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Proceedings Papers

Dynamic Event Tree Analysis of SGTR Accidents Considering HRA

Nianchun Qu, He Wang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136092
https://doi.org/10.1115/ICONE31-136092
View Paper titled, Dynamic Event Tree Analysis of SGTR Accidents Considering HRA
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Topics: Accidents, Boilers, Errors, Human reliability analysis, Probability, Rupture, Safety, Modeling, Event history analysis, Human factors
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92584
https://doi.org/10.1115/ICONE29-92584
View Paper titled, Seismic Isolation Reliability Analysis of a Lead-Bismuth Small Modular Reactor
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Topics: Event history analysis, Small modular reactors
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

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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93001
https://doi.org/10.1115/ICONE29-93001
View Paper titled, Research on Key Problems of Digital Instrument and Control System Reliability Analysis for Probabilistic Safety Assessment
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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
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
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91772
https://doi.org/10.1115/ICONE29-91772
View Paper titled, Reliability Analysis of Phased Mission Systems Using GO-FLOW Methodology
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Topics: Event history analysis, Flow (Dynamics)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16209
https://doi.org/10.1115/ICONE2020-16209
View Paper titled, The Fire Event Analysis for Fire Frequency Estimation on Japanese Nuclear Power Plant
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Topics: Event history analysis, Fire, Ignition, 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82185
https://doi.org/10.1115/ICONE26-82185
View Paper titled, One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81647
https://doi.org/10.1115/ICONE26-81647
View Paper titled, Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS
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Topics: Computer software, Reliability, Safety, Failure, Event history analysis, Nuclear power stations
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81300
https://doi.org/10.1115/ICONE26-81300
View Paper titled, Application of Monte Carlo Methods in Reactor Protection System Reliability Research
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81183
https://doi.org/10.1115/ICONE26-81183
View Paper titled, Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81336
https://doi.org/10.1115/ICONE26-81336
View Paper titled, Structural Redundancy Design and Reliability Analysis of Magnetic Bearing for HTGR Primary Helium Circulator
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67621
https://doi.org/10.1115/ICONE25-67621
View Paper titled, Passive System Reliability Analysis Based on Improved Support Vector Machine
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67116
https://doi.org/10.1115/ICONE25-67116
View Paper titled, Dependency Analysis of Critical Parameters Influencing the Reliability of Thermal-Hydraulic Nuclear Passive Systems
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66117
https://doi.org/10.1115/ICONE25-66117
View Paper titled, Research and Application to Risk-Informed NPP Events Trend Analysis Method
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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
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67773
https://doi.org/10.1115/ICONE25-67773
View Paper titled, Discussion on STR and PFD Analysis of I&C System
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66862
https://doi.org/10.1115/ICONE25-66862
View Paper titled, Operating Reliability Assessment of FPGA-Based NPP I&C Systems: Approach, Technique and Implementation
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67041
https://doi.org/10.1115/ICONE25-67041
View Paper titled, Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67540
https://doi.org/10.1115/ICONE25-67540
View Paper titled, Modeling DCS of Nuclear Power Plant With Extended GO-FLOW Methodology
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Topics: Flow (Dynamics), Modeling, Nuclear power stations, Control systems, Hardware, Reliability, Engineering drawings, Event history analysis