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Proceedings Papers

Improvements on Fuel Failures Diagnosis Method for Pressurized Water Reactor Nuclear Power Plant Based on Radioactive Activities Inside the Waste Gas Treatment System

Weifeng Lyu, Runchun Guo, Wenwang Ran, Yaoyi Gao, Jun Xiong
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A072, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92996
https://doi.org/10.1115/ICONE29-92996
View Paper titled, Improvements on Fuel Failures Diagnosis Method for Pressurized Water Reactor Nuclear Power Plant Based on Radioactive Activities Inside the Waste Gas Treatment System
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Topics: Failure, Fuels, Nuclear power stations, Pressurized water reactors
Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92788
https://doi.org/10.1115/ICONE29-92788
View Paper titled, A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs
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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)
Proceedings Papers

Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products

Zhirui Jiang
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92012
https://doi.org/10.1115/ICONE29-92012
View Paper titled, Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products
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Topics: Control systems, Nuclear power, Probabilistic safety assessment, Simulation, Algorithms, Failure, Failure mechanisms, Probability, Reliability, Deformation
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88933
https://doi.org/10.1115/ICONE29-88933
View Paper titled, Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter
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Topics: Design, Failure, Optimization, Probability, Transients (Dynamics)
Proceedings Papers

Assessment and Control Value Formulation on Radiological Consequence of On-Site Worker due to Radioactive Component Failure for Pressurized Water Reactor Plant

Zhou Jing, Ran Wen Wang, Gong Quan, Lv Wei Feng
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91624
https://doi.org/10.1115/ICONE29-91624
View Paper titled, Assessment and Control Value Formulation on Radiological Consequence of On-Site Worker due to Radioactive Component Failure for Pressurized Water Reactor Plant
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Topics: Failure, Nuclear power stations, Pressurized water reactors, Safety
Proceedings Papers

Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment

Zhaohui Lu, Zewen Li, Jianming Zhou, Qingsong Liu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90150
https://doi.org/10.1115/ICONE29-90150
View Paper titled, Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment
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Topics: Design, Engineering prototypes, Failure, Kinematics, Polishing equipment, Pressurized water reactors, Stress, Structural design, Surface finishing, Wear
Proceedings Papers

Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology

Guilian Shi, Huang Xiaojin, Mo Changyu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89387
https://doi.org/10.1115/ICONE29-89387
View Paper titled, Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology
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Topics: Circuits, Failure, Physics, Electronic equipment, Hardware, Design, Failure mechanisms, Nuclear power, Nuclear power stations, Time series
Proceedings Papers

Reliability Analysis of Off-Plant Power for Multi-Units

Chen Honghao, Ren Cheng, Wu Jian, Liu Deyi, Luo Yang, Zou Shengjia, Wang Zilong
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91870
https://doi.org/10.1115/ICONE29-91870
View Paper titled, Reliability Analysis of Off-Plant Power for Multi-Units
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Topics: Accidents, Emergencies, Event history analysis, Failure, Modeling, Nuclear power, Nuclear power stations, Power grids, Probabilistic safety assessment, Reliability
Proceedings Papers

On Line Monitoring of Sensor Failure in Nuclear Power Plant Based on Sequential Probability Ratio Test

Fangxiaozhi Yu, Xintong Ma, Zhuang Miao, Min Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89215
https://doi.org/10.1115/ICONE29-89215
View Paper titled, On Line Monitoring of Sensor Failure in Nuclear Power Plant Based on Sequential Probability Ratio Test
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Topics: Failure, Nuclear power stations, Probability, Sensors
Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93417
https://doi.org/10.1115/ICONE29-93417
View Paper titled, Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature
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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis
Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89461
https://doi.org/10.1115/ICONE29-89461
View Paper titled, Research on the Influence of Degassing on the Release of Fission Gases in PWRs
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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods
Proceedings Papers

Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

Zhang Xingzhen, Sun Hui, Zhao Yanjun, Shi Xianzuo
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92834
https://doi.org/10.1115/ICONE29-92834
View Paper titled, Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant
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Topics: Excitation, Excitation systems, Nuclear power stations, Simulation, Bridges (Structures), Maintenance, Failure, Nuclear power, Accidents, Construction
Proceedings Papers

Intelligent Monitoring and Diagnosis of CCWS Heat Exchanger For Nuclear Power Plant

Qian Ming, Jian Hu, Wu Wang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92260
https://doi.org/10.1115/ICONE29-92260
View Paper titled, Intelligent Monitoring and Diagnosis of CCWS Heat Exchanger For Nuclear Power Plant
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Topics: Cooling, Failure, Heat exchangers, Nuclear power stations, Water
Proceedings Papers

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91669
https://doi.org/10.1115/ICONE29-91669
View Paper titled, Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method
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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91785
https://doi.org/10.1115/ICONE29-91785
View Paper titled, The Development and Application of Real-Time Risk Monitor System Based on Level 2 PSA for NPP
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Topics: Nuclear power stations, Risk monitoring, Risk, Risk management, Safety, Economics , Optimization, China, Damage, Failure
Proceedings Papers

Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials

Deyan Kong, Xu Liu, Jie Cheng, Jianjun Wang, Jinqiang Zhang, Dingyong Chen, Qingzhao Li, Yanting Liu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A029, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91951
https://doi.org/10.1115/ICONE29-91951
View Paper titled, Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials
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Topics: Chaos, Failure, Polynomials, Pressurized water reactors, Probability, Stress corrosion cracking, Uncertainty analysis
Proceedings Papers

Probabilistic Analysis of Containment Overpressure Failure in Level 2 PSA

Yu Liu, Wenjing Li, Wenkui Lu, Gaopeng Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92038
https://doi.org/10.1115/ICONE29-92038
View Paper titled, Probabilistic Analysis of Containment Overpressure Failure in Level 2 PSA
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Topics: Containment, Failure
Proceedings Papers

Research of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects

Xiaoming Zhang, Lijuan Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92459
https://doi.org/10.1115/ICONE29-92459
View Paper titled, Research of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects
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Topics: Failure, Probabilistic safety assessment, Risk, Accidents, Damage, Cables, China, Coolants, Nuclear power, Pipes
Proceedings Papers

Research on PSA Analysis for Equipment Degradation in Nuclear Power Plant

Zhi Yang, Sifan Zhang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A049, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93228
https://doi.org/10.1115/ICONE29-93228
View Paper titled, Research on PSA Analysis for Equipment Degradation in Nuclear Power Plant
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Topics: Failure, Nuclear power stations, Probability, Safety
Proceedings Papers

Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant

Feng Chu-ran, Ma Yuan, Yan Lin, Yang Guansan, Liu Bin
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93295
https://doi.org/10.1115/ICONE29-93295
View Paper titled, Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant
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Topics: Nuclear power stations, Pressurized water reactors, Statistical analysis, Design, Damage, Decision making, Errors, Event history analysis, Failure, Model development