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Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A028, July 22–26, 2018

Paper No: ICONE26-81880

DOI: https://doi.org/10.1115/ICONE26-81880

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Topics: Accidents, Transients (Dynamics), Nuclear reactors, Oceans, Pressurized water reactors, Automobiles, Boats, Computer programming, Nuclear power stations, Ocean engineering

Proceedings Papers

Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition

Simin Luo, Xin'an Wang, Yapei Zhang, Dalin Zhang, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A066, July 22–26, 2018

Paper No: ICONE26-81994

DOI: https://doi.org/10.1115/ICONE26-81994

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Topics: Flow (Dynamics), Accidents, China, Computational fluid dynamics, Construction, Heat transfer, Heating, Military systems, Natural convection, Nuclear reactors

Proceedings Papers

COPRA Experiments on Melt Pool Behavior With Eutectic NaNO 3 -KNO 3 Simulant

Yukun Zhou, Yapei Zhang, Simin Luo, Zhichun Xu, Luteng Zhang, Suizheng Qiu, G. H. Su

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A032, July 22–26, 2018

Paper No: ICONE26-81367

DOI: https://doi.org/10.1115/ICONE26-81367

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Topics: Fluids, Heat flux, Heat transfer, Heating, Natural convection, Rayleigh number, Reactor vessels, Temperature

Proceedings Papers

Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor

Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G. H. Su

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A061, July 22–26, 2018

Paper No: ICONE26-81630

DOI: https://doi.org/10.1115/ICONE26-81630

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Topics: Heat, Sodium fast reactors, Accidents, Design, China, Circuits, Errors, Fast neutron reactors, Flow (Dynamics), Generation IV reactors

Proceedings Papers

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Longze Li, Jue Wang, Yapei Zhang, G. H. Su

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A047, July 22–26, 2018

Paper No: ICONE26-82267

DOI: https://doi.org/10.1115/ICONE26-82267

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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels

Proceedings Papers

Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method

Yapei Zhang, Luteng Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su

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, V004T10A024, June 26–30, 2016

Paper No: ICONE24-60857

DOI: https://doi.org/10.1115/ICONE24-60857

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Topics: Heat transfer, Rayleigh number, Accidents, Fluids, Geometry, Heat flux, Large eddy simulation, Natural convection, Pressurized water reactors, Reactor vessels

Journal Articles

The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

Jun Wang, Yuqiao Fan, Yapei Zhang, Xinghe Ni, Wenxi Tian, Michael L. Corradini, Guanghui Su, Suizheng Qiu

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021002.

Paper No: NERS-15-1009

DOI: https://doi.org/10.1115/1.4031842

Published Online: February 29, 2016

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Topics: Accidents, Flow (Dynamics), Temperature, Vessels, Melting, Hydrogen

Proceedings Papers

The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase

Shipeng Niu, Yapei Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A034, July 7–11, 2014

Paper No: ICONE22-30282

DOI: https://doi.org/10.1115/ICONE22-30282

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Topics: Coolants, Flow (Dynamics), Fuels, Heat transfer, Pressure, Safety, Subcooling, Thermohydrodynamics

Proceedings Papers

Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood

Tao Huang, Wenxi Tian, Yapei Zhang, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A035, July 7–11, 2014

Paper No: ICONE22-30283

DOI: https://doi.org/10.1115/ICONE22-30283

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Topics: Floods, Particulate matter, Quenching (Metalworking), Temperature, Coolants, Porosity, Flow (Dynamics), Cooling, Porous materials, Steam

Proceedings Papers

Comparison of CORA and MELCOR Core Degradation Simulation and MELCOR Oxidation Model

Jun Wang, Michael L. Corradini, Wen Fu, Troy Haskin, Wenxi Tian, Yapei Zhang, Guanghui Su, Suizheng Qiu

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A019, July 7–11, 2014

Paper No: ICONE22-30475

DOI: https://doi.org/10.1115/ICONE22-30475

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Topics: Oxidation, Simulation, Accidents, Hydrogen, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Steam, Zirconium

Proceedings Papers

MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident

Longze Li, Yapei Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A001, July 7–11, 2014

Paper No: ICONE22-30535

DOI: https://doi.org/10.1115/ICONE22-30535

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Topics: Accidents, Pressurized water reactors, Safety, Simulation, Valves, Pressure, Coolants, Accident management, Boilers, Computers

Proceedings Papers

Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR

Shasha Yin, Liang Gao, Wenxi Tian, Yapei Zhang, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A046, July 7–11, 2014

Paper No: ICONE22-31066

DOI: https://doi.org/10.1115/ICONE22-31066

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Topics: Accidents, Flow (Dynamics), Safety, Coolants, Transients (Dynamics), Heat, Steady state, Boilers, Feedwater, Pressurized water reactors

Proceedings Papers

Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool

Xiaoli Wu, Yapei Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A041, July 7–11, 2014

Paper No: ICONE22-30515

DOI: https://doi.org/10.1115/ICONE22-30515

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Topics: Accidents, Heat, Pressurized water reactors, Spent nuclear fuels, Water, Evaporation, Flow (Dynamics), Nuclear power stations, Cooling, Fuel rods

Proceedings Papers

A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident

Yapei Zhang, Suizheng Qiu, Guanghui Su, Wenxi Tian

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 1-14, May 17–21, 2010

Paper No: ICONE18-29008

DOI: https://doi.org/10.1115/ICONE18-29008

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Topics: Accidents, Accident management, Cavities, Floods, Reactor vessels, Vessels, Cooling, Light water reactors, Modeling, Nuclear power stations

Journal citation

NARROW

Heat Transfer Characteristics of Two-Layer Corium Pools Under Rolling Conditions

Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI)

Research on Natural Convection of Two-Layer Corium Pools

Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium

Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions

Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition

COPRA Experiments on Melt Pool Behavior With Eutectic NaNO 3 -KNO 3 Simulant

Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method

The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase

Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood

Comparison of CORA and MELCOR Core Degradation Simulation and MELCOR Oxidation Model

MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident

Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR

Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool

A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident

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