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Proceedings Papers

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022
Paper No: ICONE29-92520
https://doi.org/10.1115/ICONE29-92520
View Paper titled, Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes
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Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors
Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022
Paper No: ICONE29-92872
https://doi.org/10.1115/ICONE29-92872
View Paper titled, Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor
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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)
Proceedings Papers

Initial Wire-Wrapped Angle Optimization Analysis of a Liquid Lead-Bismuth Cooled Fuel Assembly Based on OpenFOAM

Jie Wu, Jiejin Cai
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A077, August 8–12, 2022
Paper No: ICONE29-92097
https://doi.org/10.1115/ICONE29-92097
View Paper titled, Initial Wire-Wrapped Angle Optimization Analysis of a Liquid Lead-Bismuth Cooled Fuel Assembly Based on OpenFOAM
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Topics: Fast neutron reactors, Fuels, Manufacturing, Optimization, Wire
Proceedings Papers

Analysis on the Effects of Thermal Migration Phenomena to the Fuel Performance in the Fast Reactor

Guangliang Yang, Weixiang Wang, Tao Ding, Hongli Chen
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A029, August 8–12, 2022
Paper No: ICONE29-90561
https://doi.org/10.1115/ICONE29-90561
View Paper titled, Analysis on the Effects of Thermal Migration Phenomena to the Fuel Performance in the Fast Reactor
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Topics: Fast neutron reactors, Fuels
Proceedings Papers

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Yuchao Wang, Daogang Lu, Fei Zhao, Yu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A071, August 8–12, 2022
Paper No: ICONE29-92039
https://doi.org/10.1115/ICONE29-92039
View Paper titled, Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants
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Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels
Proceedings Papers

Development of the Digital Human-Computer Interaction Platform of the M 2 LFR-1000 Reactor Based on QT and ICoCo

Tianyi Liu, Tao Ding, Yanyi Shen, Hongli Chen
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A081, August 8–12, 2022
Paper No: ICONE29-92142
https://doi.org/10.1115/ICONE29-92142
View Paper titled, Development of the Digital Human-Computer Interaction Platform of the M 2 LFR-1000 Reactor Based on QT and ICoCo
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Topics: Circuits, Computers, Fast neutron reactors
Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022
Paper No: ICONE29-92103
https://doi.org/10.1115/ICONE29-92103
View Paper titled, Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation
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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results
Proceedings Papers

Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor

Jun Zhang, Daogang Lu, Jinsong Guo, Yuhao Zhang, Danting Sui
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A025, August 8–12, 2022
Paper No: ICONE29-92794
https://doi.org/10.1115/ICONE29-92794
View Paper titled, Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor
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Topics: Fast neutron reactors, Heat, Heat transfer, Sodium
Proceedings Papers

Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

Chong Qin, Kefan Zhang, Wenpei Feng, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A065, August 8–12, 2022
Paper No: ICONE29-92114
https://doi.org/10.1115/ICONE29-92114
View Paper titled, Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor
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Topics: Accidents, Boilers, Fast neutron reactors, Pressure, Rupture, Waves
Proceedings Papers

The Thermal-Hydraulic Analysis and Optimization of Annular Fuel for Lead-Cooled Fast Reactor

Zhang Kefan, Qin Chong, Dong Wenmeng, Pan Rui, Duan Wenshun, Chen Hongli
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A008, August 8–12, 2022
Paper No: ICONE29-92408
https://doi.org/10.1115/ICONE29-92408
View Paper titled, The Thermal-Hydraulic Analysis and Optimization of Annular Fuel for Lead-Cooled Fast Reactor
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Topics: Fast neutron reactors, Fuels, Optimization
Proceedings Papers

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Jinsong Guo, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, Yuhao Zhang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A003, August 8–12, 2022
Paper No: ICONE29-92364
https://doi.org/10.1115/ICONE29-92364
View Paper titled, Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core
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Topics: Computer simulation, Heat, Modeling, Flow (Dynamics), Wire, Fuel rods, Porous materials, Safety, Sodium fast reactors, Dynamics (Mechanics)
Proceedings Papers

Three-Dimensional Numerical Simulation of the Release and Migration Behavior of Fission Gas Bubbles in Advanced Reactor Pool Under Serious Accident

Zijun Mai, Zichen Zhao, Hui Cheng, Songbai Cheng
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A010, August 8–12, 2022
Paper No: ICONE29-91240
https://doi.org/10.1115/ICONE29-91240
View Paper titled, Three-Dimensional Numerical Simulation of the Release and Migration Behavior of Fission Gas Bubbles in Advanced Reactor Pool Under Serious Accident
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Topics: Accidents, Bubbles, Computer simulation, Nuclear fission, Engineering simulation, Simulation, Water, Bifurcation, Design, Eutectic alloys
Proceedings Papers

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Xinyue Luo, Daogang Lu, Jiaqi Feng, Yuhao Zhang
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A040, August 8–12, 2022
Paper No: ICONE29-92323
https://doi.org/10.1115/ICONE29-92323
View Paper titled, Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor
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Topics: Heat transfer, Radiation (Physics), Sodium fast reactors, Cavities, Fast neutron reactors, Temperature, Vessels, Computational fluid dynamics, Construction, Containers
Proceedings Papers

Numerical Simulation of Annular Dispersed Flow in Simplified Subchannel of Light Water Cooled Fast Reactor RBWR

Hiroyuki Yoshida, Horiguchi Naoki, Ayako Ono, Hajime Furuichi, Kenichi Katono
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A016, August 8–12, 2022
Paper No: ICONE29-91630
https://doi.org/10.1115/ICONE29-91630
View Paper titled, Numerical Simulation of Annular Dispersed Flow in Simplified Subchannel of Light Water Cooled Fast Reactor RBWR
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Topics: Computer simulation, Fast neutron reactors, Flow (Dynamics), Water
Proceedings Papers

Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor

Yutai Cai, Wenzhong Zhou, Long Gu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A041, August 8–12, 2022
Paper No: ICONE29-91817
https://doi.org/10.1115/ICONE29-91817
View Paper titled, Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor
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Topics: Fast neutron reactors, Fuels, Modeling, Thermomechanics, Uranium
Proceedings Papers

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022
Paper No: ICONE29-90146
https://doi.org/10.1115/ICONE29-90146
View Paper titled, Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)
Proceedings Papers

Application Research on Human Reliability Analysis Method of Class C Human Action of China Fast Reactor

Jingjuan Niu
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A032, August 8–12, 2022
Paper No: ICONE29-93025
https://doi.org/10.1115/ICONE29-93025
View Paper titled, Application Research on Human Reliability Analysis Method of Class C Human Action of China Fast Reactor
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Topics: China, Fast neutron reactors, Human reliability analysis
Proceedings Papers

Application Research on Human Reliability Analysis Method of Class A Human Action of China Fast Reactor

Jingjuan Niu
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A036, August 8–12, 2022
Paper No: ICONE29-93831
https://doi.org/10.1115/ICONE29-93831
View Paper titled, Application Research on Human Reliability Analysis Method of Class A Human Action of China Fast Reactor
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Topics: China, Fast neutron reactors, Human reliability analysis
Proceedings Papers

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022
Paper No: ICONE29-91821
https://doi.org/10.1115/ICONE29-91821
View Paper titled, Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions
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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting
Proceedings Papers

Comprehensive Comparison and Analysis for Fast Reactors

Zheng Yan, Weiguang Zhao, Xiaxin Cao, Changqi Yan
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A006, August 8–12, 2022
Paper No: ICONE29-90528
https://doi.org/10.1115/ICONE29-90528
View Paper titled, Comprehensive Comparison and Analysis for Fast Reactors
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Topics: Fast neutron reactors, Fuels