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Yuan Fu
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Proceedings Papers

Experimental and Numerical Study on Convective Heat Transfer Characteristic in the Turbulent Region of Molten Salt in Shell-Side of Shell and Tube Heat Exchanger

Meng-Ting Ding, Yu-Shuang Chen, Yuan Fu
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A022, August 8–12, 2022
Paper No: ICONE29-92752
https://doi.org/10.1115/ICONE29-92752
View Paper titled, Experimental and Numerical Study on Convective Heat Transfer Characteristic in the Turbulent Region of Molten Salt in Shell-Side of Shell and Tube Heat Exchanger
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Topics: Computational fluid dynamics, Convection, Heat exchangers, Shells, Turbulence
Proceedings Papers

Design and Test for a High-Temperature Molten Salt Pump

Zhong Li, Yuan Fu, Jianyu Zhang, Liancheng Lin, Jianping Huang, Wenyu Mao, Dongsheng Yang, Dandan Zhao, Xiao Wang
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 208-222, June 23–25, 2014
Paper No: NRC2014-5024
https://doi.org/10.1115/NRC2014-5024
View Paper titled, Design and Test for a High-Temperature Molten Salt Pump
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Topics: Design, High temperature, Pumps, Temperature, Hydraulics, Bearings, Flow (Dynamics), Thermal stresses, Corrosion resistance, Engines
Proceedings Papers

Preliminary Study of the Use of Freeze-Valves for a Passive Shutdown System in Molten Salt Reactors

Qiming Li, Zhongfeng Tang, Yuan Fu, Zhong Li, Naxiu Wang
Proc. ASME. NRC2014, ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium, 325-341, June 23–25, 2014
Paper No: NRC2014-5025
https://doi.org/10.1115/NRC2014-5025
View Paper titled, Preliminary Study of the Use of Freeze-Valves for a Passive Shutdown System in Molten Salt Reactors
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Topics: Molten salt reactors, Valves, Design, Accidents, Chain, Control systems, Finite element methods, Fuels, Generation IV reactors, Graphite
Proceedings Papers

Numerical Study on the Creep Strain Characteristics for TMSR Reactor Coolant Piping Under Thermal Loading

Wei Gong, Xiaochun Zhang, Mingqiang Xie, Yuan Fu, Xiao Wang
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A058, July 15–20, 2018
Paper No: PVP2018-84333
https://doi.org/10.1115/PVP2018-84333
View Paper titled, Numerical Study on the Creep Strain Characteristics for TMSR Reactor Coolant Piping Under Thermal Loading
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Topics: Creep, Nuclear reactor coolants, Pipes, Fatigue, Cycles, Damage, Stress, Computational methods, Design, Design methodology
Proceedings Papers

Upgrade and Shakedown Test of a High Temperature Fluoride Salt Test Loop

Xiangbo Kong, Yuan Fu, Jianyu Zhang, Huiju Lu, Naxiu Wang
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, V001T13A004, July 22–26, 2018
Paper No: ICONE26-81222
https://doi.org/10.1115/ICONE26-81222
View Paper titled, Upgrade and Shakedown Test of a High Temperature Fluoride Salt Test Loop
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Topics: High temperature, Storage tanks, Flow (Dynamics), Heat exchangers, Pipes, Pumps, Temperature, Alloys, Centrifugal pumps, Convection
Proceedings Papers

Stress Analysis and Optimum Design of the Heat Transport System at Molten Salt Reactor

Xiaochun Zhang, Xiao Wang, Wei Gong, Yuan Fu
Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A019, July 19–23, 2015
Paper No: PVP2015-45519
https://doi.org/10.1115/PVP2015-45519
View Paper titled, Stress Analysis and Optimum Design of the Heat Transport System at Molten Salt Reactor
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Topics: Design, Heat, Molten salt reactors, Stress analysis (Engineering), Pipes, Flexible systems, Heat exchangers, High temperature, Pipelines, Pumps