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Proceedings Papers

Study on Safety Class 2 Piping Fatigue Evaluation for 60 Years of Design Life

Dae-Geon Lee, Kyoung-Su Kim, Young-Hun Heo, Seong-Ho Cho, Hyeong-Wook Kim
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A004, August 4–6, 2021
Paper No: ICONE28-62333
DOI: https://doi.org/10.1115/ICONE28-62333
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Topics: Design, Fatigue, Pipes, Safety
Proceedings Papers

Study on Local Sub-Cooling Boiling in the Vertical Upward Pipe

Meng-Meng Liu, Zhen Zhang, Xing-Tuan Yang
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A001, August 4–6, 2021
Paper No: ICONE28-61374
DOI: https://doi.org/10.1115/ICONE28-61374
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Topics: Boiling, Cooling, Pipes
Proceedings Papers

Experimental Study on Flow Pattern of 10 mm Vertical Pipe

Wangtao Xu, Qingche He, Meiyue Yan, Wen Zhu, Luteng Zhang, Dan Wu, Tao Huang, Zaiyong Ma, Wan Sun, Liangming Pan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A062, August 4–6, 2021
Paper No: ICONE28-64725
DOI: https://doi.org/10.1115/ICONE28-64725
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Topics: Flow (Dynamics), Pipes, Two-phase flow
Proceedings Papers

Pipe Performance in Long Term Operation Framework: Ageing Issues

S. A. Cancemi, R. Lo Frano
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A089, August 4–6, 2021
Paper No: ICONE28-65931
DOI: https://doi.org/10.1115/ICONE28-65931
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Topics: Nuclear power stations, Pipes
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

Water Hammer Simulation in Two-Phase Flow Regimes Using Open Source Code OpenFOAM

Paul Fuchs, Marco K. Koch
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A001, August 4–6, 2021
Paper No: ICONE28-61351
DOI: https://doi.org/10.1115/ICONE28-61351
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Topics: Computational fluid dynamics, Simulation, Two-phase flow, Water hammer, Pipes, Pressure, Cavitation, Fluid structure interaction, Bubbles, Fluids
Proceedings Papers

Flow Induced Vibration Analysis and Remediation Using a Cartesian Grid Flow Solver

Alexander Boschitsch, Pavel Danilov, Andrew Kaufman, Alan Bilanin
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A015, August 4–6, 2021
Paper No: ICONE28-64842
DOI: https://doi.org/10.1115/ICONE28-64842
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Topics: Design, Flow (Dynamics), Flow-induced vibrations, Junctions, Pipes
Proceedings Papers

Experimental Study on Aerosol Transport Behavior in Multiple Cells With Expandable Connecting Pipe for Safety Assessment of Sodium-Cooled Fast Reactors

Ryota Umeda, Toshiki Kondo, Shin Kikuchi, Akikazu Kurihara
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A002, August 4–6, 2021
Paper No: ICONE28-61200
DOI: https://doi.org/10.1115/ICONE28-61200
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Topics: Aerosols, Fire, Pipes, Safety, Sodium, Sodium fast reactors
Proceedings Papers

Assessment and Analysis of Various Mechanisms in the Coalescence and Breakup Models for Upward Bubbly Flow

Shunran Guan, Jinyu Han, Chenru Zhao, Hanliang Bo
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A006, August 4–6, 2021
Paper No: ICONE28-64436
DOI: https://doi.org/10.1115/ICONE28-64436
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Topics: Bubbles, Bubbly flow, Computational fluid dynamics, Simulation, Flow (Dynamics), Boilers, Boiling, Collisions (Physics), Fluids, Heat transfer
Proceedings Papers

Analysis of Temperature Field in Hot Leg Piping of Space Nuclear Closed Brayton Cycle

Wenkui Ma, Ping Ye, Yue Gao, Gang Zhao, Xiaoyong Yang, Jie Wang
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A050, August 4–6, 2021
Paper No: ICONE28-64526
DOI: https://doi.org/10.1115/ICONE28-64526
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Topics: Brayton cycle, Insulation, Pipes, Temperature
Proceedings Papers

Experiment on Vortex Shedding in Water Medium of Three-Way Closed Branch Pipe

Shuai Liu, Xuan Huang, ZhiPeng Feng, XiaoZhou Jiang, BiHao Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A003, August 4–6, 2021
Paper No: ICONE28-64450
DOI: https://doi.org/10.1115/ICONE28-64450
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Topics: Pipes, Vibration, Vortex shedding, Water
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Paper No: ICONE2020-16897
DOI: https://doi.org/10.1115/ICONE2020-16897
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

Study on the Interaction Between Safety-Related and Non Safety-Related Items in the Component Cooling Water System Room of the Qinshan Nuclear Power Plant in the Earthquake Condition

Liang Zhang, Gang Xu, Yue Wang, Li Chen, Shao Chong Zhou
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, V001T06A028, August 4–5, 2020
Paper No: ICONE2020-16825
DOI: https://doi.org/10.1115/ICONE2020-16825
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Topics: Cooling, Earthquakes, Nuclear power stations, Pipes, Safety, Valves, Water
Proceedings Papers

Feasibility Study for Multi-Branches and Elbow in Stub Pipe System due to Flow-Induced Vibration Using Computational Fluid Dynamics

Khac-Ha Nguyen, Won-Tae Kim, Seung-Pyo Hong, Haein Lee, Ahram Lee
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, V001T03A012, August 4–5, 2020
Paper No: ICONE2020-16431
DOI: https://doi.org/10.1115/ICONE2020-16431
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Topics: Acoustics, Computational fluid dynamics, Flow (Dynamics), Flow-induced vibrations, Pipes, Resonance, Vibration, Vortex shedding
Proceedings Papers

CFD Analysis of S-Gamma Model Coupled With Two-Group Interfacial Area Transport Equations and AMUSIG Model for a Large Diameter Pipe

Sungje Hong, Joshua P. Schlegel, Subash L. Sharma
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, V001T03A014, August 4–5, 2020
Paper No: ICONE2020-16645
DOI: https://doi.org/10.1115/ICONE2020-16645
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Topics: Computational fluid dynamics, Pipes
Proceedings Papers

Effects of Domain-Size on Large-Eddy Simulation for a Forced-Convection Flow in a Pipe With Circumferentially-Varying Heat Flux

Yasuo Hattori, Hitoshi Suto, Keisuke Nakao, Yuma Hasebe, Shuji Ishihara
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, V001T03A017, August 4–5, 2020
Paper No: ICONE2020-16732
DOI: https://doi.org/10.1115/ICONE2020-16732
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Topics: Flow (Dynamics), Forced convection, Heat flux, Large eddy simulation, Pipes, Turbulence
Proceedings Papers

Development on Simulation Method for Two-Phase Flow in Large Diameter Pipes With 90 Degree Elbows

Yoshiteru Komuro, Atsushi Kodama, Yoshiyuki Kondo, Koichi Tanimoto, Takashi Hibiki
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, V001T03A019, August 4–5, 2020
Paper No: ICONE2020-16747
DOI: https://doi.org/10.1115/ICONE2020-16747
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Topics: Pipes, Simulation, Two-phase flow
Proceedings Papers

Experimental Study on Flow Patterns and Pressure Drop of Decaying Swirling Gas-Liquid Flow in a Vertical Pipe

Jiarong Zhang, Li Liu, Shuai Liu, Hanyang Gu
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, V001T01A010, August 4–5, 2020
Paper No: ICONE2020-16484
DOI: https://doi.org/10.1115/ICONE2020-16484
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Topics: Flow (Dynamics), Pipes, Pressure drop, Swirling flow
Proceedings Papers

Proposal of Inspection Rationalization Method and Application for Sodium Cooled Fast Reactor

Yada Hiroki, Takaya Shigeru, Enuma Yasuhiro
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, V001T02A003, August 4–5, 2020
Paper No: ICONE2020-16735
DOI: https://doi.org/10.1115/ICONE2020-16735
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Topics: Fast neutron reactors, Inspection, Pipes, Sodium, Sodium fast reactors