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Proceedings Papers

Thermal Performance Monitoring and Analysis of Nuclear Power Plant

Jianfei Hou, Xun Zhang, Heino Zimmermann, Zhaohui Xiang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A011, August 8–12, 2022

Paper No: ICONE29-91886

DOI: https://doi.org/10.1115/ICONE29-91886

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Topics: Nuclear power stations, Instrumentation, Circuits, Computer software, Condensers (steam plant), Damage, Design, Feedwater, High pressure (Physics), Pressure

Proceedings Papers

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

Jie Zhang, Jing Wang, Peiying Zhang, Kun Tan, Minxue Yang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A024, August 8–12, 2022

Paper No: ICONE29-91837

DOI: https://doi.org/10.1115/ICONE29-91837

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Topics: China, Construction, Nuclear power stations, Water, Safety, Risk, Accidents, Maintenance, Pressurized water reactors, Cooling

Proceedings Papers

Parametric Study of Throttling Window Shapes on Flow Force Characteristics in Main Feed Water Regulating Valve

Lei Zhao, Qiang Ru, Jia-Yi Wu, Jin-Yuan Qian

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A114, August 8–12, 2022

Paper No: ICONE29-93483

DOI: https://doi.org/10.1115/ICONE29-93483

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Topics: Feedwater, Flow (Dynamics), Shapes, Valves

Proceedings Papers

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

Zhiming Wu, Yixin Ling, Xing Liu, Dongdong Fei, Xiaoyu Hou, Xue Wen

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A078, August 8–12, 2022

Paper No: ICONE29-93343

DOI: https://doi.org/10.1115/ICONE29-93343

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Topics: Corrosion, Feedwater, Pipes, Pumps

Proceedings Papers

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

Dongyuan Li, Jinkai Wang, Jiaoshen Xu, Zengpei Zhu, Yaqi Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A072, August 8–12, 2022

Paper No: ICONE29-93277

DOI: https://doi.org/10.1115/ICONE29-93277

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Topics: Nuclear power plant operations, Nuclear reactor coolants, Nucleate boiling, Safety, Accidents, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Feedwater, Steam

Proceedings Papers

Design Verification of Minimum Flow Valve of the Main Feed Water Pump Based on the Full-Range Simulation Platform of CPR 1000

Zhenhua Zhang, Bo Zhang, Chaoying Zheng

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A014, August 8–12, 2022

Paper No: ICONE29-90543

DOI: https://doi.org/10.1115/ICONE29-90543

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Topics: Design, Feedwater, Flow (Dynamics), Pumps, Simulation, Valves

Proceedings Papers

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Wei Li, Jianfeng Shi, Yulong Qin, Lihua Wang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A047, August 8–12, 2022

Paper No: ICONE29-92633

DOI: https://doi.org/10.1115/ICONE29-92633

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Topics: Feedwater, Pumps, Rods, Nuclear power stations, Turbines

Proceedings Papers

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Merouane Najar, He Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022

Paper No: ICONE29-91516

DOI: https://doi.org/10.1115/ICONE29-91516

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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors

Proceedings Papers

Study of Effective Isolation Technology of Main Feedwater

Jiaming Zhao, Liqiang Fang, Liang Ding

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A047, August 8–12, 2022

Paper No: ICONE29-91611

DOI: https://doi.org/10.1115/ICONE29-91611

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Topics: Feedwater, Valves, Water hammer

Proceedings Papers

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A020, August 4–6, 2021

Paper No: ICONE28-64532

DOI: https://doi.org/10.1115/ICONE28-64532

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Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design

Proceedings Papers

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Masashi Sekine, Junichi Kaneko, Takeshi Takeda

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021

Paper No: ICONE28-64117

DOI: https://doi.org/10.1115/ICONE28-64117

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Topics: Accidents, Boilers, Pressurized water reactors, Rupture, Damage, Cooling, Earthquakes, Emergency core cooling systems, Failure, Feedwater

Proceedings Papers

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Jingrui Yang, Qian Ma, Lingtong Han, Peiwei Sun

Paper No: ICONE28-64460

DOI: https://doi.org/10.1115/ICONE28-64460

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Topics: Boilers, Coolants, Design, Electric power generation, Feedwater, Flow (Dynamics), Frequency-domain analysis, Heating, Momentum, Neutrons

Proceedings Papers

Loss of Main Feedwater ATWS Accident Analysis for Ship Nuclear Power Platform

Jinrong Qiu, Song Feifei, Li Longze, Hou Xiaofan, Chao Fei

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, V003T12A032, August 4–6, 2021

Paper No: ICONE28-65078

DOI: https://doi.org/10.1115/ICONE28-65078

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Topics: Accidents, Feedwater, Nuclear power, Ships

Proceedings Papers

Coordinated Control Scheme Design of a Nuclear Heating Reactor Cogeneration Plant for Balancing Renewables

Zhe Dong

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A004, August 4–5, 2020

Paper No: ICONE2020-16254

DOI: https://doi.org/10.1115/ICONE2020-16254

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Topics: Cogeneration plants, Combined heat and power, Design, Heating, Renewable energy sources, Steam, Flow (Dynamics), Nuclear power stations, Stress, Turbines

Proceedings Papers

Study on Measures During Loss of Normal Feedwater Accident for AP1000 NPP in Lower Power Operation

Baisong Ma, Zhengqiang Miao, Yaping Zhuang, Weili Hou

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A010, August 4–5, 2020

Paper No: ICONE2020-16122

DOI: https://doi.org/10.1115/ICONE2020-16122

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Topics: Accidents, Feedwater, Nuclear power stations, Water

Proceedings Papers

Transient Analysis of Dedicated Pressure Relief Valve Under High-Pressure Condition in Severe Accident for Tianwan 56 Nuclear Power Plant

Youyou Xu, Jian Deng, Xiaoji Wang, Lingjun Wu, Ming Zhang, Libo Qian, Rong Cai, Lei Zhong, Zhengyu Du

Paper No: ICONE2020-16847

DOI: https://doi.org/10.1115/ICONE2020-16847

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Topics: Accidents, Feedwater, High pressure (Physics), Nuclear power stations, Relief valves, Transient analysis

Proceedings Papers

Unsteady CFD Analyses of the Thermal Mixing of the Feedwater in the Downcomer of a BWR

Yann Le Moigne

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A035, July 22–26, 2018

Paper No: ICONE26-82179

DOI: https://doi.org/10.1115/ICONE26-82179

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Topics: Boiling water reactors, Computational fluid dynamics, Feedwater, Water, Design, Fluctuations (Physics), Reactor vessels, Temperature, Transients (Dynamics), High temperature

Proceedings Papers

Welded Joint Evaluation for Chromium Controlled Carbon Steel Piping to Improve FAC Resistance

Yoshio Uemoto, Takahiro Kawabe, Hiroyuki Shibata, Shoh Tarasawa, Hiroshi Asano, Junya Kaneda

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A022, July 22–26, 2018

Paper No: ICONE26-81913

DOI: https://doi.org/10.1115/ICONE26-81913

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Topics: Carbon steel, Pipes, Welded joints, Welding, Alloy steel, Alloys, Condensed matter, Construction, Corrosion, Feedwater

Proceedings Papers

Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000

Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A011, July 22–26, 2018

Paper No: ICONE26-82074

DOI: https://doi.org/10.1115/ICONE26-82074

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Topics: Accidents, Sensitivity analysis, Nuclear fission, Pressure, Boilers, Feedwater, Flow (Dynamics), Valves, Accident management, Nuclear reactor coolants

Proceedings Papers

LBLOCA Initiated Emergency Condition Analysis for a China Three-Loop PWR

Wang Ning, Chen Lei, Zhang Jiangang, Yang Yapeng, Xu Xiaoxiao, Feng Zongyang, Jia Linsheng

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A031, July 22–26, 2018

Paper No: ICONE26-81960

DOI: https://doi.org/10.1115/ICONE26-81960

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Topics: China, Emergencies, Pressurized water reactors, Accidents, Failure, Feedwater, Fukushima nuclear disaster, Japan, 2011, Safety, Water, Boilers

NARROW

Thermal Performance Monitoring and Analysis of Nuclear Power Plant

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

Parametric Study of Throttling Window Shapes on Flow Force Characteristics in Main Feed Water Regulating Valve

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

Design Verification of Minimum Flow Valve of the Main Feed Water Pump Based on the Full-Range Simulation Platform of CPR 1000

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Study of Effective Isolation Technology of Main Feedwater

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Loss of Main Feedwater ATWS Accident Analysis for Ship Nuclear Power Platform

Coordinated Control Scheme Design of a Nuclear Heating Reactor Cogeneration Plant for Balancing Renewables

Study on Measures During Loss of Normal Feedwater Accident for AP1000 NPP in Lower Power Operation

Transient Analysis of Dedicated Pressure Relief Valve Under High-Pressure Condition in Severe Accident for Tianwan 56 Nuclear Power Plant

Unsteady CFD Analyses of the Thermal Mixing of the Feedwater in the Downcomer of a BWR

Welded Joint Evaluation for Chromium Controlled Carbon Steel Piping to Improve FAC Resistance

Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000

LBLOCA Initiated Emergency Condition Analysis for a China Three-Loop PWR

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