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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

DOI: https://doi.org/10.1115/ICONE29-90528

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Topics: Fast neutron reactors, Fuels

Proceedings Papers

The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method

Weiquan Yuan, Zhao Chen, Kangli Shi, Chang Su, Jinghua Tang, Dawei Cui, Chengjie Duan

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A024, August 8–12, 2022

Paper No: ICONE29-92077

DOI: https://doi.org/10.1115/ICONE29-92077

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Topics: Fast neutron reactors

Proceedings Papers

Pre-Conceptual Core Design of a Micro-LBE-Cooled Fast Reactor

Eing Yee Yeoh, Menglu Liu, Zhen Luo, Xiaosong Chen, Linsen Li, Gang Zheng

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A008, August 8–12, 2022

Paper No: ICONE29-90903

DOI: https://doi.org/10.1115/ICONE29-90903

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Topics: Design, Fast neutron reactors

Proceedings Papers

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A019, August 8–12, 2022

Paper No: ICONE29-91812

DOI: https://doi.org/10.1115/ICONE29-91812

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Topics: Accidents, Fast neutron reactors, Sodium fast reactors

Proceedings Papers

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Donghao Li, Daogang Lu, Yuxuan Zhu, Yu Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A032, August 8–12, 2022

Paper No: ICONE29-92137

DOI: https://doi.org/10.1115/ICONE29-92137

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Topics: Fluid structure interaction, Pipes, Shells, Vibration, Finite element model, Fluids, Water, Computer software, Fast neutron reactors, Heat shielding

Proceedings Papers

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

Yali Qiu, Qin Zeng, Hongli Chen

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A031, August 8–12, 2022

Paper No: ICONE29-92104

DOI: https://doi.org/10.1115/ICONE29-92104

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Topics: Fast neutron reactors, Radioisotopes, Coolants, Volatility, Accidents, Circuits, Computational fluid dynamics, Containment, Hazards, Irradiation (Radiation exposure)

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

DOI: https://doi.org/10.1115/ICONE29-92103

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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

DOI: https://doi.org/10.1115/ICONE29-92794

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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

DOI: https://doi.org/10.1115/ICONE29-92114

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Topics: Accidents, Boilers, Fast neutron reactors, Pressure, Rupture, Waves

Proceedings Papers

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Chaofan Zhang, Daogang Lu, Yu Liu, Haotian Qiu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A036, August 8–12, 2022

Paper No: ICONE29-92274

DOI: https://doi.org/10.1115/ICONE29-92274

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Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)

Proceedings Papers

Research of Supercritical Carbon Dioxide Thermal Power System Based on Lead-Cooled Fast Reactor

Zhihui Li, Chunyuan Liu, Mian Xing, Gang Zheng, Yu Wang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A030, August 8–12, 2022

Paper No: ICONE29-90432

DOI: https://doi.org/10.1115/ICONE29-90432

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Topics: Brayton cycle, Compression, Fast neutron reactors, Supercritical carbon dioxide, Thermal energy

Proceedings Papers

Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100

Wenshun Duan, Kefan Zhang, Hongli Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A050, August 8–12, 2022

Paper No: ICONE29-91709

DOI: https://doi.org/10.1115/ICONE29-91709

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Topics: Fast neutron reactors, Fluids, Reactor vessels

Proceedings Papers

Thermal Fatigue Analysis of Thermocouple Protector at the Core Outlet of Fast Reactor Under Thermal Striping

Yu Si, Zaojing Chen, Haoliang Zhong, Xiaofei Chen, Yading Zhang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A076, August 8–12, 2022

Paper No: ICONE29-92271

DOI: https://doi.org/10.1115/ICONE29-92271

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Topics: Fast neutron reactors, Fatigue, Fatigue analysis, Thermocouples

Proceedings Papers

Thermal-Hydraulic Safety Analysis of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Core Based on Porous Medium Approach

Wenpei Feng, Guangliang Yang, Kefan Zhang, Chong Qin, Xiao Luo, Tao Ding, Hongli Chen

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A005, August 8–12, 2022

Paper No: ICONE29-92379

DOI: https://doi.org/10.1115/ICONE29-92379

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Topics: Fast neutron reactors, Porous materials, Safety

Proceedings Papers

Experimental Study on Natural Circulation in Pool Type Fast Reactor Using a Water Model

Daoxi Cheng, Xuefeng Zhang, Kaiwen Du, Xiaoguang Qi, Weiming Zhai, Song Yu, Ping Zhou, Baohua Chai

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A057, August 8–12, 2022

Paper No: ICONE29-91869

DOI: https://doi.org/10.1115/ICONE29-91869

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Topics: Fast neutron reactors, Water

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

DOI: https://doi.org/10.1115/ICONE29-92520

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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

DOI: https://doi.org/10.1115/ICONE29-92872

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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

DOI: https://doi.org/10.1115/ICONE29-92097

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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

DOI: https://doi.org/10.1115/ICONE29-90561

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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

DOI: https://doi.org/10.1115/ICONE29-92039

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Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels

2 3 4 5

NARROW

Comprehensive Comparison and Analysis for Fast Reactors

The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method

Pre-Conceptual Core Design of a Micro-LBE-Cooled Fast Reactor

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

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

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

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

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Research of Supercritical Carbon Dioxide Thermal Power System Based on Lead-Cooled Fast Reactor

Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100

Thermal Fatigue Analysis of Thermocouple Protector at the Core Outlet of Fast Reactor Under Thermal Striping

Thermal-Hydraulic Safety Analysis of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Core Based on Porous Medium Approach

Experimental Study on Natural Circulation in Pool Type Fast Reactor Using a Water Model

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

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

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

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

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

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