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Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022
Paper No: ICONE29-90172
https://doi.org/10.1115/ICONE29-90172
View Paper titled, On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads
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Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation
Proceedings Papers

Effect of the Plasticity of Piping and Support Structures on the Seismic Response of Piping Systems

Takahiro Okuda, Hideki Takahashi, Tomoyoshi Watakabe, Masaki Morishita
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A001, August 8–12, 2022
Paper No: ICONE29-89097
https://doi.org/10.1115/ICONE29-89097
View Paper titled, Effect of the Plasticity of Piping and Support Structures on the Seismic Response of Piping Systems
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Topics: Earthquake resistant design, Pipes, Piping systems, Plasticity
Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems

Yukihiko Okuda, Akemi Nishida, Michiya Sakai, Yuzo Shiogama, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A023, August 4–6, 2021
Paper No: ICONE28-64586
https://doi.org/10.1115/ICONE28-64586
View Paper titled, Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems
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Topics: Dynamic response, Piping systems, Pipes, Evaluation methods, Design, Mechanical behavior, Nuclear power stations, Probabilistic risk assessment, Structures
Proceedings Papers

Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems

Hyeong-Yeon Lee, Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T06A004, August 4–6, 2021
Paper No: ICONE28-65552
https://doi.org/10.1115/ICONE28-65552
View Paper titled, Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems
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Topics: Creep, Design, High temperature, Pipes, Piping systems, Pressure, Temperature
Proceedings Papers

Design Applicability of the Advanced Spectrum Method Assisted by Time History Analysis for Multiply Supported Piping System

Ayaka Yoshida, Yoshihiro Takayama, Hiromichi Shudo
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, V001T06A007, August 4–5, 2020
Paper No: ICONE2020-16198
https://doi.org/10.1115/ICONE2020-16198
View Paper titled, Design Applicability of the Advanced Spectrum Method Assisted by Time History Analysis for Multiply Supported Piping System
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Topics: Design, Piping systems
Proceedings Papers

The Effects of Compressibility and Piping Geometry on Steamhammer Loads

Frederick J. Moody, Robert Stakenborghs
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, V001T01A001, July 22–26, 2018
Paper No: ICONE26-81003
https://doi.org/10.1115/ICONE26-81003
View Paper titled, The Effects of Compressibility and Piping Geometry on Steamhammer Loads
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Topics: Compressibility, Geometry, Pipes, Stress, Flow (Dynamics), Valves, Turbines, ASME Standards, Fluids, Nuclear power stations
Proceedings Papers

The Influence of Centrifugal Pump Characteristics on Dynamic Loadings on Pipelines After Power Failure

Jerzy Marcinkiewicz, Krzysztof Karaskiewicz, Claes Joheman
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, V001T01A011, July 22–26, 2018
Paper No: ICONE26-81825
https://doi.org/10.1115/ICONE26-81825
View Paper titled, The Influence of Centrifugal Pump Characteristics on Dynamic Loadings on Pipelines After Power Failure
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Topics: Centrifugal pumps, Failure, Pipelines, Pumps, Interpolation, Design, Flow (Dynamics), Pipes, Piping systems, Stress
Proceedings Papers

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018
Paper No: ICONE26-81095
https://doi.org/10.1115/ICONE26-81095
View Paper titled, Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements
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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue
Proceedings Papers

Cyclic Plasticity Behavior of 90° Back-to-Back Pipe Bends Under Cyclic Bending and Steady Pressure

Nak-Kyun Cho, Haofeng Chen
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A082, July 22–26, 2018
Paper No: ICONE26-82386
https://doi.org/10.1115/ICONE26-82386
View Paper titled, Cyclic Plasticity Behavior of 90° Back-to-Back Pipe Bends Under Cyclic Bending and Steady Pressure
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Topics: Pipe bends, Plasticity, Pressure, Structural response analysis, Bearings, Geometry, Piping systems, Stress
Proceedings Papers

Structural Dynamic Transient Analysis of Fire Protection System at a Nuclear Power Plant

Milton Dong, Eugene Tom
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A038, July 22–26, 2018
Paper No: ICONE26-82627
https://doi.org/10.1115/ICONE26-82627
View Paper titled, Structural Dynamic Transient Analysis of Fire Protection System at a Nuclear Power Plant
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Topics: Fire, Nuclear power stations, Structural dynamics, Transient analysis, Stress, Pipeline risers, Piping systems, Risers (Casting), Pipes, Water hammer
Proceedings Papers

Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings

Kenshiro Ishiki, Hirokazu Tsuji, Minoru Kanechika, Yoshinori Mihara
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A002, July 22–26, 2018
Paper No: ICONE26-81072
https://doi.org/10.1115/ICONE26-81072
View Paper titled, Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings
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Topics: Displacement, Nuclear power stations, Structures, Uncertainty, Soil, Hazards, Accidents, Building materials, Chaos, Design
Proceedings Papers

A Validation of RELAP on Predicting Nuclear Power Plant Phenomena

Ji Soo Ahn, Michael Bluck, Matthew Eaton, Chris Jackson
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A006, July 22–26, 2018
Paper No: ICONE26-81424
https://doi.org/10.1115/ICONE26-81424
View Paper titled, A Validation of RELAP on Predicting Nuclear Power Plant Phenomena
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Topics: Nuclear power stations, Thermal stratification, Pipes, Surges, Computational fluid dynamics, Cooling, Errors, Feedwater, Junctions, Piping systems
Proceedings Papers

Study of the Impact of Stellite Material on PWR Co-60 Contamination

Liying Zhang, Yaxiao Wang, Xiaoxia Wang, Bo Gao, Aijun Mi, Yawei Mao
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A041, July 2–6, 2017
Paper No: ICONE25-67859
https://doi.org/10.1115/ICONE25-67859
View Paper titled, Study of the Impact of Stellite Material on PWR Co-60 Contamination
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Topics: Contamination, Pressurized water reactors, Cobalt, Corrosion, Radiation (Physics), Design, Alloys, Circuits, Coolants, Flow (Dynamics)
Proceedings Papers

Piping Vibration and Vibration Damage Prevention Through Screening of Dynamic Susceptibility

Lingfu Zeng, Lennart G. Jansson, Alexander Börjesson
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A057, July 2–6, 2017
Paper No: ICONE25-66658
https://doi.org/10.1115/ICONE25-66658
View Paper titled, Piping Vibration and Vibration Damage Prevention Through Screening of Dynamic Susceptibility
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Topics: Damage, Pipes, Vibration, Piping systems, Stress, Excitation, Finite element analysis, Nuclear industry, Risk, Vibration control
Proceedings Papers

Investigation of Thermal Fatigue Characteristics of Charging Line of RCV in PWR

Naeem Ahmad, XiangBin Li, Iftikhar Ahmad, Nan Li, Shahroze Ahmed, Ahmed Abdul Ghani Abdul Gayoum AlFadl
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A097, July 2–6, 2017
Paper No: ICONE25-67417
https://doi.org/10.1115/ICONE25-67417
View Paper titled, Investigation of Thermal Fatigue Characteristics of Charging Line of RCV in PWR
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Topics: Fatigue, Pressurized water reactors, Nuclear power stations, Transients (Dynamics), Fatigue damage, Fluid structure interaction, Piping systems, Computational fluid dynamics, Control systems, Fatigue analysis
Proceedings Papers

Nonlinear Finite Element Analysis of Class 1 Pressure Vessels

Mingya Chen, Weiwei Yu, Jinhua Shi, Feng Lu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A004, July 2–6, 2017
Paper No: ICONE25-66910
https://doi.org/10.1115/ICONE25-66910
View Paper titled, Nonlinear Finite Element Analysis of Class 1 Pressure Vessels
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Topics: Finite element analysis, Pressure vessels, Stress, Design, Nozzles, Elastic analysis, Failure, Pipes, Reactor vessels, ASME Standards
Proceedings Papers

Tackling Coolant Freezing in Generation-IV Molten Salt Reactors

N. Le Brun, A. Charogiannis, G. F. Hewitt, C. N. Markides
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A067, July 2–6, 2017
Paper No: ICONE25-67984
https://doi.org/10.1115/ICONE25-67984
View Paper titled, Tackling Coolant Freezing in Generation-IV Molten Salt Reactors
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Topics: Coolants, Freezing, Molten salt reactors, Internal flow, Transients (Dynamics), Accidents, Computer simulation, Fluids, Fluorescence, Heat
Proceedings Papers

Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant

Pei-Hsun Huang, Chao-Jen Li
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A002, July 2–6, 2017
Paper No: ICONE25-66022
https://doi.org/10.1115/ICONE25-66022
View Paper titled, Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant
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Topics: Fluid structure interaction, Fluids, Nuclear power stations, Pipes, Simulation, Stress, Boiling water reactors, Cracking (Materials), Deformation, Flow (Dynamics)
Proceedings Papers

Study on Water Hammer in the Overpressure Discharge Pipe of Nuclear Power Plant

Qingmu Xu, Kun Cai, Jie Qin, Junkai Yuan, Juan Li
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A031, July 2–6, 2017
Paper No: ICONE25-66459
https://doi.org/10.1115/ICONE25-66459
View Paper titled, Study on Water Hammer in the Overpressure Discharge Pipe of Nuclear Power Plant
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Topics: Nuclear power stations, Pipes, Water hammer, Steam, Pressure, Spent nuclear fuels, Valves, Water, Cavities, Collisions (Physics)