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Yu Weng
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Journal Articles

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401.
Paper No: NERS-17-1237
DOI: https://doi.org/10.1115/1.4045125
Published Online: November 29, 2019
View Article titled, Experimental Investigation on Flash Evaporation Related to Pipe Leakage
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Topics: Evaporation, Flow (Dynamics), High temperature, Leakage, Pipes, Pressure, Sensors, Sprays, Temperature, Temperature distribution
Proceedings Papers

Dynamic Seismic Response Analysis of Nuclear Storage Tank Based on Fluid-Structure Coupling Method

Yu Weng, Lang Liu, Yang Jiang, Hongfang Gu, Haijun Wang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A064, July 2–6, 2017
Paper No: ICONE25-66835
DOI: https://doi.org/10.1115/ICONE25-66835
View Paper titled, Dynamic Seismic Response Analysis of Nuclear Storage Tank Based on Fluid-Structure Coupling Method
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Topics: Fluids, Storage tanks, Computational fluid dynamics, Finite element methods, Flow (Dynamics), Displacement, Earthquakes, Stress, Vessels, Turbulence
Proceedings Papers

Experimental Investigation on the Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A026, July 2–6, 2017
Paper No: ICONE25-67251
DOI: https://doi.org/10.1115/ICONE25-67251
View Paper titled, Experimental Investigation on the Pipe Leakage
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Topics: Leakage, Pipes, Temperature, Fracture (Materials), Pipelines, Nuclear power stations, High temperature, Fatigue, Fluids, High pressure (Physics)
Proceedings Papers

Investigation of Transient Flow and Heat Transfer for Passive Nuclear Reactor Direct Safety Injection

Yu Weng, Lang Liu, Yang Jiang, Hongfang Gu, Haijun Wang
Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T03A003, June 26–30, 2017
Paper No: NUCLRF2017-3452
DOI: https://doi.org/10.1115/NUCLRF2017-3452
View Paper titled, Investigation of Transient Flow and Heat Transfer for Passive Nuclear Reactor Direct Safety Injection
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Topics: Heat transfer, Nuclear reactors, Safety, Unsteady flow, Flow (Dynamics), Reactor vessels, Transients (Dynamics), Accidents, Computational fluid dynamics, Nozzles
Proceedings Papers

A Numerical Solution for the Transient Inverse Heat Conduction Problem

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Proc. ASME. POWER2017-ICOPE-17, Volume 2: I&C, Digital Controls, and Influence of Human Factors; Plant Construction Issues and Supply Chain Management; Plant Operations, Maintenance, Aging Management, Reliability and Performance; Renewable Energy Systems: Solar, Wind, Hydro and Geothermal; Risk Management, Safety and Cyber Security; Steam Turbine-Generators, Electric Generators, Transformers, Switchgear, and Electric BOP and Auxiliaries; Student Competition; Thermal Hydraulics and Computational Fluid Dynamics, V002T13A007, June 26–30, 2017
Paper No: POWER-ICOPE2017-3347
DOI: https://doi.org/10.1115/POWER-ICOPE2017-3347
View Paper titled, A Numerical Solution for the Transient Inverse Heat Conduction Problem
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Topics: Heat conduction, Transients (Dynamics), Temperature, Temperature distribution, Exterior walls, Pipelines, Fatigue, Pipes, Cycles, Fluids