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Proceedings Papers

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

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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

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

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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

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

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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

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

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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

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

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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

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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

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

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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

Preliminary Fuel Cycle Analysis of a Fusion-Driven Subcritical Reactor

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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

Scenario of a Symbiotic Nuclear Fleet Composed of PWRs and SFRs

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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

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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

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

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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

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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

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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

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

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

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

Treatment and Disposal of the Radioactive Graphite Waste

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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

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

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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
Proceedings Papers

Advanced Recycling Reactor Design Study

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Makoto Mito, Shigeru Kunishima, Kim O. Stein, Kazumi Ikeda, Horoyuki Sato
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 909-918, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75698
https://doi.org/10.1115/ICONE17-75698
View Paper titled, Advanced Recycling Reactor Design Study
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Topics: Design, Pumps, Recycling
Proceedings Papers

An Economic Model of Nuclear Reprocessing Using Vensim

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Samuel Brinton, Akira Tokuhiro
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 587-593, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75648
https://doi.org/10.1115/ICONE17-75648
View Paper titled, An Economic Model of Nuclear Reprocessing Using Vensim
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Topics: Climate change, Combustion, Computer software, Construction, Electric power generation, Feedback, Flow (Dynamics), Fuels, Licensing, Light water reactors