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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81142
https://doi.org/10.1115/ICONE26-81142
View Paper titled, Design of Decoupled Mechanical Shim Control System for a Generation III+ Pressurized Water Reactor Based on Feedforward Compensation and Multimodel Approach
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Topics: Control systems, Design, Feedforward control, Pressurized water reactors, Control equipment, Temperature, Coolants, Stability, Stress, Transients (Dynamics)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81276
https://doi.org/10.1115/ICONE26-81276
View Paper titled, Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems
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Topics: Thermal hydraulics, Steady state, Transients (Dynamics), Computer simulation, Dynamic models, Engineering simulation, Fuels, Neutron sources, Neutrons, Simulation
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60328
https://doi.org/10.1115/ICONE24-60328
View Paper titled, Identification Modeling of Accelerator Driven System Based on Growing and Pruning Radial Basis Function Network
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60149
https://doi.org/10.1115/ICONE24-60149
View Paper titled, Verification of the AP1000 Nuclear Power Plant Simulator NPPSim Against RELAP5 for Transient Analysis
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60148
https://doi.org/10.1115/ICONE24-60148
View Paper titled, Parameter Optimization for AP1000 Steam Generator Feedwater Control System Using Particle Swarm Optimization Algorithm
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Topics: Algorithms, Boilers, Control systems, Feedwater, Optimization, Particle swarm optimization, Nuclear power stations, Simulation, Water, Control equipment
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
Publisher: American Society of Mechanical Engineers
Paper No: OMAE2015-41651
https://doi.org/10.1115/OMAE2015-41651
View Paper titled, Sediment Attractors: Seabed Shear Stress Shadows Around Subsea Pipelines Cause Net Sediment Accretion
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30468
https://doi.org/10.1115/ICONE22-30468
View Paper titled, Helical Pitch Optimization of Double-Tube Once-Through Steam Generator
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Topics: Boilers, Optimization, Pressure drop, Boiling, Coolants, Heat transfer, Superheating, Temperature distribution, Gradient methods, Nuclear reactors
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
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T13A005, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30373
https://doi.org/10.1115/ICONE22-30373
View Paper titled, Development of a Fast Simulation Program for AP1000 Reactor With Application of Mechanical Shim (MSHIM) Control Strategy and Nodal Method
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30747
https://doi.org/10.1115/ICONE22-30747
View Paper titled, An Alternative Approach to Prediction of Critical Heat Flux: Projection Support Vector Regression
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Topics: Critical heat flux, Support vector machines, Artificial neural networks, Boilers, Boiling, Cooling systems, Design, Fuels, Trains
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30376
https://doi.org/10.1115/ICONE22-30376
View Paper titled, Modeling and Control Strategy of the China LBE Cooled Fast Reactor
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Topics: China, Control modeling, Fast neutron reactors, Coolants, Simulation, Control equipment, Feedforward control, Temperature, Control systems, Design
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15396
https://doi.org/10.1115/ICONE21-15396
View Paper titled, Modeling and Simulation of Nuclear Power Units for Primary Frequency Regulation Research
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Topics: Modeling, Nuclear power, Simulation, Power systems (Machinery), Pressurized water reactors, Stability, Matlab, Nuclear power stations, Accidents, China
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16209
https://doi.org/10.1115/ICONE21-16209
View Paper titled, Simultaneous Fault Diagnosis of the Reactor Coolant System Based on the DSM Evidence Theory
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Topics: Fault diagnosis, Nuclear reactor coolants, Nuclear power stations, Sensors, Uncertainty, Probability, Reliability, Safety
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54266
https://doi.org/10.1115/ICONE20-POWER2012-54266
View Paper titled, On the Use of Support Vector Regression Technique for the Analysis of Rod Ejection Accidents
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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
Journal: ASME Journal of Heat and Mass Transfer
Publisher: ASME
Article Type: Heat Exchangers
J. Heat Mass Transfer. July 2012, 134(7): 071801.
https://doi.org/10.1115/1.4006102
Published Online: May 24, 2012
View Article titled, Multi-Objective Optimization of Double-Tube Once-Through Steam Generator
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29137
https://doi.org/10.1115/ICONE18-29137
View Paper titled, Characteristic Optimization of the Double-Tube OTSG
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29922
https://doi.org/10.1115/ICONE18-29922
View Paper titled, A Convenient Multi-Model Simulation Technique for Nuclear Reactor System
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Topics: Nuclear reactors, Simulation, Nonlinear systems, Switches, Transfer functions, Computer software, Matlab