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Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91791
https://doi.org/10.1115/ICONE29-91791
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92520
https://doi.org/10.1115/ICONE29-92520
View Paper titled, Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes
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Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors
Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

Leo A. Carrilho
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16872
https://doi.org/10.1115/ICONE2020-16872
View Paper titled, Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions
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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants
Proceedings Papers

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Yugao Ma, Minyun Liu, Wenbin Han, Biheng Xie, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16100
https://doi.org/10.1115/ICONE2020-16100
View Paper titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs
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Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors
Proceedings Papers

Particle Deposition by Thermophoresis Under High Temperature Conditions in a Helium-Flow

Felix Fischer, Andreas Andris, Wolfgang Lippmann, Antonio Hurtado
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66391
https://doi.org/10.1115/ICONE25-66391
View Paper titled, Particle Deposition by Thermophoresis Under High Temperature Conditions in a Helium-Flow
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Topics: Flow (Dynamics), Helium, High temperature, Particulate matter, Dust, Graphite, Aerosols, Fuels, Safety, Temperature
Proceedings Papers

Simulation of Direct Contact Condensation Using Large Scale Interface Multifluid Model

Vinesh H. Gada, Mohit P. Tandon, Jebin Elias, Andrew Splawski, Simon Lo
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, V004T10A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60786
https://doi.org/10.1115/ICONE24-60786
View Paper titled, Simulation of Direct Contact Condensation Using Large Scale Interface Multifluid Model
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Topics: Condensation, Simulation, Steam, Water, Damping, Drag (Fluid dynamics), Emergency core cooling systems, Flow (Dynamics), Heat, Nuclear power
Proceedings Papers

Isothermal Rectangular Roughness Elements in a Rectangular Cavity Heated at Bottom

M. Yousaf, S. Usman
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A067, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60908
https://doi.org/10.1115/ICONE24-60908
View Paper titled, Isothermal Rectangular Roughness Elements in a Rectangular Cavity Heated at Bottom
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Topics: Cavities, Surface roughness, Algorithms, Fluids, Heat transfer, Lattice Boltzmann methods, Natural convection, Prandtl number, Relaxation (Physics)
Proceedings Papers

A Comparison of Creep-Fatigue Assessment and Modelling Methods

Rami H. Pohja, Stefan B. Holmström
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, V001T07A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30640
https://doi.org/10.1115/ICONE22-30640
View Paper titled, A Comparison of Creep-Fatigue Assessment and Modelling Methods
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Topics: Creep, Fatigue, Modeling, Damage, Design, Cycles, Fatigue damage, Rupture, Steel, Tensile strength
Proceedings Papers

A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld

Seung-gun Lee, Youngho Son
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, V001T01A025, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31083
https://doi.org/10.1115/ICONE22-31083
View Paper titled, A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld
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Topics: Heat treating (Metalworking), Relaxation (Physics), Stress, Finite element analysis, Heat, Alloy steel, Engineering standards, Fracture (Materials), Furnaces, Nuclear power stations
Proceedings Papers

Stress, Strain, and Energy at Fracture of Degraded Surfaces: Study of Replicates of Rough Surfaces

Hector E. Medina, Brian Hinderliter
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A059, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16907
https://doi.org/10.1115/ICONE21-16907
View Paper titled, Stress, Strain, and Energy at Fracture of Degraded Surfaces: Study of Replicates of Rough Surfaces
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Topics: Fracture (Materials), Fracture (Process), Stress, Surface roughness, Failure, Brittleness, Finite element analysis, Licensing, Load bearing capacity, Maintenance
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

Effect of Weld HAZ Mis-Matching on Joint Performances in High Chromium Steel Welded Joint

Masahito Mochizuki
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, 457-466, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54699
https://doi.org/10.1115/ICONE20-POWER2012-54699
View Paper titled, Effect of Weld HAZ Mis-Matching on Joint Performances in High Chromium Steel Welded Joint
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Topics: Steel, Welded joints, Tensile strength, Piping systems, Stainless steel, Welding, Base metals, Breeder reactors, Coolants, Design
Proceedings Papers

The Benefits of Using a Risk-Informed Approach to Resolving GSI-191

Timothy D. Sande, Gilbert L. Zigler, Ernie J. Kee, Bruce C. Letellier, C. Rick Grantom, Zahra Mohaghegh
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 725-734, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54604
https://doi.org/10.1115/ICONE20-POWER2012-54604
View Paper titled, The Benefits of Using a Risk-Informed Approach to Resolving GSI-191
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Topics: Risk, Emergency core cooling systems, Pressurized water reactors, Acceptance criteria, Cooling, Boiling water reactors, Safety, Suction, Accidents, Containment
Proceedings Papers

The Investigation of Shock Waves Forming by Disruption of Vessel With High-Enthalpy Coolant

N. Pribaturin, S. Lezhnin, A. Sorokin, D. Arhipov, M. Bykov, D. Posusaev
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 1263-1269, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30297
https://doi.org/10.1115/ICONE18-30297
View Paper titled, The Investigation of Shock Waves Forming by Disruption of Vessel With High-Enthalpy Coolant
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Topics: Coolants, Enthalpy, Shock waves, Vessels, Pressure, Boiling, Temperature, High pressure (Physics), Nucleation (Physics), Outflow
Proceedings Papers

Coefficients for I-131 Sorption on Different Surfaces

M. M. Stempniewicz
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 35-42, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29290
https://doi.org/10.1115/ICONE18-29290
View Paper titled, Coefficients for I-131 Sorption on Different Surfaces
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Topics: Sorption, Computers, Spectra (Spectroscopy), Dust, Equilibrium (Physics), Graphite, Nuclear fission, Safety, Steel, Desorption
Proceedings Papers

Aging Management of Nuclear Power Plant Reactor Internals

Frank J. Marx, Randy G. Lott, Cheryl L. Boggess, Anne Demma
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 137-144, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75788
https://doi.org/10.1115/ICONE17-75788
View Paper titled, Aging Management of Nuclear Power Plant Reactor Internals
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Topics: Nuclear power stations, Damage, Inspection, Irradiation (Radiation exposure), Finite element analysis, Embrittlement, Stress corrosion cracking, Creep, Engineering simulation, Fatigue
Proceedings Papers

A Discrete Equation Method for Two-Dimensional Calculations of Two-Phase Compressible Mixtures

A. A. Leonov, V. V. Chudanov
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, 505-512, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75586
https://doi.org/10.1115/ICONE17-75586
View Paper titled, A Discrete Equation Method for Two-Dimensional Calculations of Two-Phase Compressible Mixtures
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Topics: Bubbles, Density, Discrete element methods, Flow (Dynamics), Flux (Metallurgy), Relaxation (Physics), Resolution (Optics), Shock tubes, Shock waves
Proceedings Papers

An Approach for Assessing Fuel Assembly’s Structural Integrity Under In-Core Operating Conditions Using Finite Element Method

Wei Zhao, Yuriy Aleshin
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 181-186, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75565
https://doi.org/10.1115/ICONE17-75565
View Paper titled, An Approach for Assessing Fuel Assembly’s Structural Integrity Under In-Core Operating Conditions Using Finite Element Method
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Topics: Finite element methods, Fuels, Stress, Design, Finite element analysis, Irradiation (Radiation exposure), Springs, Structural elements (Construction), Absorption, Creep
Proceedings Papers

Modeling Approach and Predictions of Boron Mixing in Core Bypass of ESBWR

Christopher F. Boyd
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 411-420, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48420
https://doi.org/10.1115/ICONE16-48420
View Paper titled, Modeling Approach and Predictions of Boron Mixing in Core Bypass of ESBWR
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Topics: Boron, Modeling, Computational fluid dynamics, Boundary-value problems, Flow (Dynamics), Transients (Dynamics), Boiling water reactors, Density, Fuels, Geometry
Proceedings Papers

Development of a Risk-Informed IST Program at Palisades Using Top Event Prevention

Robert A. White, David P. Blanchard
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 677-684, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22758
https://doi.org/10.1115/ICONE10-22758
View Paper titled, Development of a Risk-Informed IST Program at Palisades Using Top Event Prevention
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Topics: Risk, Safety, Testing, Pumps, Valves, Defense industry, Reliability, Trains, ASME Boiler and Pressure Vessel Code, In-service testing