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Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022

Paper No: ICONE29-92103

DOI: https://doi.org/10.1115/ICONE29-92103

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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results

Proceedings Papers

Optimization of Transient Control Method for RCV System

Yong Qiang Huang, Zhi Lin Chen, Xin Chen, Zheng Gu, Han Min Chen, Run Ze Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A073, August 8–12, 2022

Paper No: ICONE29-93279

DOI: https://doi.org/10.1115/ICONE29-93279

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Topics: Optimization, Transients (Dynamics)

Proceedings Papers

Quality Analysis and Abnormal Repair of Transient Monitoring Data of CPR1000 Unit

Wangjie Qian, Zhilin Chen, Feng Lv, Yanwei Zhang, Zheng Gu, Xin Chen, Hanming Chen, Nianqing Fan

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A085, August 8–12, 2022

Paper No: ICONE29-93587

DOI: https://doi.org/10.1115/ICONE29-93587

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Topics: Maintenance, Nuclear power stations, Statistics, Transients (Dynamics)

Proceedings Papers

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Xifeng Lu, Furui Xiong, Xinjun Wang, Honglei Ai, Bingjin Li, Xuejiao Shao, Kang Yang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A017, August 8–12, 2022

Paper No: ICONE29-90677

DOI: https://doi.org/10.1115/ICONE29-90677

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Topics: Boilers, Dynamic response, Heat transfer, Time-domain analysis, Stress, Modal analysis, Dynamic response analysis, Emission spectroscopy, Finite element model, Frequency-domain analysis

Proceedings Papers

Research on Intelligent Classification Method of Primary Loop Transient in Nuclear Power Plant

Run Ze Zhang, Zhi Lin Chen, Yong Qiang Huang, Xin Chen

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A058, August 8–12, 2022

Paper No: ICONE29-92874

DOI: https://doi.org/10.1115/ICONE29-92874

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Topics: Machine learning, Nuclear power stations, Transients (Dynamics)

Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022

Paper No: ICONE29-90521

DOI: https://doi.org/10.1115/ICONE29-90521

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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors

Proceedings Papers

Research on Once-Through Steam Generator Steam Pressure Response Characteristics

Xiaoting Wang, Yiran Liu, Jianmin Zhu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A054, August 8–12, 2022

Paper No: ICONE29-93564

DOI: https://doi.org/10.1115/ICONE29-93564

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Topics: Boilers, Control systems, Engineering simulation, Pressure, Pressure control, Simulation, Steam, Transients (Dynamics)

Proceedings Papers

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Peng Yuan, Jian Deng, Zhifang Qiu, Qinglan Xu, Dahuan Zhu, Tao Huang, Zhongchun Li, Peng Du

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A006, August 8–12, 2022

Paper No: ICONE29-92380

DOI: https://doi.org/10.1115/ICONE29-92380

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Topics: Accidents, Algorithms, Artificial neural networks, China, Coolants, Design, Flow (Dynamics), Machine learning, Nuclear power stations, Nuclear reactors

Proceedings Papers

Numerical Simulation of Transient Thermal-Hydraulic Characteristics of Intermediate Heat Exchanger for Sodium Cooled Fast Reactor Under Accident Conditions

Xiehu Zeng, Qinglong Wen, Genxing Bai

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A047, August 8–12, 2022

Paper No: ICONE29-93387

DOI: https://doi.org/10.1115/ICONE29-93387

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Topics: Accidents, Computer simulation, Heat exchangers, Sodium fast reactors, Transients (Dynamics)

Proceedings Papers

Numerical Analysis on Pressurizer Liquid Level Characteristic Under Marine Conditions

Sijie Xu, Tianyi Wei, Jinyu Yue, Dongyang Li, Sichao Tan

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A039, August 8–12, 2022

Paper No: ICONE29-92322

DOI: https://doi.org/10.1115/ICONE29-92322

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Topics: Algorithms, Computational fluid dynamics, Computer simulation, Equations of motion, Flow (Dynamics), Numerical analysis, Ocean waves, Pressure, Sloshing, Transients (Dynamics)

Proceedings Papers

Numerical Model Development for the Transient Heat and Mass Transfer Performance of a Water-Copper Wicked Heat Pipe

Jian Liu, Xingchi Jiang, Syed Waqar Ali Shah, Yuanjie Li, Chongju Hu, Dali Yu, Taosheng Li, Chin Pan

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A037, August 8–12, 2022

Paper No: ICONE29-92297

DOI: https://doi.org/10.1115/ICONE29-92297

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Topics: Computer simulation, Copper, Heat, Heat pipes, Mass transfer, Transients (Dynamics), Water

Proceedings Papers

Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant

Jiaolong Deng, Xiang Chai, Tengfei Zhang, Xiaojing Liu

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A036, August 8–12, 2022

Paper No: ICONE29-92247

DOI: https://doi.org/10.1115/ICONE29-92247

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Topics: Nuclear power stations, Physics, Simulation, Transients (Dynamics)

Proceedings Papers

Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator

Pietro Cioli Puviani, Ivan Di Piazza, Ranieri Marinari, Roberto Zanino, Mariano Tarantino

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A064, August 8–12, 2022

Paper No: ICONE29-93457

DOI: https://doi.org/10.1115/ICONE29-93457

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Topics: Complex systems, Computational fluid dynamics, Design, Fuels, Heating, Manufacturing, Porous materials, Safety, Simulation, Steady state

Proceedings Papers

Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter

Satoshi Okajima, Takero Mori, Norihiro Kikuchi, Masaaki Tanaka, Masashi Miyazaki

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 8–12, 2022

Paper No: ICONE29-88933

DOI: https://doi.org/10.1115/ICONE29-88933

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Topics: Design, Failure, Optimization, Probability, Transients (Dynamics)

Proceedings Papers

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Yu Tan, Xuejiao Shao, Enming Liang, Shuchun Zuo, Feng Lv, Thomas Metais, Han Liu

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A015, August 8–12, 2022

Paper No: ICONE29-93561

DOI: https://doi.org/10.1115/ICONE29-93561

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Topics: China, Vessels, Bullets, Computational methods, Computer software, Evaluation methods, Fatigue, Fatigue analysis, Geometry, Nozzles

Proceedings Papers

A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A020, August 8–12, 2022

Paper No: ICONE29-94327

DOI: https://doi.org/10.1115/ICONE29-94327

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Topics: Fatigue damage, Nuclear power stations, Transients (Dynamics)

Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022

Paper No: ICONE29-89017

DOI: https://doi.org/10.1115/ICONE29-89017

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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis

Proceedings Papers

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

Xiaoyan Yang, Hongyi Yang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A072, August 8–12, 2022

Paper No: ICONE29-92214

DOI: https://doi.org/10.1115/ICONE29-92214

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Topics: Kalman filters, Design, Nuclear reactors, Porosity, Safety, Simulation, Transients (Dynamics)

Proceedings Papers

Visual Experimental Investigation on Vapor-Liquid Interface Fluctuation Characteristics During CHF Transient

Haidong Liu, Deqi Chen, Jiang Qin, Peigang Yan

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A060, August 8–12, 2022

Paper No: ICONE29-92044

DOI: https://doi.org/10.1115/ICONE29-92044

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Topics: Boiling, Critical heat flux, Flow (Dynamics), Transients (Dynamics), Vapors

Proceedings Papers

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

Xiao Ke

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022

Paper No: ICONE29-90343

DOI: https://doi.org/10.1115/ICONE29-90343

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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback

2 3 4 5

NARROW

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Optimization of Transient Control Method for RCV System

Quality Analysis and Abnormal Repair of Transient Monitoring Data of CPR1000 Unit

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Research on Intelligent Classification Method of Primary Loop Transient in Nuclear Power Plant

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Research on Once-Through Steam Generator Steam Pressure Response Characteristics

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Numerical Simulation of Transient Thermal-Hydraulic Characteristics of Intermediate Heat Exchanger for Sodium Cooled Fast Reactor Under Accident Conditions

Numerical Analysis on Pressurizer Liquid Level Characteristic Under Marine Conditions

Numerical Model Development for the Transient Heat and Mass Transfer Performance of a Water-Copper Wicked Heat Pipe

Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant

Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator

Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

Visual Experimental Investigation on Vapor-Liquid Interface Fluctuation Characteristics During CHF Transient

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

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