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Proceedings Papers

Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor

Keiko Chitose, Yoshiaki Tachi, Toshio Wakabayashi, Naoyuki Takaki
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81331
https://doi.org/10.1115/ICONE26-81331
View Paper titled, Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor
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Topics: Geometry, Sodium fast reactors, Fuels, Compacting, Neutrons, Coolants, Deformation, Design, Feedback, Leakage
Proceedings Papers

Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium

Liang Hu, Kui Ge, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A024, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81400
https://doi.org/10.1115/ICONE26-81400
View Paper titled, Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium
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Topics: Sodium, Copper, Pressure, Sodium fast reactors, Accidents, Boiling, Ceramics, Compacting, Coolants, Cooling
Proceedings Papers

Analysis of the Thermal-Hydraulic and Mechanical Performance of Intermediate Heat Exchangers Used in Systems With Very High Temperature Nuclear Reactors

Raciel de la Torre Valdés, Juan Luis Francois Lacouture
Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T04A004, June 24–28, 2018
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2018-7620
https://doi.org/10.1115/NUCLRF2018-7620
View Paper titled, Analysis of the Thermal-Hydraulic and Mechanical Performance of Intermediate Heat Exchangers Used in Systems With Very High Temperature Nuclear Reactors
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Topics: Equipment performance, Heat exchangers, High temperature, Nuclear reactors, Computational fluid dynamics, Design, Stress, Circuits, Compacting, Dimensions
Proceedings Papers

Influence of Working Pressure and Pressure Difference on Static Droplet Evaporation Characteristics

Fulong Zhao, Chenru Zhao, Hanliang Bo, Ying Liu
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A004, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66039
https://doi.org/10.1115/ICONE25-66039
View Paper titled, Influence of Working Pressure and Pressure Difference on Static Droplet Evaporation Characteristics
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Topics: Drops, Evaporation, Pressure, Steam, Water, Vapors, Nuclear power stations, Power stations, Separation (Technology), Water vapor
Proceedings Papers

Analysis of the Effects Caused by the Core Compaction Into LFR Reactor

Rosa Lo Frano, Pugliese Giovanni
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A002, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60022
https://doi.org/10.1115/ICONE24-60022
View Paper titled, Analysis of the Effects Caused by the Core Compaction Into LFR Reactor
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Topics: Compacting, Buckling, Coolants, Deformation, Displacement, Earthquakes, Fast neutron reactors, Finite element methods, Finite element model, Fuels
Proceedings Papers

Safety Evaluation of Prototype Fast-Breeder Reactor: Analysis of ULOF Accident to Demonstrate In-Vessel Retention

Tohru Suzuki, Yoshiharu Tobita, Kenichi Kawada, Hirotaka Tagami, Joji Sogabe
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A020, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30604
https://doi.org/10.1115/ICONE22-30604
View Paper titled, Safety Evaluation of Prototype Fast-Breeder Reactor: Analysis of ULOF Accident to Demonstrate In-Vessel Retention
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Topics: Accidents, Engineering prototypes, Safety, Vessels, Fuels, Licensing, Failure, Heat, Cooling, Boiling
Proceedings Papers

Validation DualSPHysics Code for Liquid Sloshing Phenomena

Sergei K. Buruchenko, Alejandro J. C. Crespo
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A041, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30968
https://doi.org/10.1115/ICONE22-30968
View Paper titled, Validation DualSPHysics Code for Liquid Sloshing Phenomena
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Topics: Sloshing, Simulation, Accidents, Compacting, Fuels, Hydrodynamics, Liquid metals, Nuclear power, Numerical analysis, Particulate matter
Proceedings Papers

Synthesis of Nanostructured Fuels: Mimicking the High Burn-Up Structure

Vaclav Tyrpekl, Raquel Jovani-Abril, Michael Holzhäuser
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A023, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30952
https://doi.org/10.1115/ICONE22-30952
View Paper titled, Synthesis of Nanostructured Fuels: Mimicking the High Burn-Up Structure
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Topics: Fuels, Nanoparticles, Sintering, Compacting, Density, Diffraction, Electron microscopy, Grain size, Nuclear fission, Nuclear reactors
Proceedings Papers

Comparative Study on Self-Compacting Concrete Pouring Methods of AP1000 Structure Module

Shuai Dai, Zhonghao Ye, Erfei Li, Chuyao Zheng
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A056, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16823
https://doi.org/10.1115/ICONE21-16823
View Paper titled, Comparative Study on Self-Compacting Concrete Pouring Methods of AP1000 Structure Module
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Topics: Compacting, Concrete placement, Concretes, Construction, Modular construction
Proceedings Papers

Finite Element Modeling Applied to Nuclear Fuel Pellet Fabrication

Leo Carrilho, Steven C. Johnson
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, 315-324, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54248
https://doi.org/10.1115/ICONE20-POWER2012-54248
View Paper titled, Finite Element Modeling Applied to Nuclear Fuel Pellet Fabrication
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Topics: Finite element analysis, Manufacturing, Modeling, Nuclear fuels, Compacting, Bulk solids, Cavities, Density, Ceramics, Die pressing
Proceedings Papers

Analysis of Central Sloshing Experiment Using Smoothed Particle Hydrodynamics (SPH) Method

Alexander Vorobyev, Vladimir Kriventsev, Werner Maschek
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 751-759, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29805
https://doi.org/10.1115/ICONE18-29805
View Paper titled, Analysis of Central Sloshing Experiment Using Smoothed Particle Hydrodynamics (SPH) Method
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Topics: Hydrodynamics, Particulate matter, Sloshing, Numerical analysis, Simulation, Accidents, Compacting, Computation, Containers, Fuels
Proceedings Papers

Thermal Conduction Experiments on Compacted GMZ Bentonite Blocks as the Potential Buffer Materials for HLW Disposal Purpose

Guang-yuan Ren, Xiao-dong Liu, Qing-chun Chen, Guo-ping Zhu, Quan-shui Chen
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 413-419, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29287
https://doi.org/10.1115/ICONE18-29287
View Paper titled, Thermal Conduction Experiments on Compacted GMZ Bentonite Blocks as the Potential Buffer Materials for HLW Disposal Purpose
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Topics: Heat conduction, Polishing equipment, Temperature, Cylinders, Heat, Temperature gradient, Compacting, Density, Design, Heating
Proceedings Papers

Implementation of a Pressure Drop Model for the CFD Simulation of Clogged Containment Sump Strainers

Alexander Grahn, Eckhard Krepper, Frank-Peter Weiß, So¨ren Alt, Wolfgang Ka¨stner, Alexander Kratzsch, Rainer Hampel
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 427-438, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75249
https://doi.org/10.1115/ICONE17-75249
View Paper titled, Implementation of a Pressure Drop Model for the CFD Simulation of Clogged Containment Sump Strainers
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Topics: Computational fluid dynamics, Containment, Pressure drop, Simulation, Fibers, Particulate matter, Porosity, Accidents, Compacting, Coolants
Proceedings Papers

Spent Resin Hot Compaction at Tihange NPP

Baudouin Centner, David Charpentier
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, 131-138, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75696
https://doi.org/10.1115/ICONE17-75696
View Paper titled, Spent Resin Hot Compaction at Tihange NPP
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Topics: Compacting, Nuclear power stations, Resins, Acceptance criteria, Fracture (Materials), Optimization, Water, Boiling water reactors, Brittleness, Condensed matter
Proceedings Papers

Modeling Atmospheric Releases From LLRW Mechanical Shredder

Mark Ledoux, Jeff Gardner, Gary M. Sandquist
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 835-843, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48547
https://doi.org/10.1115/ICONE16-48547
View Paper titled, Modeling Atmospheric Releases From LLRW Mechanical Shredder
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Topics: Meteorology, Modeling, Computers, Air pollution control, Compacting, Metals, Radioactive substances
Proceedings Papers

Thoria-Based Cermet Nuclear Fuel: Cermet Fabrication and Behavior Estimates

Sean M. McDeavitt, T. J. Downar, A. A. Solomon, S. T. Revankar, M. C. Hash, A. S. Hebden
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 59-67, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22317
https://doi.org/10.1115/ICONE10-22317
View Paper titled, Thoria-Based Cermet Nuclear Fuel: Cermet Fabrication and Behavior Estimates
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Topics: Cermets, Manufacturing, Nuclear fuels, Fuels, Nuclear fuel cycle, Temperature, Zirconium, Ceramics, Compacting, Cycles
Proceedings Papers

Technology Perspectives on the Management of Spent-Resin Wastes Generated From Nuclear Power Reactor Operations

Shiv Vijayan, Makoto Kikuchi, Akihiro Komatsu
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 405-412, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22573
https://doi.org/10.1115/ICONE10-22573
View Paper titled, Technology Perspectives on the Management of Spent-Resin Wastes Generated From Nuclear Power Reactor Operations
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Topics: Nuclear reactors, Resins, Radioisotopes, Storage, Carbon, Half-life, Acceptance criteria, Compacting, Drying, Heavy metals