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Proceedings Papers

Calculation of Detector Response Rate Based on BEAVRS Benchmark Using PWR-Core Analysis Code CORAL

Wen Yang, Baolin Liu, Shiwei Yao, Fei Chao, Xing Li, Jinrong Qiu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A082, August 8–12, 2022
Paper No: ICONE29-93495
DOI: https://doi.org/10.1115/ICONE29-93495
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Topics: Pressurized water reactors, Sensors
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

Verification of PWR-Core Analysis Code CORAL Using VERA Core Physics Benchmark

Wen Yang, Fei Chao, Jinrong Qiu, Xing Li, Baolin Liu
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, V003T09A005, August 4–6, 2021
Paper No: ICONE28-64721
DOI: https://doi.org/10.1115/ICONE28-64721
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Topics: Physics, Pressurized water reactors
Proceedings Papers

Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem

Fei Chao, Jianqiang Shan, Junli Gou, Pan Wu, Li Ge
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A013, July 22–26, 2018
Paper No: ICONE26-81942
DOI: https://doi.org/10.1115/ICONE26-81942
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Topics: Fluids, Pressure, Water, Gravity (Force), Diffusion (Physics), Flow (Dynamics), Waves, Algorithms, Drag (Fluid dynamics), Pressure gradient