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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

Finite Element Models of Progressive Failure of Grain Boundaries

Mihaela Irina Uplaznik, Leon Cizelj, Igor Simonovski
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, 545-550, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55191
https://doi.org/10.1115/ICONE20-POWER2012-55191
View Paper titled, Finite Element Models of Progressive Failure of Grain Boundaries
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Topics: Failure, Finite element model, Grain boundaries, Computational methods, Damage, Modeling, Stress corrosion cracking, Alloys, Anisotropy, Cracking (Materials)
Proceedings Papers

Assessing the Integrity of Generator Stator End Windings

Matthew Ellis, Joop Kraijesteijn
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, 387-392, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54570
https://doi.org/10.1115/ICONE20-POWER2012-54570
View Paper titled, Assessing the Integrity of Generator Stator End Windings
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Topics: Generators, Stators, Stiffness, Testing, Corrective actions, Dampers, Damping, Excitation, Impulse (Physics), Insulation
Proceedings Papers

Preliminary Discussion on LFR Fuel Pin Design: Current Status, Fuel Modeling and Open Issues

Davide Rozzia, Alessandro Del Nevo, Mariano Tarantino, Nicola Forgione
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, 467-473, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54728
https://doi.org/10.1115/ICONE20-POWER2012-54728
View Paper titled, Preliminary Discussion on LFR Fuel Pin Design: Current Status, Fuel Modeling and Open Issues
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Topics: Design, Fuels, Modeling, Fuel rods, Cladding systems (Building), Conceptual design, Fast neutron reactors, High temperature, Irradiation (Radiation exposure), Sodium
Proceedings Papers

Compatibility of Ferritic/Martensitic Steels With Flowing Lead-Bismuth Eutectic at 450°–550°C and 10 −6 Mass% Dissolved Oxygen

Carsten Schroer, Olaf Wedemeyer, Josef Novotny, Aleksandr Skrypnik, Jürgen Konys
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, 325-335, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54277
https://doi.org/10.1115/ICONE20-POWER2012-54277
View Paper titled, Compatibility of Ferritic/Martensitic Steels With Flowing Lead-Bismuth Eutectic at 450°–550°C and 10 −6 Mass% Dissolved Oxygen
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Topics: Martensitic steel, Oxygen, Corrosion, Flow (Dynamics), Steel
Proceedings Papers

Nanostructural Characterization of Ni-Base Alloy/Low Alloy Steel Dissimilar Metal Weld (DMW) Interfaces

Kyoung Joon Choi, Jong Jin Kim, Ji Hyun Kim
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, 551-558, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55199
https://doi.org/10.1115/ICONE20-POWER2012-55199
View Paper titled, Nanostructural Characterization of Ni-Base Alloy/Low Alloy Steel Dissimilar Metal Weld (DMW) Interfaces
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Topics: Alloy steel, Alloys, Metals, Nozzles, Filler metals, Light water reactors, Secondary ion mass spectrometry, Welded joints, Atoms, Boilers
Proceedings Papers

Fracture Toughness of Nuclear Graphite NBG-18

Haiyan Li, Gyanender Singh, Young Heo, Lianshan Lin, Alex Fok
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, 393-397, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54581
https://doi.org/10.1115/ICONE20-POWER2012-54581
View Paper titled, Fracture Toughness of Nuclear Graphite NBG-18
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Topics: Fracture toughness, Graphite
Proceedings Papers

Analysis of the Transient Electromagnetic Field of Direct Action Solenoid Valve

Qianfeng Liu, Hanliang Bo, Benke Qin
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, 475-479, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54786
https://doi.org/10.1115/ICONE20-POWER2012-54786
View Paper titled, Analysis of the Transient Electromagnetic Field of Direct Action Solenoid Valve
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Topics: Electromagnetic fields, Hydraulic drive systems, Solenoids, Transients (Dynamics), Valves
Proceedings Papers

Atomistic Modeling of Interstitial Diffusion of Oxygen in Nickel Chromium Binary Alloy

Jong Jin Kim, Ji Hyun Kim
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, 559-564, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55202
https://doi.org/10.1115/ICONE20-POWER2012-55202
View Paper titled, Atomistic Modeling of Interstitial Diffusion of Oxygen in Nickel Chromium Binary Alloy
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Topics: Alloys, Diffusion (Physics), Modeling, Nickel, Oxygen, Water, Chemistry, Density functional theory, Diffusion processes, High temperature
Proceedings Papers

Impact of Weld Sequencing and Fabrication on Residual Stress Fields

F. W. Brust, T. Zhang, G. Wilkowski, H. Xu, K. Wichman
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, 399-408, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54585
https://doi.org/10.1115/ICONE20-POWER2012-54585
View Paper titled, Impact of Weld Sequencing and Fabrication on Residual Stress Fields
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Topics: Manufacturing, Stress, Welding, Nuclear industry, Residual stresses, Stress corrosion cracking, ASME Standards, Cladding systems (Building), Cracking (Materials), Design
Proceedings Papers

EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
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, 481-489, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54965
https://doi.org/10.1115/ICONE20-POWER2012-54965
View Paper titled, EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels
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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Dosimeters, Pressure vessels, Chemical kinetics, Dosimetry
Proceedings Papers

Use of FEA Software in Diagnosing Valve Performance Degradation

Gregory Kramer, Bob Stakenborghs, Sean Moles, Lindsey Dziuba
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, 565-571, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55242
https://doi.org/10.1115/ICONE20-POWER2012-55242
View Paper titled, Use of FEA Software in Diagnosing Valve Performance Degradation
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Topics: Computer software, Finite element analysis, Valves, Leakage, Maintenance, Simulation, Disks, Gates (Closures), Inspection, Nuclear industry
Proceedings Papers

Effect of Feeding Velocity on Wear Behavior of Graphite Ball Under Elevating Process With HTGR Fuel Handling System

Zhipeng Chen, Xiaowei Luo, Suyuan Yu
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, 337-344, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54357
https://doi.org/10.1115/ICONE20-POWER2012-54357
View Paper titled, Effect of Feeding Velocity on Wear Behavior of Graphite Ball Under Elevating Process With HTGR Fuel Handling System
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Topics: Fuels, Graphite, Very high temperature reactors, Wear, Stainless steel, Cutting, Gas cooled reactors, Nitrogen, Surface roughness, Temperature
Proceedings Papers

Radiation Resistance of Rubber Compounds for Gaskets (Second Report)

Mitsuyuki Nakano, Haruko Sasaki
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, 491-497, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54985
https://doi.org/10.1115/ICONE20-POWER2012-54985
View Paper titled, Radiation Resistance of Rubber Compounds for Gaskets (Second Report)
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Topics: Compression, EPDM rubber, Fourier transform infrared spectroscopy, Gaskets, Radiation (Physics), Rubber, Rubber compounds, Silicone rubber
Proceedings Papers

Long Term Strategy for Pipeline Replacement due to FAC Degradation at EDF Using BRT-CICERO™ Software

S. Friol, R. Lafon-Delpit, S. Trevin
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, 409-415, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54647
https://doi.org/10.1115/ICONE20-POWER2012-54647
View Paper titled, Long Term Strategy for Pipeline Replacement due to FAC Degradation at EDF Using BRT-CICERO™ Software
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Topics: Computer software, Pipelines, Nuclear power stations, Pipes, Alloys, Corrosion, Maintenance, Safety, Steam, Water
Proceedings Papers

Evaluation of Thermal Stress Distribution With Elasticoluminescent Materials

Wei Liu, Taku Nagatake, Kazuyuki Takase, C. X. Wu, Daisuke Ono, Ueno Naohiro, Hiroshi Yamada, C. N. Xu
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, 345-350, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54360
https://doi.org/10.1115/ICONE20-POWER2012-54360
View Paper titled, Evaluation of Thermal Stress Distribution With Elasticoluminescent Materials
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Topics: Thermal stresses, Luminescence, Temperature, High temperature, Stress, Bridges (Structures), Deformation, Temperature distribution, Visualization
Proceedings Papers

Ramifications of RAM

Brian M. Wodka
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, 417-421, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54658
https://doi.org/10.1115/ICONE20-POWER2012-54658
View Paper titled, Ramifications of RAM
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Topics: ASME Standards, Construction, Design, Maintainability, Power stations, Reliability
Proceedings Papers

Life Cycle Management of Gas Turbine: An OEM Independent Approach

Joop Kraijesteijn, Eric Vogelaar
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, 499-506, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55020
https://doi.org/10.1115/ICONE20-POWER2012-55020
View Paper titled, Life Cycle Management of Gas Turbine: An OEM Independent Approach
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Topics: Gas turbines, Life cycle management, Inspection, Failure analysis, Maintenance, Quality control, Combustion, Compressors, Dynamics (Mechanics), Nondestructive evaluation
Proceedings Papers

Stress Corrosion Cracking Behavior Around Interface Between Nickel Base Alloy (Alloy182) and Low-Alloy Steel

Yu Itabashi, Yohei Sakakibara, Masahiro Takanashi, Guen Nakayama, Takashi Hirano
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, 573-582, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55266
https://doi.org/10.1115/ICONE20-POWER2012-55266
View Paper titled, Stress Corrosion Cracking Behavior Around Interface Between Nickel Base Alloy (Alloy182) and Low-Alloy Steel
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Topics: Alloys, Nickel, Steel, Stress corrosion cracking, Fracture (Materials), Stress, Water, Electrical conductivity, Light water reactors, Coolants
Proceedings Papers

Qualification of a New Insulation Material Concept for Nuclear Power Plants Based on Aerogel ®

Sören Alt, Wolfgang Kästner, Josep Badelles
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, 351-357, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54431
https://doi.org/10.1115/ICONE20-POWER2012-54431
View Paper titled, Qualification of a New Insulation Material Concept for Nuclear Power Plants Based on Aerogel ®
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Topics: Insulation, Nuclear power stations, Steam, Flow (Dynamics), Pipes, Pressurized water reactors, Boron, Accidents, Coolants, Density