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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

DOI: https://doi.org/10.1115/ICONE2020-16083

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Topics: Natural convection

Proceedings Papers

Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor

Jian Song, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A016, July 22–26, 2018

Paper No: ICONE26-81248

DOI: https://doi.org/10.1115/ICONE26-81248

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Topics: China, Sodium fast reactors, Flow (Dynamics), Pumps, Reliability, Safety, Accidents, Coolants, Design, Engineering prototypes

Proceedings Papers

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A035, July 22–26, 2018

Paper No: ICONE26-81551

DOI: https://doi.org/10.1115/ICONE26-81551

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Topics: Sodium fast reactors, Thermal stratification, Turbulence, Sodium, Momentum, Breeder reactors, Buoyancy, Convection, Deformation, Diffusion (Physics)

Proceedings Papers

Optimization of Moving Particle Semi-Implicit (MPS) Method and Studying of Flow Instability

Kailun Guo, Ronghua Chen, Suizheng Qiu, Wenxi Tian, Guanghui Su, Junmei Wu

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A031, July 22–26, 2018

Paper No: ICONE26-81948

DOI: https://doi.org/10.1115/ICONE26-81948

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Topics: Flow instability, Optimization, Particulate matter, Fluids, Density, Multiphase flow, Flow (Dynamics), Accidents, Rayleigh-Taylor instability, Turbulence

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

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

Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions

Hao Qin, Chenglong Wang, Suizheng Qiu, Dalin Zhang, Wenxi Tian, Guanghui Su

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A023, July 22–26, 2018

Paper No: ICONE26-81728

DOI: https://doi.org/10.1115/ICONE26-81728

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Topics: Molten salt reactors, Transients (Dynamics), Absorption, Accidents, Corrosion, Dynamic response, Graphite, High temperature, Steady state

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

Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.

Paper No: NERS-17-1163

DOI: https://doi.org/10.1115/1.4040887

Published Online: September 10, 2018

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Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations

Proceedings Papers

Accident Tolerance Cladding Thermal Hydraulic Simulation and Oxidation Kinetic Sensitivity Analysis

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A036, July 2–6, 2017

Paper No: ICONE25-66523

DOI: https://doi.org/10.1115/ICONE25-66523

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Topics: Accidents, Cladding systems (Building), Oxidation, Sensitivity analysis, Simulation, Fuels, Alloys, Design, Fukushima nuclear disaster, Japan, 2011, Hydrogen

Proceedings Papers

Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop

Leitai Shi, Guanghui Su, Tan Bing, Ronghua Chen, Wenxi Tian, Suizheng Qiu, Junmei Wu

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A017, July 2–6, 2017

Paper No: ICONE25-66261

DOI: https://doi.org/10.1115/ICONE25-66261

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Topics: Cooling, Flow (Dynamics), Heat sinks, Heat transfer, Heating, Natural convection, Pumps, Temperature, Test facilities, Thermal expansion

Proceedings Papers

Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line

Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A063, July 2–6, 2017

Paper No: ICONE25-66893

DOI: https://doi.org/10.1115/ICONE25-66893

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Topics: Flow (Dynamics), Friction, Steam, Surges, Water, Pressure drop, Pressure, Accidents, Coolants, Manufacturing

Proceedings Papers

Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors

Jian Song, Limin Liu, Simiao Tang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A002, July 2–6, 2017

Paper No: ICONE25-66009

DOI: https://doi.org/10.1115/ICONE25-66009

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Topics: Liquid metals, Safety, Sodium fast reactors, Fluids, Sodium, Temperature, Vapors, Water, Boilers, Boiling

Journal Articles

Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop

Chaofei Jiang, Wenxi Tian, Suizheng Qiu, Guanghui Su

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011002.

Paper No: NERS-15-1106

DOI: https://doi.org/10.1115/1.4035046

Published Online: December 20, 2016

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Topics: Accidents, Coolants, Flow (Dynamics), Fuels, Heat, Pressure, Safety, Supercritical water reactors, Transients (Dynamics), Water

Proceedings Papers

Numerical Analysis of the Corium Behavior Within the Fuel Support Piece by MPS

Ronghua Chen, Lie Chen, Wenxi Tian, Guanghui Su, Suizheng Qiu

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A086, June 26–30, 2016

Paper No: ICONE24-61072

DOI: https://doi.org/10.1115/ICONE24-61072

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Topics: Fuels, Numerical analysis, Flow (Dynamics), Boiling water reactors, Accidents, Particulate matter, Ablation (Vaporization technology), Freezing, Simulation, Solidification

Proceedings Papers

Validation of the ATHROC Code With NUPEC Tests

Yongzheng Chen, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A025, June 26–30, 2016

Paper No: ICONE24-60432

DOI: https://doi.org/10.1115/ICONE24-60432

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Topics: China, Containment, Cooling, Design, Domes (Structural elements), Errors, Flow (Dynamics), Heat, Helium, Nuclear 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

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

Proceedings Papers

Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions

Rong Cai, Siyang Huang, Kai Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su

Paper No: ICONE24-60394

DOI: https://doi.org/10.1115/ICONE24-60394

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Topics: Computational fluid dynamics, Coolants, Engineering simulation, Flow (Dynamics), Simulation, Steady state, Transients (Dynamics)

Proceedings Papers

Start-Up Simulation of the Improved TOPAZ-II Space Power System

Wenwen Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A032, June 26–30, 2016

Paper No: ICONE24-60829

DOI: https://doi.org/10.1115/ICONE24-60829

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Topics: Power systems (Machinery), Simulation, Heat pipes, Coolants, Ducts, Neutrons, Physics, Pipes, Pumps, Secondary cells

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

Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus

Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, Guanghui Su

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A025, July 7–11, 2014

Paper No: ICONE22-30244

DOI: https://doi.org/10.1115/ICONE22-30244

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Topics: Annulus, Sodium, Flow (Dynamics), Fluids, Heat flux, Temperature, Friction, Heat transfer coefficients, Laminar flow, Turbulence

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Journal citation

NARROW

Research on Natural Convection of Two-Layer Corium Pools

Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Optimization of Moving Particle Semi-Implicit (MPS) Method and Studying of Flow Instability

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

Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions

Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

Accident Tolerance Cladding Thermal Hydraulic Simulation and Oxidation Kinetic Sensitivity Analysis

Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop

Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line

Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors

Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop

Numerical Analysis of the Corium Behavior Within the Fuel Support Piece by MPS

Validation of the ATHROC Code With NUPEC Tests

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

Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions

Start-Up Simulation of the Improved TOPAZ-II Space Power System

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

Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus

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