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Proceedings Papers

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Run Luo, Pengfei Wang, Xinyu Wei, Shripad T. Revankar, Fuyu Zhao

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A004, July 22–26, 2018

Paper No: ICONE26-81276

DOI: https://doi.org/10.1115/ICONE26-81276

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Topics: Thermal hydraulics, Steady state, Transients (Dynamics), Computer simulation, Dynamic models, Engineering simulation, Fuels, Neutron sources, Neutrons, Simulation

Proceedings Papers

Design of Decoupled Mechanical Shim Control System for a Generation III+ Pressurized Water Reactor Based on Feedforward Compensation and Multimodel Approach

Pengfei Wang, Xinyu Wei, Fuyu Zhao

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, V001T04A002, July 22–26, 2018

Paper No: ICONE26-81142

DOI: https://doi.org/10.1115/ICONE26-81142

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Topics: Control systems, Design, Feedforward control, Pressurized water reactors, Control equipment, Temperature, Coolants, Stability, Stress, Transients (Dynamics)

Proceedings Papers

Parameter Optimization for AP1000 Steam Generator Feedwater Control System Using Particle Swarm Optimization Algorithm

Shifa Wu, Pengfei Wang, Jiashuang Wan, Xinyu Wei, Fuyu Zhao

Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T04A006, June 26–30, 2016

Paper No: ICONE24-60148

DOI: https://doi.org/10.1115/ICONE24-60148

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Topics: Algorithms, Boilers, Control systems, Feedwater, Optimization, Particle swarm optimization, Nuclear power stations, Simulation, Water, Control equipment

Proceedings Papers

Identification Modeling of Accelerator Driven System Based on Growing and Pruning Radial Basis Function Network

Run Luo, Shifa Wu, Xinyu Wei, Fuyu Zhao

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A011, June 26–30, 2016

Paper No: ICONE24-60328

DOI: https://doi.org/10.1115/ICONE24-60328

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Topics: Modeling, Radial basis function networks, Artificial neural networks, Computation, Algorithms, Kalman filters, Simulation results, Transient analysis

Proceedings Papers

Verification of the AP1000 Nuclear Power Plant Simulator NPPSim Against RELAP5 for Transient Analysis

Shifa Wu, Pengfei Wang, Huawei Fang, Xinyu Wei, Fuyu Zhao

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A008, June 26–30, 2016

Paper No: ICONE24-60149

DOI: https://doi.org/10.1115/ICONE24-60149

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Topics: Nuclear power stations, Transient analysis, Transients (Dynamics), Control systems, Pressurized water reactors, Stress, Matlab, Nuclear reactors, Simulation results

Proceedings Papers

Sediment Attractors: Seabed Shear Stress Shadows Around Subsea Pipelines Cause Net Sediment Accretion

Fuyu Zhao, Terry Griffiths, Wenwen Shen, Scott Draper, Hongwei An, Jeremy Leggoe, Daniel Carneiro

Proc. ASME. OMAE2015, Volume 5A: Pipeline and Riser Technology, V05AT04A015, May 31–June 5, 2015

Paper No: OMAE2015-41651

DOI: https://doi.org/10.1115/OMAE2015-41651

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Topics: Attractors, Seabed, Sediments, Shades and shadows, Shear stress, Underwater pipelines, Pipes, Sedimentation, Waves, Computational fluid dynamics

Proceedings Papers

Helical Pitch Optimization of Double-Tube Once-Through Steam Generator

Huawei Fang, Xinyu Wei, Shoujun Yan, Jiashuang Wan, Fuyu Zhao

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A061, July 7–11, 2014

Paper No: ICONE22-30468

DOI: https://doi.org/10.1115/ICONE22-30468

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Topics: Boilers, Optimization, Pressure drop, Boiling, Coolants, Heat transfer, Superheating, Temperature distribution, Gradient methods, Nuclear reactors

Proceedings Papers

Modeling and Control Strategy of the China LBE Cooled Fast Reactor

Shoujun Yan, Zhao Wang, Pengfei Wang, Jiashuang Wan, Huawei Fang, Fuyu Zhao

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T13A007, July 7–11, 2014

Paper No: ICONE22-30376

DOI: https://doi.org/10.1115/ICONE22-30376

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Topics: China, Control modeling, Fast neutron reactors, Coolants, Simulation, Control equipment, Feedforward control, Temperature, Control systems, Design

Proceedings Papers

Development of a Fast Simulation Program for AP1000 Reactor With Application of Mechanical Shim (MSHIM) Control Strategy and Nodal Method

Pengfei Wang, Huawei Fang, Zhao Wang, Shoujun Yan, Jiashuang Wan, Fuyu Zhao

Paper No: ICONE22-30373

DOI: https://doi.org/10.1115/ICONE22-30373

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Topics: Simulation, Stress, Neutrons, Transients (Dynamics), Computation, Computer programming, Control equipment, Diffusion (Physics), Dynamics (Mechanics), Matlab

Proceedings Papers

An Alternative Approach to Prediction of Critical Heat Flux: Projection Support Vector Regression

Botao Jiang, Fuyu Zhao

Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A030, July 7–11, 2014

Paper No: ICONE22-30747

DOI: https://doi.org/10.1115/ICONE22-30747

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Topics: Critical heat flux, Support vector machines, Artificial neural networks, Boilers, Boiling, Cooling systems, Design, Fuels, Trains

Proceedings Papers

Simultaneous Fault Diagnosis of the Reactor Coolant System Based on the DSM Evidence Theory

Jinshen Ren, Botao Jiang, Fuyu Zhao

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A031, July 29–August 2, 2013

Paper No: ICONE21-16209

DOI: https://doi.org/10.1115/ICONE21-16209

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Topics: Fault diagnosis, Nuclear reactor coolants, Nuclear power stations, Sensors, Uncertainty, Probability, Reliability, Safety

Proceedings Papers

Modeling and Simulation of Nuclear Power Units for Primary Frequency Regulation Research

Zhenpeng Tang, Fuyu Zhao, Pengfei Wang, Li Chen, Huawei Fang

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, V005T13A007, July 29–August 2, 2013

Paper No: ICONE21-15396

DOI: https://doi.org/10.1115/ICONE21-15396

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Topics: Modeling, Nuclear power, Simulation, Power systems (Machinery), Pressurized water reactors, Stability, Matlab, Nuclear power stations, Accidents, China

Proceedings Papers

On the Use of Support Vector Regression Technique for the Analysis of Rod Ejection Accidents

Botao Jiang, Yang Liu, Fuyu Zhao

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 99-102, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54266

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54266

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Topics: Accidents, Support vector machines, Artificial neural networks, Pressurized water reactors, Trains, Computers, Design, Machine learning, Nuclear engineering, Power stations

Journal Articles

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

Xinyu Wei, Chunhui Dai, Yun Tai, Fuyu Zhao

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

A Convenient Multi-Model Simulation Technique for Nuclear Reactor System

Jinfeng Peng, Fuyu Zhao, Cheng Liu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 803-807, May 17–21, 2010

Paper No: ICONE18-29922

DOI: https://doi.org/10.1115/ICONE18-29922

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Topics: Nuclear reactors, Simulation, Nonlinear systems, Switches, Transfer functions, Computer software, Matlab

Journal citation

NARROW

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Design of Decoupled Mechanical Shim Control System for a Generation III+ Pressurized Water Reactor Based on Feedforward Compensation and Multimodel Approach

Parameter Optimization for AP1000 Steam Generator Feedwater Control System Using Particle Swarm Optimization Algorithm

Identification Modeling of Accelerator Driven System Based on Growing and Pruning Radial Basis Function Network

Verification of the AP1000 Nuclear Power Plant Simulator NPPSim Against RELAP5 for Transient Analysis

Sediment Attractors: Seabed Shear Stress Shadows Around Subsea Pipelines Cause Net Sediment Accretion

Helical Pitch Optimization of Double-Tube Once-Through Steam Generator

Modeling and Control Strategy of the China LBE Cooled Fast Reactor

Development of a Fast Simulation Program for AP1000 Reactor With Application of Mechanical Shim (MSHIM) Control Strategy and Nodal Method

An Alternative Approach to Prediction of Critical Heat Flux: Projection Support Vector Regression

Simultaneous Fault Diagnosis of the Reactor Coolant System Based on the DSM Evidence Theory

Modeling and Simulation of Nuclear Power Units for Primary Frequency Regulation Research

On the Use of Support Vector Regression Technique for the Analysis of Rod Ejection Accidents

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

Characteristic Optimization of the Double-Tube OTSG

A Convenient Multi-Model Simulation Technique for Nuclear Reactor System

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