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Wenjun Hu
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Proceedings Papers

Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor

Yang Yu, Jun Yang, Jin Wang, Xiaokun Wang, Wenjun Hu, Donghui Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91857
https://doi.org/10.1115/ICONE29-91857
View Paper titled, Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor
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Topics: Heat transfer, Optimization, Scram, Sodium fast reactors, Stress
Proceedings Papers

A Combined Analytical, Experimental and Simulation Investigation on LBE Natural Circulation Flow and Heat Transmission

Yiquan Zhou, Bo Kuang, Xin Wang, Shuting Wang, Wenjun Hu, Lixia Ren
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93584
https://doi.org/10.1115/ICONE29-93584
View Paper titled, A Combined Analytical, Experimental and Simulation Investigation on LBE Natural Circulation Flow and Heat Transmission
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Topics: Flow (Dynamics), Heat transfer, Simulation
Proceedings Papers

Experimental Study on the Interaction of Molten Sn With Water

Longkun He, Pengfei Liu, Xisi Zhang, Wenjun Hu, Bo Kuang, Liangzhang Wei
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A038, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82204
https://doi.org/10.1115/ICONE26-82204
View Paper titled, Experimental Study on the Interaction of Molten Sn With Water
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Topics: Tin, Water, Explosions, Coolants, Water temperature, Pressure, Accidents, Containment, Fuels, Metals
Proceedings Papers

The Study About the Transient Characteristics of Metallic Fuel Sodium Cooled Fast Reactor in the Unprotected Loss of Flow Accident Based on the SAS4A Code

Pengrui Qiao, Wenjun Hu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A001, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66018
https://doi.org/10.1115/ICONE25-66018
View Paper titled, The Study About the Transient Characteristics of Metallic Fuel Sodium Cooled Fast Reactor in the Unprotected Loss of Flow Accident Based on the SAS4A Code
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Topics: Accidents, Flow (Dynamics), Fuels, Sodium fast reactors, Transients (Dynamics), Safety, Feedback
Proceedings Papers

The Research of SFR Aerosol Deposition Behavior in Ventilation Ducts

Lei Zhao, Lixia Ren, Wenjun Hu, Shirui Li
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A016, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66384
https://doi.org/10.1115/ICONE25-66384
View Paper titled, The Research of SFR Aerosol Deposition Behavior in Ventilation Ducts
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Topics: Aerosols, Ducts, Sodium fast reactors, Ventilation, Particulate matter, Agglomeration (Materials), Emergencies, Sodium, Turbulence, Channel flow
Proceedings Papers

Unprotected Loss of Flow Analysis of a Million Kilowatt Traveling Wave Reactor Core

Wenjun Hu, Pengrui Qiao
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A004, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66101
https://doi.org/10.1115/ICONE25-66101
View Paper titled, Unprotected Loss of Flow Analysis of a Million Kilowatt Traveling Wave Reactor Core
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Topics: Flow (Dynamics), Traveling waves, Fuels, Safety, Accidents, Design, Innovation, China, Cladding systems (Building), Combustion
Proceedings Papers

Safety Performance of a Large Scale Sodium Cooled Fast Reactor in Unprotected Transient Overpower Scenarios

Yuanyu Wu, Hong Yu, Lixia Ren, Wenjun Hu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A068, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16704
https://doi.org/10.1115/ICONE21-16704
View Paper titled, Safety Performance of a Large Scale Sodium Cooled Fast Reactor in Unprotected Transient Overpower Scenarios
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Topics: Safety, Sodium fast reactors, Transients (Dynamics), Design, China, Fast neutron reactors, Cladding systems (Building), Fuels, Simulation, Sodium
Proceedings Papers

A Study and Development of Primary Circuit Simulation Code for China Experimental Fast Reactor

Jin Wang, Donghui Zhang, Wenjun Hu, Lixia Ren
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A021, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15790
https://doi.org/10.1115/ICONE21-15790
View Paper titled, A Study and Development of Primary Circuit Simulation Code for China Experimental Fast Reactor
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Topics: China, Circuits, Fast neutron reactors, Simulation, Sodium, Cooling, Coolants, Economics , Electricity (Physics), Flow (Dynamics)
Proceedings Papers

Experimental Study on the Sodium Spray Fire

Haiou Du, Chen Liu, Rongdong Wang, Wenjun Hu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A047, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16237
https://doi.org/10.1115/ICONE21-16237
View Paper titled, Experimental Study on the Sodium Spray Fire
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Topics: Fire, Sodium, Sprays, Combustion, Temperature, Pressure, Accidents, Data acquisition systems, Design, Instrumentation
Proceedings Papers

The Investigation of Minor Losses in T-Pipe Flow

Dajie Sun, Donghui Zhang, Wenjun Hu, Lixia Ren
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A063, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16610
https://doi.org/10.1115/ICONE21-16610
View Paper titled, The Investigation of Minor Losses in T-Pipe Flow
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Topics: Flow (Dynamics), Pipes, Pressure drop, Pressure, Safety, Design, Fast neutron reactors, Fittings, Rods, Sodium
Proceedings Papers

A Study on the Influences of Reactivity Feedback Mechanisms in China Experimental Fast Reactor Unprotected Transients

Yuanyu Wu, Hong Yu, Lixia Ren, Wenjun Hu, Hongtao Qian
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A037, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16114
https://doi.org/10.1115/ICONE21-16114
View Paper titled, A Study on the Influences of Reactivity Feedback Mechanisms in China Experimental Fast Reactor Unprotected Transients
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Topics: China, Fast neutron reactors, Feedback, Transients (Dynamics), Accidents, Coolants, Flow (Dynamics), Fuels, Temperature, Design