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Proceedings Papers

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

Zhang Hengrui, Huang Qian, Fu Peiren, Zhang Daoke, Cai Rui, Sun Lei, Chen Qiuyang, Xue Feng

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A050, August 8–12, 2022

Paper No: ICONE29-92727

DOI: https://doi.org/10.1115/ICONE29-92727

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Topics: Damage, Nuclear reactor coolants, Pumps

Proceedings Papers

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

Rui Nie, Yu Wang, Feng Xie, Shan Qing, Jianzhu Cao

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022

Paper No: ICONE29-88883

DOI: https://doi.org/10.1115/ICONE29-88883

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Topics: Damage, Fuels, Nuclides, Pressurized water reactors, Very high temperature reactors

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

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022

Paper No: ICONE29-90146

DOI: https://doi.org/10.1115/ICONE29-90146

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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)

Proceedings Papers

Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3

Zhuang Shao, Ziqi Cai, Qingmin Zhang

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A027, August 8–12, 2022

Paper No: ICONE29-92600

DOI: https://doi.org/10.1115/ICONE29-92600

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Topics: Damage, Displacement, Energy gap, Irradiation (Radiation exposure), Neutrons, Protons, Semiconductors (Materials), Simulation

Proceedings Papers

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Yan Zhang, JianLei Zhang, Zhonghe Cheng

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A045, August 8–12, 2022

Paper No: ICONE29-92978

DOI: https://doi.org/10.1115/ICONE29-92978

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Topics: Boilers, Damage, Maintenance, Melting, Nondestructive evaluation, Pressurized water reactors, Welded joints

Proceedings Papers

Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact by Projectiles: Numerical Analysis on Test Results

Zuoyi Kang, Yukihiko Okuda, Akemi Nishida, Haruji Tsubota, Yinsheng Li

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A001, August 8–12, 2022

Paper No: ICONE29-88884

DOI: https://doi.org/10.1115/ICONE29-88884

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Topics: Damage, Impact testing, Numerical analysis, Projectiles, Reinforced concrete

Proceedings Papers

Research on Liability Insurance for Radioactive Sources and Suggestions to China

Xiao Ding Li, Yu Gong, Guang Hui Li, Gang Bai, Jie Ying Zheng, Yun Huan Qu, Zhe Li

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A060, August 8–12, 2022

Paper No: ICONE29-93505

DOI: https://doi.org/10.1115/ICONE29-93505

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Topics: China, Damage, Insurance, Liabilities

Proceedings Papers

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Saifeng Wu, Wenguang Liu, Wenfu He

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A045, August 8–12, 2022

Paper No: ICONE29-92541

DOI: https://doi.org/10.1115/ICONE29-92541

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Topics: Friction, Mechanical properties, Bearings, Damage, Deformation, Design, Earthquakes, Errors, Rubber, Stiffness

Proceedings Papers

Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite

Tianchen Zeng, Yuewen Sun, Peng Cong

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A037, August 8–12, 2022

Paper No: ICONE29-92295

DOI: https://doi.org/10.1115/ICONE29-92295

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Topics: Damage, Graphite, Simulation

Proceedings Papers

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

Guogang Bao, Changdong Lu, Weiwei Wang, Ren Liang, Zhikang Lin, Yong Ouyang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A013, August 8–12, 2022

Paper No: ICONE29-89383

DOI: https://doi.org/10.1115/ICONE29-89383

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Topics: Accidents, Cladding systems (Building), Coolants, Damage, Fuel rods, Heat, Pressure, Resonance ionization spectroscopy, Safety, Leakage

Proceedings Papers

Investigation the Fuel Damage Fraction of IB-LOCA

Zhidong Yue, Ting Wei, Wei Cai, Xiao Ke, Ying Zhang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A055, August 8–12, 2022

Paper No: ICONE29-91811

DOI: https://doi.org/10.1115/ICONE29-91811

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Topics: Cladding systems (Building), Damage, Fuels

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

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022

Paper No: ICONE29-91707

DOI: https://doi.org/10.1115/ICONE29-91707

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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry

Proceedings Papers

The Development and Application of Real-Time Risk Monitor System Based on Level 2 PSA for NPP

Wenjing Li, Yu Liu, Wei Wei, Xinli Yu

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A022, August 8–12, 2022

Paper No: ICONE29-91785

DOI: https://doi.org/10.1115/ICONE29-91785

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Topics: Nuclear power stations, Risk monitoring, Risk, Risk management, Safety, Economics , Optimization, China, Damage, Failure

Proceedings Papers

Study on Interfacing System LOCA of VVER-1200

Jinyan Du, Fangyu Dong, Chao Ma

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A008, August 8–12, 2022

Paper No: ICONE29-89803

DOI: https://doi.org/10.1115/ICONE29-89803

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Topics: Accidents, Containment, Coolants, Damage, Defense industry, Emergency core cooling systems, High pressure (Physics), Nuclear power stations, Nuclear reactor coolants, Pressure

Proceedings Papers

Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State

Yanzhu Chen, Zhi Yang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A021, August 8–12, 2022

Paper No: ICONE29-91782

DOI: https://doi.org/10.1115/ICONE29-91782

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Topics: Nuclear power stations, Probability, Safety, Risk, Maintenance, Damage, Heat, Power grids, Power stations, Sensitivity analysis

Proceedings Papers

Research on Development of On-Line Monitoring of Fuel Damage in Nuclear Power Plant

Tian Yiduo, Hu Wenjun

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A044, August 8–12, 2022

Paper No: ICONE29-93128

DOI: https://doi.org/10.1115/ICONE29-93128

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Topics: Damage, Fuels, Nuclear power stations

Proceedings Papers

Level 1 Probabilistic Safety Analysis (PSA) of TNPP Units 3 and 4

Wenge Yu, Youyi Li, Xiye Lang, Yang Sun, Pengfei Zhao

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A035, August 8–12, 2022

Paper No: ICONE29-92359

DOI: https://doi.org/10.1115/ICONE29-92359

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Topics: Accidents, China, Damage, Design, Governments, Maintenance, Nuclear power, Nuclear power stations, Probabilistic safety assessment, Risk

Proceedings Papers

Radioactive Substance Release Risk Assessment for Fuel Mechanical Damage in Fuel Route

Ming Wang, Dingqing Guo, Fei Wang, Zhixin Xu, Bing Zhang, Jinkai Wang, Lili Tong, Xuewu Cao

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A034, August 8–12, 2022

Paper No: ICONE29-92301

DOI: https://doi.org/10.1115/ICONE29-92301

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Topics: Damage, Fuels, Probabilistic safety assessment, Radioactive substances, Risk, Risk assessment

NARROW

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

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

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact by Projectiles: Numerical Analysis on Test Results

Research on Liability Insurance for Radioactive Sources and Suggestions to China

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

Investigation the Fuel Damage Fraction of IB-LOCA

Thermal Performance Monitoring and Analysis of Nuclear Power Plant

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

The Development and Application of Real-Time Risk Monitor System Based on Level 2 PSA for NPP

Study on Interfacing System LOCA of VVER-1200

Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State

Research on Development of On-Line Monitoring of Fuel Damage in Nuclear Power Plant

Level 1 Probabilistic Safety Analysis (PSA) of TNPP Units 3 and 4

Radioactive Substance Release Risk Assessment for Fuel Mechanical Damage in Fuel Route

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