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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
DOI: https://doi.org/10.1115/ICONE29-90172
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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
DOI: https://doi.org/10.1115/ICONE29-89097
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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
DOI: https://doi.org/10.1115/ICONE29-93082
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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
DOI: https://doi.org/10.1115/ICONE28-64586
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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
DOI: https://doi.org/10.1115/ICONE28-65552
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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
DOI: https://doi.org/10.1115/ICONE2020-16198
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Topics: Design, Piping systems
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
DOI: https://doi.org/10.1115/ICONE26-81424
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Topics: Nuclear power stations, Thermal stratification, Pipes, Surges, Computational fluid dynamics, Cooling, Errors, Feedwater, Junctions, 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
DOI: https://doi.org/10.1115/ICONE26-81003
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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
DOI: https://doi.org/10.1115/ICONE26-81825
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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
DOI: https://doi.org/10.1115/ICONE26-81095
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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
DOI: https://doi.org/10.1115/ICONE26-82386
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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
DOI: https://doi.org/10.1115/ICONE26-82627
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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
DOI: https://doi.org/10.1115/ICONE26-81072
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Topics: Displacement, Nuclear power stations, Structures, Uncertainty, Soil, Hazards, Accidents, Building materials, Chaos, Design
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
DOI: https://doi.org/10.1115/ICONE25-67984
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Topics: Coolants, Freezing, Molten salt reactors, Internal flow, Transients (Dynamics), Accidents, Computer simulation, Fluids, Fluorescence, Heat
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
DOI: https://doi.org/10.1115/ICONE25-67859
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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
DOI: https://doi.org/10.1115/ICONE25-66658
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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
DOI: https://doi.org/10.1115/ICONE25-67417
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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

Research and Design of the Sodium Steam Filter System in Large Liquid Metal Cooled Fast Reactors

Wang Leijian, Lu Yuan, Xiao Changzhi
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A030, July 2–6, 2017
Paper No: ICONE25-67094
DOI: https://doi.org/10.1115/ICONE25-67094
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Topics: Design, Fast neutron reactors, Filters, Liquid metals, Sodium, Steam, Filtration, Valves, Atoms, Chemical properties
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
DOI: https://doi.org/10.1115/ICONE25-66910
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Topics: Finite element analysis, Pressure vessels, Stress, Design, Nozzles, Elastic analysis, Failure, Pipes, Reactor vessels, ASME Standards
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
DOI: https://doi.org/10.1115/ICONE25-66022
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Topics: Fluid structure interaction, Fluids, Nuclear power stations, Pipes, Simulation, Stress, Boiling water reactors, Cracking (Materials), Deformation, Flow (Dynamics)