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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

Paper No: ICONE29-91669

DOI: https://doi.org/10.1115/ICONE29-91669

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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains

Proceedings Papers

Research on Key Problems of Digital Instrument and Control System Reliability Analysis for Probabilistic Safety Assessment

Shuhan Lin

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A039, August 8–12, 2022

Paper No: ICONE29-93001

DOI: https://doi.org/10.1115/ICONE29-93001

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Topics: Control systems, Event history analysis, Instrumentation, Probabilistic safety assessment

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

Paper No: ICONE29-93295

DOI: https://doi.org/10.1115/ICONE29-93295

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Topics: Nuclear power stations, Pressurized water reactors, Statistical analysis, Design, Damage, Decision making, Errors, Event history analysis, Failure, Model development

Proceedings Papers

Reliability Analysis of Phased Mission Systems Using GO-FLOW Methodology

Zhanyu He, Jun Yang, Takeshi Matsuoka, Ming Yang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A059, August 8–12, 2022

Paper No: ICONE29-91772

DOI: https://doi.org/10.1115/ICONE29-91772

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Topics: Event history analysis, Flow (Dynamics)

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

Paper No: ICONE29-91870

DOI: https://doi.org/10.1115/ICONE29-91870

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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

Seismic Isolation Reliability Analysis of a Lead-Bismuth Small Modular Reactor

Yi Huang, Min Qi

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A030, August 8–12, 2022

Paper No: ICONE29-92584

DOI: https://doi.org/10.1115/ICONE29-92584

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Topics: Event history analysis, Small modular reactors

Proceedings Papers

The Fire Event Analysis for Fire Frequency Estimation on Japanese Nuclear Power Plant

Yasunori Nagata, Tsuyoshi Uchida, Koji Shirai

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A004, August 4–5, 2020

Paper No: ICONE2020-16209

DOI: https://doi.org/10.1115/ICONE2020-16209

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Topics: Event history analysis, Fire, Ignition, Nuclear power stations

Proceedings Papers

Structural Redundancy Design and Reliability Analysis of Magnetic Bearing for HTGR Primary Helium Circulator

Yangbo Zheng, Zhengang Shi, Xingnan Liu, Ni Mo, Guojun Yang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A011, July 22–26, 2018

Paper No: ICONE26-81336

DOI: https://doi.org/10.1115/ICONE26-81336

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Topics: Design, Event history analysis, Helium, Magnetic bearings, Redundancy (Engineering), Very high temperature reactors, Reliability, Safety, Bearings, Conceptual design

Proceedings Papers

Application of Monte Carlo Methods in Reactor Protection System Reliability Research

Duo Li, Zhaojun Hao, Shuqiao Zhou, Chao Guo

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A006, July 22–26, 2018

Paper No: ICONE26-81300

DOI: https://doi.org/10.1115/ICONE26-81300

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Topics: Monte Carlo methods, Reactor protection systems, Reliability, Event history analysis, Simulation, Nuclear power stations, Chain, Complex systems, Control systems, Instrumentation

Proceedings Papers

Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor

Huang Yi, Zhang Tian-yi, Wang Jun, Yuan Yu-chen, Dong Xin

Paper No: ICONE26-81183

DOI: https://doi.org/10.1115/ICONE26-81183

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Topics: Boilers, Reliability, Sodium fast reactors, Failure mechanisms, Design, Fast neutron reactors, Event history analysis, Failure, Failure mode and effects analysis, Filters

Proceedings Papers

Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS

Liu Ying, Wang Ya-feng, Pang Bo, Tang Lei, Feng Bo, Cao Guo-hai

Paper No: ICONE26-81647

DOI: https://doi.org/10.1115/ICONE26-81647

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Topics: Computer software, Reliability, Safety, Failure, Event history analysis, Nuclear power stations

Proceedings Papers

One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation

Xiaotong Shang, Guanlin Shi, Kan Wang

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A043, July 22–26, 2018

Paper No: ICONE26-82185

DOI: https://doi.org/10.1115/ICONE26-82185

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Topics: Neutron flux, Neutrons, Nuclear fission, Transients (Dynamics), Cross section (Physics), Event history analysis, Monte Carlo methods, Nuclear reactor kinetics, Probability, Transient analysis

Proceedings Papers

Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Wentao Li, Danying Gu, Henan Zhang

Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A029, July 2–6, 2017

Paper No: ICONE25-67041

DOI: https://doi.org/10.1115/ICONE25-67041

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Topics: Control systems, Event history analysis, Feedwater, Nuclear power stations, Failure, Computer software, Probability, Uncertainty, Failure mechanisms, Reliability

Proceedings Papers

Modeling DCS of Nuclear Power Plant With Extended GO-FLOW Methodology

Lu Hongxing, Yang Ming, Dai Xinyu, Li Wei, Yoshikawa Hidekazu

Paper No: ICONE25-67540

DOI: https://doi.org/10.1115/ICONE25-67540

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Topics: Flow (Dynamics), Modeling, Nuclear power stations, Control systems, Hardware, Reliability, Engineering drawings, Event history analysis

Proceedings Papers

A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology

Yi Xiao-jian, Lu Ming-chao, Mu Hui-na, Shi Jian, Hou Peng

Paper No: ICONE25-67546

DOI: https://doi.org/10.1115/ICONE25-67546

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Topics: Nuclear power, Reliability, Failure, Control systems, Event history analysis, Monte Carlo methods, Nuclear power stations, Systems analysis

Proceedings Papers

Hierarchical Modeling of GO-FLOW Models for Online Risk Monitoring of Nuclear Power Plants

Dai Xinyu, Yang Ming, Zou Bowen, Lu Hongxing

Paper No: ICONE25-67543

DOI: https://doi.org/10.1115/ICONE25-67543

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Topics: Flow (Dynamics), Modeling, Nuclear power stations, Risk monitoring, Reliability, Failure, Risk assessment, Event history analysis, Accidents, Algorithms

Proceedings Papers

Passive System Reliability Analysis Based on Improved Support Vector Machine

Hao Ding, Qi Cai, Yongfa Zhang, Lizhi Jiang

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A037, July 2–6, 2017

Paper No: ICONE25-67621

DOI: https://doi.org/10.1115/ICONE25-67621

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Topics: Event history analysis, Support vector machines, Failure, Approximation, Artificial neural networks, Failure mechanisms, Nuclear reactors, Polynomials, Probability, Reliability

Proceedings Papers

Dependency Analysis of Critical Parameters Influencing the Reliability of Thermal-Hydraulic Nuclear Passive Systems

Samuel Abiodun Olatubosun, Zhijian Zhang

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A023, July 2–6, 2017

Paper No: ICONE25-67116

DOI: https://doi.org/10.1115/ICONE25-67116

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Topics: Reliability, Boilers, Event history analysis, Nuclear reactors, Safety, Water

Proceedings Papers

Research and Application to Risk-Informed NPP Events Trend Analysis Method

Chen Shijun, Zhang Sifan, Chen Peifeng, Zhang Kuan

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A006, July 2–6, 2017

Paper No: ICONE25-66117

DOI: https://doi.org/10.1115/ICONE25-66117

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Topics: Nuclear power stations, Risk, Trend analysis, Corrective actions, Event history analysis, Probabilistic safety assessment, Safety, Statistics, Weight (Mass)

Proceedings Papers

Discussion on STR and PFD Analysis of I&C System

Zhang Chao, Su Yanqin, Li Wei, Chen Wanqing, Chen Qiang

Paper No: ICONE25-67773

DOI: https://doi.org/10.1115/ICONE25-67773

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Topics: Design, Event history analysis, Instrumentation, Nuclear power stations, Probability, Reliability, Safety, Semiconductor industry

NARROW

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

Research on Key Problems of Digital Instrument and Control System Reliability Analysis for Probabilistic Safety Assessment

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

Reliability Analysis of Phased Mission Systems Using GO-FLOW Methodology

Reliability Analysis of Off-Plant Power for Multi-Units

Seismic Isolation Reliability Analysis of a Lead-Bismuth Small Modular Reactor

The Fire Event Analysis for Fire Frequency Estimation on Japanese Nuclear Power Plant

Structural Redundancy Design and Reliability Analysis of Magnetic Bearing for HTGR Primary Helium Circulator

Application of Monte Carlo Methods in Reactor Protection System Reliability Research

Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor

Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS

One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation

Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Modeling DCS of Nuclear Power Plant With Extended GO-FLOW Methodology

A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology

Hierarchical Modeling of GO-FLOW Models for Online Risk Monitoring of Nuclear Power Plants

Passive System Reliability Analysis Based on Improved Support Vector Machine

Dependency Analysis of Critical Parameters Influencing the Reliability of Thermal-Hydraulic Nuclear Passive Systems

Research and Application to Risk-Informed NPP Events Trend Analysis Method

Discussion on STR and PFD Analysis of I&C System

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