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Proceedings Papers

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Hidemasa Yamano, Shigenobu Kubo, Taro Kan, Akihiro Shibata, Edouard Hourcade, Jean François Dirat
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91505
https://doi.org/10.1115/ICONE29-91505
View Paper titled, Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor
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Topics: Accidents, Sodium fast reactors, Design, Coolants, Fuels, Probability, Sodium, Vessels
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

Study on Probability Safety Assessment Method of Small Aircraft Crash Event in a Nuclear Power Plant

Handing Wang, Xiaoyu Liang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90733
https://doi.org/10.1115/ICONE29-90733
View Paper titled, Study on Probability Safety Assessment Method of Small Aircraft Crash Event in a Nuclear Power Plant
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Topics: Aircraft, Nuclear power stations, Probability, Safety
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91782
https://doi.org/10.1115/ICONE29-91782
View Paper titled, Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State
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Topics: Nuclear power stations, Probability, Safety, Risk, Maintenance, Damage, Heat, Power grids, Power stations, Sensitivity analysis
Proceedings Papers

Fire Probability Safety Analysis for a Compact Small Modular Reactor

Yanzhu Chen
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91381
https://doi.org/10.1115/ICONE29-91381
View Paper titled, Fire Probability Safety Analysis for a Compact Small Modular Reactor
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Topics: Fire, Probability, Safety, Small modular reactors, Design, Damage, Nuclear power stations
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

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

A Statistical Approach to Quantify Taylor Microscale for Turbulent Flow Surrogate Model

Molly Ross, John Matulis, Hitesh Bindra
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91452
https://doi.org/10.1115/ICONE29-91452
View Paper titled, A Statistical Approach to Quantify Taylor Microscale for Turbulent Flow Surrogate Model
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Topics: Microscale devices, Turbulence, Dynamics (Mechanics), Diffusion (Physics), Fluid mechanics, Time series, Channel flow, Density, Equilibrium (Physics), Fluctuations (Physics)
Proceedings Papers

Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor

Risako Nakashima, Akari Koike, Takaaki Sakai, Norihiro Doda, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A107, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93039
https://doi.org/10.1115/ICONE29-93039
View Paper titled, Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor
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Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants
Proceedings Papers

A Location Algorithm for Orphan Radioactive Source

Qianxi Xiao, Jiejin Cai
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A115, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93592
https://doi.org/10.1115/ICONE29-93592
View Paper titled, A Location Algorithm for Orphan Radioactive Source
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Topics: Algorithms, Robots, Probability, Radiation (Physics), Gaussian distribution, Mobile robots, Path planning, Safety, Simulation experiments, Switches
Proceedings Papers

Development of Adaptive Sampling Software Based on Relap5

Haoyin Chen, He Wang, Mohamedelmogtabh Omer Elfadni Suliman, Xinyue Wang, Qiang Zhao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A094, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92454
https://doi.org/10.1115/ICONE29-92454
View Paper titled, Development of Adaptive Sampling Software Based on Relap5
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Topics: Computer software, Nuclear power stations, Accidents, Failure, Probability, Safety, Dynamic response, Industrial research, Probabilistic safety assessment
Proceedings Papers

Numerical Model for Subcooled Flow Boiling Heat Transfer and Critical Heat Flux Based on Probability of Bubble Interaction

Shichang Dong, Shengjie Gong
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A058, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93755
https://doi.org/10.1115/ICONE29-93755
View Paper titled, Numerical Model for Subcooled Flow Boiling Heat Transfer and Critical Heat Flux Based on Probability of Bubble Interaction
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Topics: Boiling, Bubbles, Computer simulation, Critical heat flux, Flow (Dynamics), Heat transfer, Probability, Subcooling
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

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

Functional Reliability Investigation on Capacity of Reactor Core Natural Circulation Cooling in XAPR Under MLOCA

Baosheng Wang, Tengyue Ma, Lihong Bao, Zhenhui Ma, Pan Hu, Da Li, Chunlei Su, Lixin Chen, Xiuhuan Tang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93526
https://doi.org/10.1115/ICONE29-93526
View Paper titled, Functional Reliability Investigation on Capacity of Reactor Core Natural Circulation Cooling in XAPR Under MLOCA
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Topics: Cooling, Probability, Reliability
Proceedings Papers

Post-hoc Interpretability Based Parameter Selection for Data Oriented Nuclear Reactor Accident Diagnosis System

Chengyuan Li, Meifu Li, Zhifang Qiu
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92505
https://doi.org/10.1115/ICONE29-92505
View Paper titled, Post-hoc Interpretability Based Parameter Selection for Data Oriented Nuclear Reactor Accident Diagnosis System
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Topics: Artificial neural networks, Errors, Nuclear power stations, Nuclear reactor accidents, Probability, Reliability, Thermal hydraulics, Trains, Transients (Dynamics), Uncertainty
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64300
https://doi.org/10.1115/ICONE28-64300
View Paper titled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64154
https://doi.org/10.1115/ICONE28-64154
View Paper titled, Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy