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Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022

Paper No: ICONE29-93244

DOI: https://doi.org/10.1115/ICONE29-93244

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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)

Proceedings Papers

Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant

Lingmei Xiao, Bing Zhang, Ming Wang, Zhiwen Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A036, August 8–12, 2022

Paper No: ICONE29-92450

DOI: https://doi.org/10.1115/ICONE29-92450

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Topics: Floods, Nuclear power stations, Reactor vessels, Risk, Vessels

Proceedings Papers

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

Wenjing Li, Yu Liu, Gaopeng Wang, Xinli Yu

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A005, August 8–12, 2022

Paper No: ICONE29-89268

DOI: https://doi.org/10.1115/ICONE29-89268

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Topics: Nuclear design, Optimization, Risk, Design, Nuclear power stations, Accidents, Cavities, Vessels, China, Damage

Proceedings Papers

PSA Application in UK HPR1000 Numerical Targets Evaluation

Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A038, August 8–12, 2022

Paper No: ICONE29-92462

DOI: https://doi.org/10.1115/ICONE29-92462

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Topics: Damage, Design, Dimensions, Floods, Nuclear power stations, Plant design, Radiation (Physics), Reactor vessels, Risk, Safety

Proceedings Papers

Dynamic Modeling and Simulation of MHTGR Plant Start-Up and Shutdown System

Bowen Li, Zhe Dong, Junyi Li

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A019, August 8–12, 2022

Paper No: ICONE29-90263

DOI: https://doi.org/10.1115/ICONE29-90263

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Topics: Dynamic modeling, Simulation, Very high temperature reactors, Modeling, Nuclear power stations, Steam, Water, Boilers, Coal, Computer simulation

Proceedings Papers

Experimental Investigation on Natural Circulation Characteristics of Core Make-Up Tank Under Rolling Conditions

Shuguang Wang, Jinlei Zhang, Ya'ou Shen, Xiaobo Liu, Shuhua Ding, Yusheng Liu, Dongyang Li, Jilin Tang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A087, August 8–12, 2022

Paper No: ICONE29-92254

DOI: https://doi.org/10.1115/ICONE29-92254

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Topics: Emergencies, Flow (Dynamics), Nuclear engineering, Nuclear power stations, Safety, Temperature, Temperature gradient, Thermal stratification, Thermocouples, Vessels

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

Proceedings Papers

Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

Hua Zheng, Shuhong Wei

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A037, August 8–12, 2022

Paper No: ICONE29-92239

DOI: https://doi.org/10.1115/ICONE29-92239

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Topics: Design, Feedback, Vessels, Nuclear power stations, Safety, Accident management, Accidents, Construction, Control panels, Control rooms

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

DOI: https://doi.org/10.1115/ICONE29-91821

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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting

Proceedings Papers

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Hidemasa Yamano, Shigenobu Kubo, Taro Kan, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022

Paper No: ICONE29-91505

DOI: https://doi.org/10.1115/ICONE29-91505

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Topics: Accidents, Sodium fast reactors, Design, Coolants, Fuels, Probability, Sodium, Vessels

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

DOI: https://doi.org/10.1115/ICONE29-92323

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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

The Optimization Design of Direct Vessel Injection Diversion Structure

Jianfei Hou, Qingli Wang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A009, August 8–12, 2022

Paper No: ICONE29-91230

DOI: https://doi.org/10.1115/ICONE29-91230

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Topics: Computational fluid dynamics, Design, Diversion structures (Hydraulic engineering), Leakage flows, Optimization, Vessels

Proceedings Papers

Extension of the IVR Analysis Module in Modeling the Ex-Vessel Water Cooling

Peng Yu, Yuer Zhao, Chen Wang, Xiaoming Yang, Rubing Ma, Yidan Yuan

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A013, August 8–12, 2022

Paper No: ICONE29-91888

DOI: https://doi.org/10.1115/ICONE29-91888

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Topics: Boiling, Cooling, Heat transfer, Modeling, Vessels, Water

Proceedings Papers

A Numerical Study of the Spray Cooling Effect on Improving the IVR Safety Margin

Peng Yu, Ningxi Jia, Qiang Guo, Zhuo Liu, Yu Jin, Yidan Yuan

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A002, August 8–12, 2022

Paper No: ICONE29-89870

DOI: https://doi.org/10.1115/ICONE29-89870

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Topics: Accidents, Cooling, Heat transfer, Safety, Sprays, Vessels

Proceedings Papers

Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region

Xinhai Zhao, Peng Chen, Dongyu He, Ruhao Zhong

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A017, August 8–12, 2022

Paper No: ICONE29-92717

DOI: https://doi.org/10.1115/ICONE29-92717

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Topics: Accidents, Algorithms, Collapse, Dams, Flow (Dynamics), Fuel rods, Geometry, Heat transfer, Melting, Porous materials

Proceedings Papers

Feasibility Analysis and Demonstration of In-Vessel-Injection in the Early Stage of Severe Accident

Shaoxiong Xia, Dekui Zhan, Zijie Wu, Xinhai Zhao, Yiqun Yu

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A018, August 8–12, 2022

Paper No: ICONE29-92736

DOI: https://doi.org/10.1115/ICONE29-92736

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Topics: Accidents, Vessels

Proceedings Papers

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

Bo Lin, Xiangyu Yun, Junying Xu, Dongshan Wei, Huiyong Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A055, August 8–12, 2022

Paper No: ICONE29-93157

DOI: https://doi.org/10.1115/ICONE29-93157

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Topics: Boiling, Coating processes, Coatings, Concretes, Critical heat flux, Glass reinforced plastics, Water, Coolants, Accidents, Construction

Proceedings Papers

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Yu Tan, Xuejiao Shao, Enming Liang, Shuchun Zuo, Feng Lv, Thomas Metais, Han Liu

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A015, August 8–12, 2022

Paper No: ICONE29-93561

DOI: https://doi.org/10.1115/ICONE29-93561

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Topics: China, Vessels, Bullets, Computational methods, Computer software, Evaluation methods, Fatigue, Fatigue analysis, Geometry, Nozzles

Proceedings Papers

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

Xiao Ke

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022

Paper No: ICONE29-90343

DOI: https://doi.org/10.1115/ICONE29-90343

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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback

Proceedings Papers

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

Ping Song, Tangtao Feng, Dalin Zhang, Lie Chen, Shaodan Li, Yuansheng Lin, Suizheng Qiu

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A012, August 4–6, 2021

Paper No: ICONE28-64293

DOI: https://doi.org/10.1115/ICONE28-64293

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Topics: Cooling systems, Numerical analysis, Reactor vessels, Sodium fast reactors, Vessels

2 3 4 5

NARROW

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

PSA Application in UK HPR1000 Numerical Targets Evaluation

Dynamic Modeling and Simulation of MHTGR Plant Start-Up and Shutdown System

Experimental Investigation on Natural Circulation Characteristics of Core Make-Up Tank Under Rolling Conditions

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

Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

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

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

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

The Optimization Design of Direct Vessel Injection Diversion Structure

Extension of the IVR Analysis Module in Modeling the Ex-Vessel Water Cooling

A Numerical Study of the Spray Cooling Effect on Improving the IVR Safety Margin

Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region

Feasibility Analysis and Demonstration of In-Vessel-Injection in the Early Stage of Severe Accident

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

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