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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

Paper No: ICONE28-64455

DOI: https://doi.org/10.1115/ICONE28-64455

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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

Paper No: ICONE28-64453

DOI: https://doi.org/10.1115/ICONE28-64453

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Topics: Dynamic analysis, Heat pipes, Transfer functions

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

Paper No: ICONE28-64459

DOI: https://doi.org/10.1115/ICONE28-64459

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Topics: Adaptive control, Design, Nuclear reactors, Control systems, Feedback, Fuels, Transfer functions, Ceramics, Control equipment, Dynamic models

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

Paper No: ICONE26-82628

DOI: https://doi.org/10.1115/ICONE26-82628

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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

Paper No: ICONE25-66189

DOI: https://doi.org/10.1115/ICONE25-66189

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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

Paper No: ICONE25-66454

DOI: https://doi.org/10.1115/ICONE25-66454

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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

Paper No: ICONE24-60714

DOI: https://doi.org/10.1115/ICONE24-60714

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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

Paper No: ICONE22-30343

DOI: https://doi.org/10.1115/ICONE22-30343

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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

Paper No: ICONE21-15418

DOI: https://doi.org/10.1115/ICONE21-15418

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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

Paper No: ICONE21-16474

DOI: https://doi.org/10.1115/ICONE21-16474

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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

Paper No: ICONE18-29906

DOI: https://doi.org/10.1115/ICONE18-29906

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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

Paper No: ICONE18-29562

DOI: https://doi.org/10.1115/ICONE18-29562

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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

Paper No: ICONE18-29754

DOI: https://doi.org/10.1115/ICONE18-29754

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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

Paper No: ICONE18-29702

DOI: https://doi.org/10.1115/ICONE18-29702

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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

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

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

Paper No: ICONE17-75562

DOI: https://doi.org/10.1115/ICONE17-75562

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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

Paper No: ICONE17-75251

DOI: https://doi.org/10.1115/ICONE17-75251

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Topics: Stability, Water, Oscillations, Pressure, Boundary-value problems, Control theory, Flow (Dynamics), Fluids, Friction, Gravitational acceleration

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

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

Paper No: ICONE16-48424

DOI: https://doi.org/10.1115/ICONE16-48424

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Topics: Damage, Earthquakes, Probabilistic risk assessment, Switches, Transfer functions

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

NARROW

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

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

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

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

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

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

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

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

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

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

Research of Nuclear Emergency Management Information System in Guangdong Province

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

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

Digital Image Evaluation Method for Digital Radiography

A Convenient Multi-Model Simulation Technique for Nuclear Reactor System

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

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

Analysis of Two-Phase Flow Instability for Steam Generator

Recent Developments on Seismic PRA

Analysis of Two-Phase Flow Instability in Multichannel System

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