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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
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, V001T01A002, July 22–26, 2018
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
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, V001T04A011, July 22–26, 2018
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

Discussion on STR and PFD Analysis of I&C System

Zhang Chao, Su Yanqin, Li Wei, Chen Wanqing, Chen Qiang
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, V001T04A045, July 2–6, 2017
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
Proceedings Papers

Operating Reliability Assessment of FPGA-Based NPP I&C Systems: Approach, Technique and Implementation

Eugene Babeshko, Ievgenii Bakhmach, Vyacheslav Kharchenko, Eugene Ruchkov, Oleksandr Siora
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, V001T04A026, July 2–6, 2017
Paper No: ICONE25-66862
DOI: https://doi.org/10.1115/ICONE25-66862
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Topics: Nuclear power stations, Reliability, Design, Integrated circuits, Blanks, Control systems, Event history analysis, Failure mechanisms, Gates (Closures), Instrumentation
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
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, V001T04A041, July 2–6, 2017
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
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, V001T01A040, July 2–6, 2017
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
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, V001T04A042, July 2–6, 2017
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

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

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