View Paper titled, An Effect of Bismuth Ion on the Reduction of Terbium Ion in Molten LiCl-KCl Eutectic Salt
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Topics: Circuits, Electrochemical reactions, Electrodes, Gibbs' free energy, Intermetallic compounds, Phase diagrams, Recycling, Tungsten, Waves
Proceedings Papers

Overview of the U.S. Department of Energy Advanced Waste Forms Development

Kimberly Gray, John Vienna, Patricia Paviet
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81017
https://doi.org/10.1115/ICONE26-81017
View Paper titled, Overview of the U.S. Department of Energy Advanced Waste Forms Development
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Topics: Alloys, Ceramics, Composite materials, Cycles, Durability, Energy generation, Fast neutron reactors, Fuels, Glass, Glass ceramics
Proceedings Papers

Lessons Learned From the Operation of Large-Scale Reprocessing-Recycling Facilities in France: What Is in It for China?

Jean-Pierre Gros
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-68004
https://doi.org/10.1115/ICONE25-68004
View Paper titled, Lessons Learned From the Operation of Large-Scale Reprocessing-Recycling Facilities in France: What Is in It for China?
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Topics: China, Recycling, Spent nuclear fuels, Transparency, Governments, Negotiation, Nuclear fuel cycle, Nuclear power, Nuclear power stations, Safety
Proceedings Papers

D&D and Waste Management: An AREVA Expertise From AREVA Sites Operations to Customers Projects

Stephane Bargues
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-68003
https://doi.org/10.1115/ICONE25-68003
View Paper titled, D&D and Waste Management: An AREVA Expertise From AREVA Sites Operations to Customers Projects
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Topics: Waste management, Decontamination, Nuclear power stations, Storage, Contamination, Feedback, Fuels, Industrial research, Innovation, Irradiation (Radiation exposure)
Proceedings Papers

Fuel-Cell and Electrolysis By-Product D2O Improves Third Way to Mitigate CO2

William Ernest Schenewerk
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T01A001, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49061
https://doi.org/10.1115/NUCLRF2015-49061
View Paper titled, Fuel-Cell and Electrolysis By-Product D2O Improves Third Way to Mitigate CO2
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Topics: Carbon dioxide, Electrolysis, Fuel cells, Nuclear power, Hydrogen, Seawater, Water, Breeder reactors, Condensed matter, Uranium
Proceedings Papers

Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

Jiři Křepel, Valentyn Bykov, Konstantin Mikityuk, Boris Hombourger, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A015, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30396
https://doi.org/10.1115/ICONE22-30396
View Paper titled, Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning
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Topics: Fuels, Molten salt reactors, Recycling, Cycles, Manufacturing, Matlab, Neutron flux, Neutrons, Nuclear fuel cycle, Safety
Proceedings Papers

Preliminary Fuel Cycle Analysis of a Fusion-Driven Subcritical Reactor

Lisheng Mao, Minghuang Wang, Xuewei Fu, Jieqiong Jiang, Yican Wu
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T08A006, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15588
https://doi.org/10.1115/ICONE21-15588
View Paper titled, Preliminary Fuel Cycle Analysis of a Fusion-Driven Subcritical Reactor
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Topics: Nuclear fuel cycle, Light water reactors, Dynamic models, Flow (Dynamics), Uranium, Cycles, Economics , Equilibrium (Physics), Recycling, Sensitivity analysis
Proceedings Papers

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

Zhenhua Zhang, Mingjun Chen, Peide Zhou, Qing Li, Zhiliang Meng, Guowei Zhang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A046, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16727
https://doi.org/10.1115/ICONE21-16727
View Paper titled, CANDU Position and Prospect in Chinese Nuclear Fuel Cycle
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Topics: Nuclear fuel cycle, Nuclear power, Uranium, Certainty, China, Climate, Recycling, Sustainable development, Thermal reactors
Proceedings Papers

Scenario of a Symbiotic Nuclear Fleet Composed of PWRs and SFRs

David Lemasson, Joël Le Mer, Claude Garzenne
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 269-278, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54223
https://doi.org/10.1115/ICONE20-POWER2012-54223
View Paper titled, Scenario of a Symbiotic Nuclear Fleet Composed of PWRs and SFRs
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Topics: Nuclear fuel cycle, Pressurized water reactors, Recycling, Sodium fast reactors
Proceedings Papers

Options for Multiple Recycling of Reprocessed U in PWR: Technical and Economic Comparison

Hubert Druenne, Charles Hardy
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 363-369, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55234
https://doi.org/10.1115/ICONE20-POWER2012-55234
View Paper titled, Options for Multiple Recycling of Reprocessed U in PWR: Technical and Economic Comparison
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Topics: Pressurized water reactors, Recycling
Proceedings Papers

Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?

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

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

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

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
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

New Progresses in the IFMIF Target and Test Cell Design and a Proposal for the Specimen Flow

Kuo Tian, Frederik Arbeiter, Dirk Eilert, Volker Heinzel, Tobias Heupel, Martin Mittwollen, Anton Mo¨slang, Nicola Scheel, Erwin Stratmanns
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 539-546, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29427
https://doi.org/10.1115/ICONE18-29427
View Paper titled, New Progresses in the IFMIF Target and Test Cell Design and a Proposal for the Specimen Flow
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Topics: Design, Flow (Dynamics), Irradiation (Radiation exposure), Conceptual design, Dimensions, Engineering design, Recycling, Vessels
Proceedings Papers

Design Study on Power Flattening to Sodium Cooled Large-Scale CANDLE Burning Reactor With Using Thorium Fuel

Tsuyoshi Okawa, Sinsuke Nakayama, Hiroshi Sekimoto
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 819-824, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30063
https://doi.org/10.1115/ICONE18-30063
View Paper titled, Design Study on Power Flattening to Sodium Cooled Large-Scale CANDLE Burning Reactor With Using Thorium Fuel
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Topics: Combustion, Design, Fuels, Sodium, Power density, Uranium, Neutrons, Coolants, Leakage, Shapes
Proceedings Papers

Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics

Yunhuang Zhang, Jean C. Ragusa
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 879-885, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30153
https://doi.org/10.1115/ICONE18-30153
View Paper titled, Advanced MOX and IMF Fuel Assembly Designs for Multi-Recycling Transuranics
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Topics: Fuels, Manufacturing, Recycling, Pins (Engineering), Uranium, Coating processes, Coatings, Pressurized water reactors, Simulation, Spent nuclear fuels
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29985
https://doi.org/10.1115/ICONE18-29985
View Paper titled, Treatment and Disposal of the Radioactive Graphite Waste
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Topics: Graphite, Carbon, Contamination, Radioactive wastes, Carbon dioxide, Chemical processes, Decontamination, Gases, Nuclear fuels, Nuclear reactors
Proceedings Papers

Volume Reduction of Radioactive Concrete Wastes by Thermal and Mechanical Treatments

Wang Kyu Choi, Byung Youn Min, Kune Woo Lee
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 193-196, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75917
https://doi.org/10.1115/ICONE17-75917
View Paper titled, Volume Reduction of Radioactive Concrete Wastes by Thermal and Mechanical Treatments
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Topics: Concretes, Nuclear decommissioning, Uranium, Weight (Mass), Cements (Adhesives), Heating, Radioactive wastes, Radioactivity, Separation (Technology), Graphite
Proceedings Papers

Agents and Processes Design for TRU Elements Back Extraction in TRPO Process

Meng Wei, Xuegang Liu, Jing Chen
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 123-130, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75652
https://doi.org/10.1115/ICONE17-75652
View Paper titled, Agents and Processes Design for TRU Elements Back Extraction in TRPO Process
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Topics: Design, Recycling, Risk, Waste disposal
Proceedings Papers

Advanced Recycling Core Accommodating Oxide Fuel and Metal Fuel for Closed Fuel Cycle

Kazumi Ikeda, James W. Maddox, Wataru Nakazato, Shigeru Kunishima
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 873-879, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75499
https://doi.org/10.1115/ICONE17-75499
View Paper titled, Advanced Recycling Core Accommodating Oxide Fuel and Metal Fuel for Closed Fuel Cycle
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Topics: Fuels, Metals, Nuclear fuel cycle, Recycling, Equilibrium (Physics), Combustion, Design, Electric power generation, Heat, Heavy metals