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Proceedings Papers

Anomaly Detection of Electric Gate Valve Based on Multi-Kernel Support Vector Machine

Jing Luo, Hang Wang, Minjun Peng

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A064, August 4–6, 2021

Paper No: ICONE28-64766

DOI: https://doi.org/10.1115/ICONE28-64766

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Topics: Gates (Closures), Support vector machines, Valves

Proceedings Papers

Analysis of IPWR Severe Accident Process Response to SBLOCA

Hao Yu, Minjun Peng

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, V003T12A023, August 4–6, 2021

Paper No: ICONE28-64417

DOI: https://doi.org/10.1115/ICONE28-64417

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Topics: Accidents

Proceedings Papers

Implementation and Validation of an Improved Interfacial Area Concentration Model for Two-Phase Flow CFD Simulations

Xiang Zhang, Minjun Peng, Tenglong Cong, Chuan Lu, Chenyang Wang

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A029, August 4–6, 2021

Paper No: ICONE28-64342

DOI: https://doi.org/10.1115/ICONE28-64342

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Topics: Boiling, Computational fluid dynamics, Drag (Fluid dynamics), Flow (Dynamics), Simulation, Two-phase flow

Proceedings Papers

Analysis of IP200 Severe Accident Process Response to SBO and Emergency Power Failure

Zhenhang Zheng, Minjun Peng, Hao Yu, Yang Yang

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A052, August 4–6, 2021

Paper No: ICONE28-64541

DOI: https://doi.org/10.1115/ICONE28-64541

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Topics: Accidents, Emergency power, Failure

Proceedings Papers

Research on Remaining Useful Lifetime Prediction Methods of Main Transformer in Nuclear Power Station

Zikang Li, Minjun Peng

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A034, August 4–6, 2021

Paper No: ICONE28-64425

DOI: https://doi.org/10.1115/ICONE28-64425

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Topics: Filters, Kalman filters, Nuclear power stations, Particulate matter

Proceedings Papers

Research on Optimization and Verification Method of Sensor Arrangement in the Chemical and Volume Control System

Gui Zhou, Hang Wang, Minjun Peng

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A068, August 4–6, 2021

Paper No: ICONE28-65466

DOI: https://doi.org/10.1115/ICONE28-65466

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Topics: Control systems, Optimization, Particle swarm optimization, Sensor placement, Sensors

Proceedings Papers

Validation of RELAP5/MOD3.4 for Flashing-Induced Instabilities in a Natural Circulation Loop

Yifan Xu, Minjun Peng, Genglei Xia, Yanan Zhao

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A020, August 4–5, 2020

Paper No: ICONE2020-16296

DOI: https://doi.org/10.1115/ICONE2020-16296

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Topics: Flashing, Flow instability

Proceedings Papers

Simulation Research on Thermal-Hydraulic Performance of a Natural Circulation Integrated Pressurized Water Reactor

Yanan Zhao, Minjun Peng, Genglei Xia, Lianxin Lv

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A004, July 22–26, 2018

Paper No: ICONE26-81059

DOI: https://doi.org/10.1115/ICONE26-81059

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Topics: Pressurized water reactors, Simulation, Control systems, Design, Flashing, Pressure, Safety, Simulation models, Steady state, Steam

Proceedings Papers

Research of Fast Modeling and Simulating Platform for Nuclear Power Plant Secondary Loop

Meijie Gong, Minjun Peng, Haishan Zhu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A053, July 22–26, 2018

Paper No: ICONE26-81779

DOI: https://doi.org/10.1115/ICONE26-81779

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Topics: Modeling, Nuclear power stations, Simulation, Simulation models, Computers, Design, Simulation results

Proceedings Papers

Prediction of Subcooled Boiling With Uncertainties From Boundary Conditions and Interaction Models

Tenglong Cong, Minjun Peng, Xiang Zhang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A003, July 22–26, 2018

Paper No: ICONE26-81101

DOI: https://doi.org/10.1115/ICONE26-81101

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Topics: Boiling, Boundary-value problems, Subcooling, Uncertainty, Computational fluid dynamics, Calibration, Gaussian distribution, Model validation, Statistical analysis, Uncertainty analysis

Proceedings Papers

Analysis of Two-Phase Flow Instability in Multi-Channel System

Genglei Xia, Minjun Peng, Du Xue

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A053, July 7–11, 2014

Paper No: ICONE22-30417

DOI: https://doi.org/10.1115/ICONE22-30417

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Topics: Two-phase flow, Flow instability, Computers, Flow (Dynamics), Microchannels, Pressure, Stability, Subcooling

Proceedings Papers

Nuclear Power Plant Passive Residual Heat Removal System Design and Simulation

Xiao Yuan, Minjun Peng, Genglei Xia

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A018, July 29–August 2, 2013

Paper No: ICONE21-15713

DOI: https://doi.org/10.1115/ICONE21-15713

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Topics: Design, Heat, Nuclear power stations, Safety, Simulation

Proceedings Papers

Thermal-Hydraulic Character Effect Factors Analysis for Passive Residual Heat Removal System of Sodium-Cooled Fast Reactor

Xiaolong Sun, Minjun Peng, Genglei Xia

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 61-66, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54319

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54319

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Topics: Heat, Sodium fast reactors, Heat exchangers, China, Fast neutron reactors, Heat transfer, Pipes, Temperature, Transients (Dynamics)

Proceedings Papers

A Review on Specific Features of Small and Medium Sized Nuclear Power Plants

Salah Ud-din Khan, Minjun Peng, Muhammad Zubair, Shaowu Wang

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 65-77, May 17–21, 2010

Paper No: ICONE18-29399

DOI: https://doi.org/10.1115/ICONE18-29399

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Topics: Nuclear power stations, Nuclear reactors, Design, Nuclear industry, Nuclear power, Safety, Climate change, Distributed power generation, Electric power generation, Light water reactors

Proceedings Papers

Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor

Liguo Jiang, Minjun Peng, Jiange Liu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 915-920, May 17–21, 2010

Paper No: ICONE18-29953

DOI: https://doi.org/10.1115/ICONE18-29953

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Topics: Accidents, Pressurized water reactors, Boilers, Rupture, Safety, Discharge coefficient, Flow (Dynamics), Heat, High pressure (Physics), Modeling

Proceedings Papers

Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD3.4

Xuhua Ye, Minjun Peng, Jiange Liu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 943-947, May 17–21, 2010

Paper No: ICONE18-29987

DOI: https://doi.org/10.1115/ICONE18-29987

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Topics: Pressurized water reactors, Boilers, Valves, Coolants, Design, Emergencies, Flow (Dynamics), Fluid dynamics, Heat, Heat exchangers

Proceedings Papers

Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code

Jiange Liu, Minjun Peng

Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 489-495, July 12–16, 2009

Paper No: ICONE17-75452

DOI: https://doi.org/10.1115/ICONE17-75452

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Topics: Annulus, Flow (Dynamics), Heat transfer, Flow instability, Fluids, Heat transfer coefficients, Nuclear power, Pressure drop, Temperature, Wall temperature

Proceedings Papers

Optimization and Analysis for Passive Residual Heat Removal System of an Integral Pressurized Water Reactor

Shoubao Dai, Minjun Peng, Jiange Liu

Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 517-522, July 12–16, 2009

Paper No: ICONE17-75503

DOI: https://doi.org/10.1115/ICONE17-75503

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Topics: Heat, Optimization, Pressurized water reactors, Design, Pressure, Heat exchangers, Boilers, Coolants, Heat sinks, Heat transfer

Proceedings Papers

Application of Virtual Reality in Evaluation and Optimization for Human Machine Interface

Shengyuan Yan, Chunyan Xia, Zhijian Zhang, Minjun Peng, Ming Yang

Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 791-796, July 12–16, 2009

Paper No: ICONE17-75644

DOI: https://doi.org/10.1115/ICONE17-75644

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Topics: Machinery, Optimization, Virtual reality, Simulation, Computer software, Control rooms

Proceedings Papers

Research on the Computerized Symptom-Oriented Procedures of Nuclear Power Plants

Fei Liu, Zhijian Zhang, Minjun Peng

Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 607-614, May 11–15, 2008

Paper No: ICONE16-48072

DOI: https://doi.org/10.1115/ICONE16-48072

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Topics: Nuclear power stations, Signals, Accidents, Emergencies, Pressurized water reactors, Safety, Accident management, Boilers, Control rooms, Design

Journal citation

NARROW

Anomaly Detection of Electric Gate Valve Based on Multi-Kernel Support Vector Machine

Analysis of IPWR Severe Accident Process Response to SBLOCA

Implementation and Validation of an Improved Interfacial Area Concentration Model for Two-Phase Flow CFD Simulations

Analysis of IP200 Severe Accident Process Response to SBO and Emergency Power Failure

Research on Remaining Useful Lifetime Prediction Methods of Main Transformer in Nuclear Power Station

Research on Optimization and Verification Method of Sensor Arrangement in the Chemical and Volume Control System

Validation of RELAP5/MOD3.4 for Flashing-Induced Instabilities in a Natural Circulation Loop

Simulation Research on Thermal-Hydraulic Performance of a Natural Circulation Integrated Pressurized Water Reactor

Research of Fast Modeling and Simulating Platform for Nuclear Power Plant Secondary Loop

Prediction of Subcooled Boiling With Uncertainties From Boundary Conditions and Interaction Models

Analysis of Two-Phase Flow Instability in Multi-Channel System

Nuclear Power Plant Passive Residual Heat Removal System Design and Simulation

Thermal-Hydraulic Character Effect Factors Analysis for Passive Residual Heat Removal System of Sodium-Cooled Fast Reactor

A Review on Specific Features of Small and Medium Sized Nuclear Power Plants

Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor

Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD3.4

Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code

Optimization and Analysis for Passive Residual Heat Removal System of an Integral Pressurized Water Reactor

Application of Virtual Reality in Evaluation and Optimization for Human Machine Interface

Research on the Computerized Symptom-Oriented Procedures of Nuclear Power Plants

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