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Proceedings Papers

Comparison of the Powderization Effect of Non-Equilibrium Plasma Oxidation and Thermochemical Oxidation Powders of Uranium Dioxide Solids for Actinide Analysis

Zhuoran Ma, Takaharu Tatsuno, Yoshiya Homma, Kenji Konashi, Katsuya Suzuki, Tatsuya Suzuki

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A010, August 8–12, 2022

Paper No: ICONE29-90894

DOI: https://doi.org/10.1115/ICONE29-90894

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Topics: Equilibrium (Physics), Oxidation, Plasmas (Ionized gases), Solids, Uranium

Proceedings Papers

Fundamental Study on Development of Air-Coupled Ultrasonic Imaging Measurement for Fuel Debris Inspection

Hironobu Kiuchi, Shun Kimura, Ari Hamdani, Hideharu Takahashi, Hiroshige Kikura, Daisuke Sasa, Shuichi Ohmori

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A072, July 22–26, 2018

Paper No: ICONE26-82150

DOI: https://doi.org/10.1115/ICONE26-82150

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Topics: Fuels, Inspection, Ultrasonic imaging, Transducers, Imaging, Nuclear power stations, Shapes, Acoustic intensity, Echoes, Fukushima nuclear disaster, Japan, 2011

Proceedings Papers

Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station

Yang Ting, Li Guang Sheng, Li Zeng Fen, Peng Yue, Hu Jian

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A019, July 2–6, 2017

Paper No: ICONE25-66189

DOI: https://doi.org/10.1115/ICONE25-66189

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Topics: Nuclear power stations, Water, Cooling, Economics , Safety, Construction, Design, Failure, Heat sinks, Reservoirs

Proceedings Papers

Developing and Exploring for Treatment Technology of ADU Wastewater Containing High-Concentration Fluorine and Ammonia-Nitrogen

Xingxing Tan, Ning Zhao

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T11A002, June 26–30, 2016

Paper No: ICONE24-60077

DOI: https://doi.org/10.1115/ICONE24-60077

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Topics: Nitrogen, Sewage, Solids, Pipes, Process control, Wastewater treatment

Proceedings Papers

Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser Based Profilimetry

Alexander R. Hagen, Thomas F. Grimes, Brian C. Archambault, Trevor N. Harris, Rusi P. Taleyarkhan

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A036, July 7–11, 2014

Paper No: ICONE22-30325

DOI: https://doi.org/10.1115/ICONE22-30325

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Topics: Fluids, Lasers, Optimization, Particulate matter, Sensors, Simulation, Cavitation, Ions, Neutrons, Acoustics

Proceedings Papers

Numerical Simulation of Single Bubble Moving in Stagnant Solid-Liquid Mixture Pool Using Finite Volume Particle Method

Yuki Aramaki, Takahito Suzuki, Ichiro Miya, Liancheng Guo, Koji Morita

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A053, July 29–August 2, 2013

Paper No: ICONE21-16688

DOI: https://doi.org/10.1115/ICONE21-16688

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Topics: Bubbles, Computer simulation, Particulate matter, Simulation, Fluids, Shapes, Discrete element methods, Drag (Fluid dynamics), Flow (Dynamics), Viscosity

Proceedings Papers

CFD Analysis for the Dome Section of Maanshan Nuclear Power Plant

Wen-Chi Cheng, Yuh-Ming Ferng, Shin-Ru Chen, Ching-Chang Chieng

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A055, July 29–August 2, 2013

Paper No: ICONE21-16769

DOI: https://doi.org/10.1115/ICONE21-16769

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Topics: Computational fluid dynamics, Domes (Structural elements), Nuclear power stations, Temperature distribution, Flow (Dynamics), Leakage, Stress concentration, Computer software, Computers, Coolants

Proceedings Papers

A CFD-Based Integral Pump-Down Model for Computing Solids Transfer From a Mixing Vessel

Michael P. Kinzel, Leonard J. Peltier, Brigette Rosendall, Andri Rizhakov, Kelly J. Knight

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, 607-617, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55203

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55203

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Topics: Computational fluid dynamics, Pumps, Solids, Vessels, Simulation, Slurries, Errors, Modeling

Proceedings Papers

Finite Element Analysis of Elastomers Using ANSYS

Manoj Kunnil, David Yamarthi, Santhosh K. Kompally

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 75-82, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54342

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54342

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Topics: Elastomers, Finite element analysis, Deformation, Design, Solids, Vibration isolation, Cycles, Dimensions, Generators, Mechanical behavior

Proceedings Papers

Upgrades Performed on an Ash Handling Water Pump to Enhance Performance and Extend the Mean Time Between Repair (MTBR)

Robert M. Morgenstern

Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 423-436, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54662

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54662

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Topics: Maintenance, Pumps, Water, Dewatering, Bearings, Damage, Design, Equipment performance, Jet pumps, Power stations

Proceedings Papers

Solids Formation Behavior of Simulated High-Level Liquid Waste During Long-Term Storage

Jin Chen, Xuegang Liu, Yanchao Zhang, Qian’ge He, Jianchen Wang

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 623-627, May 17–21, 2010

Paper No: ICONE18-29590

DOI: https://doi.org/10.1115/ICONE18-29590

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Topics: Solids, Storage, Precipitation, Zirconium, Hazards, Light water reactors, Nuclear fission, Separation (Technology), Spent nuclear fuels, Stability

Proceedings Papers

Next Generation Safety Analysis Methods for SFRs—(4) Development of a Computational Framework on Fluid-Solid Mixture Flow Simulations for the COMPASS Code

Shuai Zhang, Koji Morita, Noriyuki Shirakawa, Yuichi Yamamoto

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, 465-471, July 12–16, 2009

Paper No: ICONE17-75549

DOI: https://doi.org/10.1115/ICONE17-75549

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Topics: Flow simulation, Fluids, Safety, Sodium fast reactors, Discrete element methods, Engineering simulation, Rods, Simulation, Solids, Accidents

Proceedings Papers

Development of the CAD/MCNP Automatic Conversion Code GEOMIT

Hesham R. Nasif, Fukuzo Masuda, Hiromasa Iida, Hidetsugu Morota, Satoshi Sato, Chikara Konno

Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 807-814, July 12–16, 2009

Paper No: ICONE17-75229

DOI: https://doi.org/10.1115/ICONE17-75229

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Topics: Computer-aided design, Shapes, Solids, Density, Errors, Heat

Proceedings Papers

CEA Preliminary Studies for Industrial MOx Reprocessing: From Laboratory Results to Successful First Industrial Campaign on UP2-800 Areva Plant

N. Reynier Tronche, C. Eysseric, JP. Dancausse

Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 51-54, May 11–15, 2008

Paper No: ICONE16-48198

DOI: https://doi.org/10.1115/ICONE16-48198

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Topics: Fuels, Phase transition temperature, Solids, Spent nuclear fuels, Teams, Temperature

Proceedings Papers

R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 3 — Improvement of Basic Fluid Dynamics Models for the COMPASS Code

Shuai Zhang, Koji Morita, Noriyuki Shirakawa, Yuichi Yamamoto

Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 345-350, May 11–15, 2008

Paper No: ICONE16-48475

DOI: https://doi.org/10.1115/ICONE16-48475

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Topics: Fast neutron reactors, Fluid dynamics, Safety, Scientific computing, Algorithms, Particulate matter, Pressure, Simulation, Fluids, Solids

Proceedings Papers

Characterisation of Full-Scale Inactive Cement-Based Intermediate Level Nuclear Wasteforms After One Decade of Storage

Robert J. Caldwell, Newton J. Bowmer, Edward J. Butcher, I. Hugh Godfrey

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 681-689, April 25–29, 2004

Paper No: ICONE12-49072

DOI: https://doi.org/10.1115/ICONE12-49072

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Topics: Cements (Adhesives), Storage, Atomic, molecular, and chemical characteristics, Density, Flocs, Fuels, Solidification, Solids, Spent nuclear fuels, Water

Proceedings Papers

Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations

F. Parozzi, S. Paci

Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 135-144, July 17–20, 2006

Paper No: ICONE14-89275

DOI: https://doi.org/10.1115/ICONE14-89275

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Topics: Safety, Accidents, Accounting, Fire, Aerosols, Chemical processes, Combustion, Cooling, Dust, Fusion reactors

Proceedings Papers

Validating CFD Models of Multiphase Mixing in the Waste Treatment Plant at the Hanford Site

Brigette Rosendall, Chris Barringer, Feng Wen, Kelly J. Knight

Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 393-402, July 17–20, 2006

Paper No: ICONE14-89744

DOI: https://doi.org/10.1115/ICONE14-89744

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Topics: Computational fluid dynamics, Waste treatment facilities, Radioactive wastes, Slurries, Transients (Dynamics), Vessels, Vitrification, Glass, Pulsejets, Rivers

Proceedings Papers

Is Nuclear Power Also the Key to Economically Clean Coal Gasification?

Jay F. Kunze, Gary M. Sandquist, David Martinez Pardo

Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 475-481, July 17–20, 2006

Paper No: ICONE14-89743

DOI: https://doi.org/10.1115/ICONE14-89743

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Topics: Clean coal technology, Fuel gasification, Nuclear power, Carbon dioxide, Oxygen, Water, Combustion, Economics , Fuel cells, Hydrogen

NARROW

Comparison of the Powderization Effect of Non-Equilibrium Plasma Oxidation and Thermochemical Oxidation Powders of Uranium Dioxide Solids for Actinide Analysis

Fundamental Study on Development of Air-Coupled Ultrasonic Imaging Measurement for Fuel Debris Inspection

Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station

Developing and Exploring for Treatment Technology of ADU Wastewater Containing High-Concentration Fluorine and Ammonia-Nitrogen

Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser Based Profilimetry

Numerical Simulation of Single Bubble Moving in Stagnant Solid-Liquid Mixture Pool Using Finite Volume Particle Method

CFD Analysis for the Dome Section of Maanshan Nuclear Power Plant

A CFD-Based Integral Pump-Down Model for Computing Solids Transfer From a Mixing Vessel

Finite Element Analysis of Elastomers Using ANSYS

Upgrades Performed on an Ash Handling Water Pump to Enhance Performance and Extend the Mean Time Between Repair (MTBR)

Solids Formation Behavior of Simulated High-Level Liquid Waste During Long-Term Storage

Next Generation Safety Analysis Methods for SFRs—(4) Development of a Computational Framework on Fluid-Solid Mixture Flow Simulations for the COMPASS Code

Development of the CAD/MCNP Automatic Conversion Code GEOMIT

CEA Preliminary Studies for Industrial MOx Reprocessing: From Laboratory Results to Successful First Industrial Campaign on UP2-800 Areva Plant

R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 3 — Improvement of Basic Fluid Dynamics Models for the COMPASS Code

Characterisation of Full-Scale Inactive Cement-Based Intermediate Level Nuclear Wasteforms After One Decade of Storage

Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations

Validating CFD Models of Multiphase Mixing in the Waste Treatment Plant at the Hanford Site

Is Nuclear Power Also the Key to Economically Clean Coal Gasification?

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