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Proceedings Papers

Study on Dynamic Characteristics and Flow Induced Vibration of Tube Bundles Based on the Fluid Structure Coupling Method

Zhipeng Feng, Qian Huang, Shuai Liu, Fengchun Cai, Xi Lv, Xiaozhou Jiang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A009, July 22–26, 2018

Paper No: ICONE26-81342

DOI: https://doi.org/10.1115/ICONE26-81342

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Topics: Flow-induced vibrations, Fluids, Computer simulation, Flow (Dynamics), Acoustics, Structural dynamics, Wave equations, Algorithms, Boilers, Computational fluid dynamics

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

Numerical Study on a Single Square Cylinder Subjected to Vortex-Induced Vibration in HTR-PM

Qiankun Xiao, Li Shi, Xiaoxin Wang, Xiaowei Luo, Xinxin Wu

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, V004T10A008, June 26–30, 2016

Paper No: ICONE24-60230

DOI: https://doi.org/10.1115/ICONE24-60230

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Topics: Cylinders, Vortex-induced vibration, Flow (Dynamics), Vibration, Computational fluid dynamics, Fluid structure interaction, Heat transfer, Boilers, Design, Eddies (Fluid dynamics)

Proceedings Papers

Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code

Koji Morita, Shuai Zhang, Tatsumi Arima, Seiichi Koshizuka, Yoshiharu Tobita, Hidemasa Yamano, Takahiro Ito, Noriyuki Shirakawa, Fusao Inoue, Hiroaki Yugo, Masanori Naitoh, Hidetoshi Okada, Yuichi Yamamoto, Masashi Himi, Etsujo Hirano, Sensuke Shimizu, Masaya Oue

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 855-863, May 17–21, 2010

Paper No: ICONE18-29886

DOI: https://doi.org/10.1115/ICONE18-29886

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Topics: Accidents, Sodium fast reactors, Failure, Fuels, Ducts, Freezing, Particulate matter, Simulation, Steel, Boiling

Proceedings Papers

Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA

Bjo¨rn Sva¨rd, Jan-Anders Larsson, Philip Ma˚rtensson, Bjo¨rn Lundin

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 671-677, May 17–21, 2010

Paper No: ICONE18-30189

DOI: https://doi.org/10.1115/ICONE18-30189

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Topics: Boiling water reactors, Finite element analysis, Power uprate, Structural dynamics, Containment, Dynamic analysis, Fluids, Reactor vessels, Safety, Stress

Proceedings Papers

Next Generation Safety Analysis Methods for SFRs—(5) Structural Mechanics Models of COMPASS Code and Verification Analyses

Noriyuki Shirakawa, Yasushi Uehara, Masanori Naitoh, Hidetoshi Okada, Yuichi Yamamoto, Seiichi Koshizuka

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, 425-434, July 12–16, 2009

Paper No: ICONE17-75532

DOI: https://doi.org/10.1115/ICONE17-75532

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Topics: Safety, Sodium fast reactors, Structural analysis, Structural mechanics, Design, Fluid dynamics, Fracture (Materials), Fracture (Process), Particulate matter, Phase transitions

Proceedings Papers

Blind Prediction of SMART 2008 Seismic Structural Response Test Results

Pentti Varpasuo, Jukka Ka¨hko¨nen

Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 131-137, May 11–15, 2008

Paper No: ICONE16-48397

DOI: https://doi.org/10.1115/ICONE16-48397

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Topics: Computer simulation, Concretes, Design, Design methodology, Displacement, Dynamic response, Earthquake resistant design, Earthquakes, Excitation, Reinforced concrete

Proceedings Papers

Flow Instabilities and Main Steam Line Vibrations in a Pressurized Water Reactor

Mats Henriksson, Johan Westin, Tord Granha¨ll, Lars Andersson, Lars-Erik Bjerke

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 909-920, April 14–18, 2002

Paper No: ICONE10-22531

DOI: https://doi.org/10.1115/ICONE10-22531

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Topics: Flow instability, Pressurized water reactors, Steam, Vibration, Boilers, Pressure, Nozzles, Testing, Flow (Dynamics), Computational fluid dynamics

Proceedings Papers

Analyses of Ex-Vessel Steam Explosion and Its Structural Dynamic Response for a Typical PWR Plant

Osamu Kawabata

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 41-49, April 25–29, 2004

Paper No: ICONE12-49105

DOI: https://doi.org/10.1115/ICONE12-49105

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Topics: Explosions, Pressurized water reactors, Steam, Structural dynamics, Vessels

Proceedings Papers

An Analytical Method to Predict Fretting-Wear Damage in the Double 90° U-Bend Tubes

Seog-Nam Choi, Ki-Seok Yoon, Taek-Sang Choi

Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 173-179, July 17–20, 2006

Paper No: ICONE14-89425

DOI: https://doi.org/10.1115/ICONE14-89425

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Topics: Damage, Wear, Flow (Dynamics), Boilers, Fluids, Adhesives, Clearances (Engineering), Excitation, Heat exchangers, Structural dynamics

NARROW

Study on Dynamic Characteristics and Flow Induced Vibration of Tube Bundles Based on the Fluid Structure Coupling Method

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

Numerical Study on a Single Square Cylinder Subjected to Vortex-Induced Vibration in HTR-PM

Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code

Experiences From Structural Dynamic Analysis Projects of BWR Plants Within the Scope of Power Uprate Projects Using FEA

Next Generation Safety Analysis Methods for SFRs—(5) Structural Mechanics Models of COMPASS Code and Verification Analyses

Blind Prediction of SMART 2008 Seismic Structural Response Test Results

Flow Instabilities and Main Steam Line Vibrations in a Pressurized Water Reactor

Analyses of Ex-Vessel Steam Explosion and Its Structural Dynamic Response for a Typical PWR Plant

An Analytical Method to Predict Fretting-Wear Damage in the Double 90° U-Bend Tubes

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