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Proceedings Papers

Experimental Study on Flow Patterns of Decaying Swirling Gas-Liquid Flow in a Horizontal Pipe

Shuai Liu, Li Liu, Jiarong Zhang, Hanyang Gu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A016, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16224
https://doi.org/10.1115/ICONE2020-16224
View Paper titled, Experimental Study on Flow Patterns of Decaying Swirling Gas-Liquid Flow in a Horizontal Pipe
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Topics: Flow (Dynamics), Pipes, Swirling flow, Separation (Technology), Water, Bubbles, Chain, Design, Drops, Fluids
Proceedings Papers

Measurement Method of Equivalent Water Level for Nuclear Steam Generator Based on Data Fusion

Xianling Li, Zhiwu Ke, Mo Tao
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A018, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66539
https://doi.org/10.1115/ICONE25-66539
View Paper titled, Measurement Method of Equivalent Water Level for Nuclear Steam Generator Based on Data Fusion
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Topics: Data fusion, Nuclear reactor steam generators, Water, Control equipment, Sensors, Boilers, Feedwater, Filters, Flow (Dynamics), Low-pass filters
Proceedings Papers

Fuzzy Logic Controller Architecture for Water Level Control in Nuclear Power Plant Steam Generator (SG) Using ANFIS Training Method

Naser Vosoughi, Zahra Naseri
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 1-5, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22015
https://doi.org/10.1115/ICONE10-22015
View Paper titled, Fuzzy Logic Controller Architecture for Water Level Control in Nuclear Power Plant Steam Generator (SG) Using ANFIS Training Method
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Topics: Boilers, Control equipment, Fuzzy logic, Nuclear power stations, Water, Power stations, Computer simulation, Flow (Dynamics), Nuclear reactor steam generators, Physics
Proceedings Papers

The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators

John M. Dyke
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 393-395, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49059
https://doi.org/10.1115/ICONE12-49059
View Paper titled, The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators
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Topics: Boilers, Coolants, Nuclear reactor steam generators, Vibration, Boiling, Bubbles, Design, Flow (Dynamics), Geometry, Japan Society of Mechanical Engineers
Proceedings Papers

Modeling and Simulation of Cross-Flow Induced Vibrations in Tube Bundles Using Bondgraph Approach

M. Afzaal Malik, Badar Rashid, M. Anwar Khan, Khawaja Sajid Bashir, Shahab Khushnood
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 133-145, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89367
https://doi.org/10.1115/ICONE14-89367
View Paper titled, Modeling and Simulation of Cross-Flow Induced Vibrations in Tube Bundles Using Bondgraph Approach
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Topics: Cross-flow, Modeling, Simulation, Vibration, Acoustics, Computer software, Damping, Excitation, Flow-induced vibrations, Fluids