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Proceedings Papers

Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method

Zehua Ma, Ren Liang, Zhikang Lin, Yong Ouyang, Xianghui Lu, Guanghui Su
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A029, August 8–12, 2022
Paper No: ICONE29-91377
DOI: https://doi.org/10.1115/ICONE29-91377
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Topics: Accidents, Computer simulation, Coolants, Discrete element methods, Fuels
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
DOI: https://doi.org/10.1115/ICONE29-89069
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Topics: Heat transfer
Proceedings Papers

Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling

Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A044, August 8–12, 2022
Paper No: ICONE29-91437
DOI: https://doi.org/10.1115/ICONE29-91437
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Topics: Fuels, Heat transfer, Modeling, Physics, Process control, Computational fluid dynamics, Nuclear reactors, Simulation, Convection, Finite element analysis
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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research Papers
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
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, V004T10A016, June 26–30, 2016
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)