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Proceedings Papers

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Qian Ma, Zhitong Yu, Peiwei Sun, Yuwen Jia, Shifa Wu
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A043, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64459
https://doi.org/10.1115/ICONE28-64459
View Paper titled, All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor
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Topics: Adaptive control, Design, Nuclear reactors, Control systems, Feedback, Fuels, Transfer functions, Ceramics, Control equipment, Dynamic models
Proceedings Papers

Study on the Dynamic Modeling of the Micro-High Temperature Gas Cooled Reactor for Control System Design

Leilei Qiu, Xinyu Wei, Peiwei Sun, Shengyong Liao
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A040, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64455
https://doi.org/10.1115/ICONE28-64455
View Paper titled, Study on the Dynamic Modeling of the Micro-High Temperature Gas Cooled Reactor for Control System Design
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Topics: Control systems, Design, Dynamic modeling, Dynamic models, Gas cooled reactors, Temperature, Transfer functions
Proceedings Papers

Transfer Function Development and Dynamic Analysis of a Heat Pipe Cooled Reactor

Songmao Pu, Peiwei Sun, Xinyu Wei
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A038, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64453
https://doi.org/10.1115/ICONE28-64453
View Paper titled, Transfer Function Development and Dynamic Analysis of a Heat Pipe Cooled Reactor
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Topics: Dynamic analysis, Heat pipes, Transfer functions
Proceedings Papers

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

Christopher Bennett, Scott Adams, Nick Alexander
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A021, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82628
https://doi.org/10.1115/ICONE26-82628
View Paper titled, Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method
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Topics: Architects, Boilers, Databases, Design, Dimensions, Engineering disciplines, Nuclear power stations, Nuclear reactors, Safety, Small modular reactors
Proceedings Papers

Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station

Yang Ting, Li Guang Sheng, Li Zeng Fen, Peng Yue, Hu Jian
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A019, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66189
https://doi.org/10.1115/ICONE25-66189
View Paper titled, Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station
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Topics: Nuclear power stations, Water, Cooling, Economics , Safety, Construction, Design, Failure, Heat sinks, Reservoirs
Proceedings Papers

The Application of Fault Tree Method in Systematic Multiple Spurious Operation Analysis in Fire PSA

Hu Yuehua, Li Lin, Yan Zhen, Song Lei
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A017, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66454
https://doi.org/10.1115/ICONE25-66454
View Paper titled, The Application of Fault Tree Method in Systematic Multiple Spurious Operation Analysis in Fire PSA
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Topics: Fire, Modeling, Nuclear reactor coolants, Risk, Transfer functions
Proceedings Papers

Effect of Soil Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building

Samer El-Bahey, Yasser Alzeni
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, V001T03A021, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60714
https://doi.org/10.1115/ICONE24-60714
View Paper titled, Effect of Soil Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building
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Topics: Nuclear reactors, Soil, Safety, Earthquake risk, Earthquakes, Damage, Design, Nuclear power stations, Accounting, Chaos
Proceedings Papers

An Improved Model to Study the Density Wave Oscillation in Tubes by Using Frequency Domain Method

Yifan Zhang, Huixiong Li, Tai Wang, Weiqiang Zhang, Tianyou Sheng
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A045, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30343
https://doi.org/10.1115/ICONE22-30343
View Paper titled, An Improved Model to Study the Density Wave Oscillation in Tubes by Using Frequency Domain Method
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Topics: Density, Oscillations, Waves, Metals, Heat flux, Heat storage, Geometry, Specific heat, Stability, Transfer functions
Proceedings Papers

The Thermal Balance Calculation of AP1000 Turbine Roll-Up by Non-Nuclear Steam

Shunda Wang, Xiuli Li
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A019, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15418
https://doi.org/10.1115/ICONE21-15418
View Paper titled, The Thermal Balance Calculation of AP1000 Turbine Roll-Up by Non-Nuclear Steam
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Topics: Steam, Turbines, Heat, Nuclear power stations, Design, Diseases, Nuclear reactor coolants, Pumps, Thermal stresses, Transfer functions
Proceedings Papers

Research and Solution on Vibration and Noise Caused by Orifice Cavitations of PTR System

Ting Yang, Yao Dong Wang, Xu Lun Jiang, Chun Ming Wu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A052, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16474
https://doi.org/10.1115/ICONE21-16474
View Paper titled, Research and Solution on Vibration and Noise Caused by Orifice Cavitations of PTR System
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Topics: Noise (Sound), Vibration, Cooling, Orifices, Cavities, Design, Nuclear power stations, Pipes, Pressure drop, Redundancy (Engineering)
Proceedings Papers

Research of Nuclear Emergency Management Information System in Guangdong Province

YongSheng Ling
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 641-646, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29906
https://doi.org/10.1115/ICONE18-29906
View Paper titled, Research of Nuclear Emergency Management Information System in Guangdong Province
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Topics: Emergency management, Emergencies, Emergency response, Oils, Petroleum, Computers, Databases, Decision making, Emergency preparedness, Nuclear power stations
Proceedings Papers

Localization of a Noise Source in VVER-1000 Reactor Core Using Neutron Noise Analysis Methods

Hessam Malmir, Naser Vosoughi, Ehsan Zahedinejad
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 189-196, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29562
https://doi.org/10.1115/ICONE18-29562
View Paper titled, Localization of a Noise Source in VVER-1000 Reactor Core Using Neutron Noise Analysis Methods
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Topics: Neutrons, Noise (Sound), Diffusion (Physics), Transfer functions, Approximation, Finite difference methods, Sensors
Proceedings Papers

Diversity-Oriented FPGA-Based NPP I&C Systems: Safety Assessment, Development, Implementation

Vyacheslav S. Kharchenko, Eugenii S. Bakhmach, Alexandr A. Siora, Vladimir V. Sklyar, Viktor I. Tokarev
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 755-764, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29754
https://doi.org/10.1115/ICONE18-29754
View Paper titled, Diversity-Oriented FPGA-Based NPP I&C Systems: Safety Assessment, Development, Implementation
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Topics: Nuclear power stations, Safety, Computer software, Cycles, Design, Engineering standards, Hardware, Redundancy (Engineering), Transfer functions
Proceedings Papers

Digital Image Evaluation Method for Digital Radiography

Masako Mori, Toshibumi Kashiwa, Yoshimitsu Aoki
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 223-228, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29702
https://doi.org/10.1115/ICONE18-29702
View Paper titled, Digital Image Evaluation Method for Digital Radiography
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Topics: Evaluation methods, Inspection, Testing, Transfer functions
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
Proceedings Papers

Closed Model for Calculation of Differential Pressure After a Loss of Coolant Accident in Boiling Water Reactors

Alexander Kratzsch, Wolfgang Ka¨stner, Rainer Hampel
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 623-628, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75562
https://doi.org/10.1115/ICONE17-75562
View Paper titled, Closed Model for Calculation of Differential Pressure After a Loss of Coolant Accident in Boiling Water Reactors
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Topics: Accidents, Boiling water reactors, Coolants, Pressure, Containment, Heat, Insulation, Exhaust systems, Condensation, Cooling systems
Proceedings Papers

Frequency Domain Linear Stability Analysis of Simplified Supercritical Water-Cooled Reactor

Pengfei Liu, Yanhua Yang, Aijun Xue, Xu Cheng
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 837-843, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75251
https://doi.org/10.1115/ICONE17-75251
View Paper titled, Frequency Domain Linear Stability Analysis of Simplified Supercritical Water-Cooled Reactor
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Topics: Stability, Water, Oscillations, Pressure, Boundary-value problems, Control theory, Flow (Dynamics), Fluids, Friction, Gravitational acceleration
Proceedings Papers

Recent Developments on Seismic PRA

Ovidiu Coman, Justin Onisoru
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 645-652, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48424
https://doi.org/10.1115/ICONE16-48424
View Paper titled, Recent Developments on Seismic PRA
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Topics: Damage, Earthquakes, Probabilistic risk assessment, Switches, Transfer functions
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48533
https://doi.org/10.1115/ICONE16-48533
View Paper titled, Analysis of Two-Phase Flow Instability for Steam Generator
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48905
https://doi.org/10.1115/ICONE16-48905
View Paper titled, Analysis of Two-Phase Flow Instability in Multichannel System
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Topics: Two-phase flow, Oscillations, Boilers, Eigenvalues, Nuclear reactors, Safety, Transfer functions