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Proceedings Papers

Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor

Yanzhu Chen, Zhichao Yang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A009, August 4–6, 2021
Paper No: ICONE28-65152
DOI: https://doi.org/10.1115/ICONE28-65152
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Topics: Fire, Ignition, Probability, Safety, Design, Evaluation methods, Innovation, Sensitivity analysis
Proceedings Papers

PSA Analysis of Switch Port Disabled on DCS Layer 1

Yang Luo, Deyi Liu, Shengjia Zou, Yong Cao
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A008, August 4–6, 2021
Paper No: ICONE28-64597
DOI: https://doi.org/10.1115/ICONE28-64597
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Topics: Switches, Failure, Control systems, Gates (Closures), Nuclear power stations, Radioactive substances, Reactor protection systems, Risk, Safety
Proceedings Papers

Periodic Test Period Extension for Partial Closing of Main Steam Isolation Valve

Deyi Liu, Yong Cao, Ming Zhao, Zilong Wang, Yang Luo, Shengjia Zou, Mengying Hu, Jie Xu, Li Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A003, August 4–6, 2021
Paper No: ICONE28-64413
DOI: https://doi.org/10.1115/ICONE28-64413
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Topics: Risk, Steam, Valves
Proceedings Papers

Application of Probabilistic Safety Analysis for Nuclear Power Plant Overhaul Risk Assessment

Deyi Liu, Yong Cao, Ming Zhao, Yang Luo, Shengjia Zou, Mengying Hu, Jie Xu, Li Wang, Ling Zhao
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A002, August 4–6, 2021
Paper No: ICONE28-64332
DOI: https://doi.org/10.1115/ICONE28-64332
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Topics: Nuclear power stations, Probabilistic safety assessment, Risk assessment, Risk, Safety, China, Damage, Decision making, Design, Fuels
Proceedings Papers

Probabilistic Safety Assessment on Unavailability of Auxiliary External Power Supply in Fangjiashan Nuclear Power Plant

Shengjia Zou, Ming Zhao, Deyi Liu, Naiyuan Zhang, Yang Luo, Li Wang, Jianguo Zhang, Honghao Chen
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A007, August 4–6, 2021
Paper No: ICONE28-64590
DOI: https://doi.org/10.1115/ICONE28-64590
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Topics: Nuclear power stations, Probabilistic safety assessment, Risk monitoring
Proceedings Papers

Configuration Risk Management Support for the Maintenance Rules at Qinshan NPP1

Li Wang, Zilong Wang, Deyi Liu, Jie Xu, Jianzhang Zhou, Shengjia Zou
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A006, August 4–6, 2021
Paper No: ICONE28-64543
DOI: https://doi.org/10.1115/ICONE28-64543
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Topics: Maintenance, Risk assessment, Risk management, Safety
Proceedings Papers

Study on the Off-Site Consequence Evaluation of NPP Severe Accident Based on JRODOS Platform

Xuan Wang, Li Guo, Xiujing Lin, Xiang Pu, Fenglei Du, Xiaodong Huang, Xiaowei Xiong, Bo Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A011, August 4–6, 2021
Paper No: ICONE28-66056
DOI: https://doi.org/10.1115/ICONE28-66056
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Topics: Accidents, Nuclear power stations
Proceedings Papers

Chinese Public and Nuclear Experts May Have Different Perceptions Of Severe Nuclear Accidents

Hsingtzu Wu, Leyao Huang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A010, August 4–6, 2021
Paper No: ICONE28-65349
DOI: https://doi.org/10.1115/ICONE28-65349
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Topics: Accidents
Proceedings Papers

Study of Recent Sodium Pool Fire Model Improvements for MELCOR Code

Mitsuhiro Aoyagi, David L. Y. Louie, Akihiro Uchibori, Takashi Takata, David Luxat
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A005, August 4–6, 2021
Paper No: ICONE28-64509
DOI: https://doi.org/10.1115/ICONE28-64509
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Topics: Fire, Liquid pool fires, Sodium, Sodium fast reactors
Proceedings Papers

The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant

Zilong Wang, Deyi Liu, Ming Zhao, Li Wang, Jie Xu
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A004, August 4–6, 2021
Paper No: ICONE28-64423
DOI: https://doi.org/10.1115/ICONE28-64423
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Topics: Design, Heat shielding, Nuclear power stations, Nuclear reactor coolants, Pumps, Safety
Proceedings Papers

Level 2 Probability Safety Assessment for External Events: Approach and Application for NPPs in China

Yu Liu, Cong Wang, Jing Liu, Heng Gao
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A001, August 4–6, 2021
Paper No: ICONE28-64329
DOI: https://doi.org/10.1115/ICONE28-64329
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Topics: China, Nuclear power stations, Probability, Safety, Computer software, Fukushima nuclear disaster, Japan, 2011, Pressurized water reactors, Radioactive substances, Risk, Tsunamis