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Proceedings Papers

Flux Rate Calculation and Analysis of the Integrated Small Pressurized Water Reactor Based on Monte Carlo Method

Wen Yang, Fei Chao, Yun Tai, Longze Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A011, August 4–6, 2021
Paper No: ICONE28-64448
DOI: https://doi.org/10.1115/ICONE28-64448
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Topics: Monte Carlo methods, Pressurized water reactors
Proceedings Papers

Application of High Accuracy Numerical Methods for the Natural Circulation Problem

Fei Chao, Longze Li, Wen Yang, Jinrong Qiu, Yun Tai, Jianqiang Shan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A014, August 4–6, 2021
Paper No: ICONE28-64367
DOI: https://doi.org/10.1115/ICONE28-64367
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Topics: Accuracy and precision, Algorithms, Density, Diffusion (Physics), Errors, Fluids, Nuclear power, Numerical analysis, Pressure, Safety
Proceedings Papers

Eigenvalue Analysis of Well-Posedness of Two-Fluid Single Pressure Model With Virtual Mass Force and Interfacial Pressure

Fei Chao, Wen Yang, Longze Li, Jinrong Qiu, Jianqiang Shan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A016, August 4–6, 2021
Paper No: ICONE28-64434
DOI: https://doi.org/10.1115/ICONE28-64434
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Topics: Eigenvalues, Fluids, Pressure
Proceedings Papers

Severe Accident Analysis of a Floating Nuclear Power Plant After Station Black Out Accident

Longze Li, Fei Chao, Chuan He, Yun Tai, Jinrong Qiu, Shiwei Yao, Wen Yang, Jue Wang, Xiaofan Hou
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, V003T12A029, August 4–6, 2021
Paper No: ICONE28-64611
DOI: https://doi.org/10.1115/ICONE28-64611
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Topics: Accidents, Containment, Nuclear power stations
Proceedings Papers

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A002, July 22–26, 2018
Paper No: ICONE26-81159
DOI: https://doi.org/10.1115/ICONE26-81159
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Topics: Nuclear power stations, Ocean engineering, Seawater, Boilers, Design, Dimensions, Hazards, Heat, Accidents, Computers
Proceedings Papers

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Longze Li, Jue Wang, Yapei Zhang, G. H. Su
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A047, July 22–26, 2018
Paper No: ICONE26-82267
DOI: https://doi.org/10.1115/ICONE26-82267
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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels
Proceedings Papers

MAAP5 Simulation of the PWR Severe Accident Induced by Pressurizer Safety Valve Stuck-Open Accident

Longze Li, Yapei Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A001, July 7–11, 2014
Paper No: ICONE22-30535
DOI: https://doi.org/10.1115/ICONE22-30535
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Topics: Accidents, Pressurized water reactors, Safety, Simulation, Valves, Pressure, Coolants, Accident management, Boilers, Computers
Proceedings Papers

The Severe Accident Analysis of CPR1000 Based on MELCOR Code

Longze Li, Mingjun Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A011, July 29–August 2, 2013
Paper No: ICONE21-15152
DOI: https://doi.org/10.1115/ICONE21-15152
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Topics: Accidents, Feedwater, Leakage, Failure, Delays, Pressure, Accident management, Nuclear power stations, Power stations, Pressure vessels