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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

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

A Small PWR-Core Physical Calculation Based on PWR-Core Analysis Code CORAL

Wen Yang, Lun Zhou, Junrong Qiu, Yun Tai
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, V003T09A007, August 4–6, 2021
Paper No: ICONE28-64912
DOI: https://doi.org/10.1115/ICONE28-64912
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Topics: Pressurized water reactors
Proceedings Papers

Extension of Load Follow Operation of PWRs Without Boron Adjustment

Li Wang, Yang Liu, Yun Tai, Yawei Zhang, Zhenpeng Tang
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T13A009, July 29–August 2, 2013
Paper No: ICONE21-15479
DOI: https://doi.org/10.1115/ICONE21-15479
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Topics: Boron, Pressurized water reactors, Stress, Nuclear power, Simulation, Optimal control, Computation, Computers, Modeling, Power systems (Machinery)
Journal Articles

Multi-Objective Optimization of Double-Tube Once-Through Steam Generator

Xinyu Wei, Chunhui Dai, Yun Tai, Fuyu Zhao
Journal: Journal of Heat Transfer
Article Type: Heat Exchangers
J. Heat Transfer. July 2012, 134(7): 071801.
DOI: https://doi.org/10.1115/1.4006102
Published Online: May 24, 2012
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Topics: Boilers, Design, Flow (Dynamics), Fluids, Pareto optimization, Pressure drop, Heat transfer
Proceedings Papers

Characteristic Optimization of the Double-Tube OTSG

Xinyu Wei, Fuyu Zhao, Yun Tai, Chunhui Dai
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 147-152, May 17–21, 2010
Paper No: ICONE18-29137
DOI: https://doi.org/10.1115/ICONE18-29137
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Topics: Optimization, Heat transfer, Flow (Dynamics), Boilers, Boiling, Fluids, Nuclear power, Pumps, Superheating
Proceedings Papers

Analysis of Instability for OTSG by Using Multivariable Frequency Domain Method

Su-xia Hou, Yun Tai, Fu-yu Zhao
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 267-273, July 12–16, 2009
Paper No: ICONE17-75024
DOI: https://doi.org/10.1115/ICONE17-75024
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Topics: Boilers, Boiling, Boundary-value problems, Computers, Laplace transforms, Stability
Proceedings Papers

Analysis of Two-Phase Flow Instability for Steam Generator

Su-Xia Hou, Yun Tai, Fu-Yu Zhao
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 541-546, May 11–15, 2008
Paper No: ICONE16-48533
DOI: https://doi.org/10.1115/ICONE16-48533
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Topics: Boilers, Two-phase flow, Stability, Steam, Generators, Flow (Dynamics), Closed loop systems, Computers, Flow instability, Heat transfer
Proceedings Papers

Analysis of Two-Phase Flow Instability in Multichannel System

Fu-Yu Zhao, Su-Xia Hou, Yun Tai
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 905-910, May 11–15, 2008
Paper No: ICONE16-48905
DOI: https://doi.org/10.1115/ICONE16-48905
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Topics: Two-phase flow, Oscillations, Boilers, Eigenvalues, Nuclear reactors, Safety, Transfer functions
Proceedings Papers

Multiple Models Predictive Control of Once-Through Steam Generator

Yun Tai, Su-Xia Hou, Fu-Yu Zhao
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 993-1000, May 11–15, 2008
Paper No: ICONE16-48641
DOI: https://doi.org/10.1115/ICONE16-48641
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Topics: Boilers, Predictive control, Control equipment, Heat transfer, Mathematics, Multiphase flow, Nonlinear systems, Screws, Switches