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Proceedings Papers

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

Simin Luo, Peng Chen, Yapei Zhang, Dekui Zhan, Guanghui Su
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A008, August 8–12, 2022
Paper No: ICONE29-89069
https://doi.org/10.1115/ICONE29-89069
View Paper titled, Heat Transfer Characteristics of Two-Layer Corium Pools Under Rolling Conditions
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Topics: Heat transfer
Proceedings Papers

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

Zhichun Xu, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A026, August 4–5, 2020
Paper No: ICONE2020-16388
https://doi.org/10.1115/ICONE2020-16388
View Paper titled, Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI)
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Topics: Ablation (Vaporization technology), Computer simulation, Concretes, Cooling, Light water reactors, Reactor vessels, Accidents, Cavities, Containment, Flow (Dynamics)
Proceedings Papers

Research on Natural Convection of Two-Layer Corium Pools

Simin Luo, Hongping Sun, Yapei Zhang, Junmei Wu, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A005, August 4–5, 2020
Paper No: ICONE2020-16083
https://doi.org/10.1115/ICONE2020-16083
View Paper titled, Research on Natural Convection of Two-Layer Corium Pools
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Topics: Natural convection
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
https://doi.org/10.1115/ICONE26-81367
View Paper titled, COPRA Experiments on Melt Pool Behavior With Eutectic NaNO 3 -KNO 3 Simulant
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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
https://doi.org/10.1115/ICONE26-81630
View Paper titled, Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor
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Topics: Heat, Sodium fast reactors, Accidents, Design, China, Circuits, Errors, Fast neutron reactors, Flow (Dynamics), Generation IV reactors
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
https://doi.org/10.1115/ICONE26-81994
View Paper titled, Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition
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Topics: Flow (Dynamics), Accidents, China, Computational fluid dynamics, Construction, Heat transfer, Heating, Military systems, Natural convection, Nuclear reactors
Proceedings Papers

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

Liang Hu, Kui Ge, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A024, July 22–26, 2018
Paper No: ICONE26-81400
https://doi.org/10.1115/ICONE26-81400
View Paper titled, Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium
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Topics: Sodium, Copper, Pressure, Sodium fast reactors, Accidents, Boiling, Ceramics, Compacting, Coolants, Cooling
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
https://doi.org/10.1115/ICONE26-82267
View Paper titled, Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors
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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels
Proceedings Papers

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

Qiqi Yan, Simin Luo, Yapei Zhang, Limin Liu, Guanghui Su, Suizheng Qiu
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
https://doi.org/10.1115/ICONE26-81880
View Paper titled, Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions
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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 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
https://doi.org/10.1115/ICONE24-60857
View Paper titled, Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021002.
Paper No: NERS-15-1009
https://doi.org/10.1115/1.4031842
Published Online: February 29, 2016
View Article titled, The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA
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Topics: Accidents, Flow (Dynamics), Temperature, Vessels, Melting, Hydrogen
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
https://doi.org/10.1115/ICONE22-30535
View Paper titled, MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident
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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
https://doi.org/10.1115/ICONE22-31066
View Paper titled, Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR
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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
https://doi.org/10.1115/ICONE22-30515
View Paper titled, Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool
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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

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
https://doi.org/10.1115/ICONE22-30282
View Paper titled, The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase
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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
https://doi.org/10.1115/ICONE22-30283
View Paper titled, Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood
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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
https://doi.org/10.1115/ICONE22-30475
View Paper titled, Comparison of CORA and MELCOR Core Degradation Simulation and MELCOR Oxidation Model
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Topics: Oxidation, Simulation, Accidents, Hydrogen, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Steam, Zirconium
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
https://doi.org/10.1115/ICONE18-29008
View Paper titled, A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident
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Topics: Accidents, Accident management, Cavities, Floods, Reactor vessels, Vessels, Cooling, Light water reactors, Modeling, Nuclear power stations