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Proceedings Papers

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

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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

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

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Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89165
https://doi.org/10.1115/ICONE29-89165
View Paper titled, Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design
Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

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Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis
Proceedings Papers

Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads

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Masato Murohara, Akira Yamazaki, Takuya Sato, Naoto Kasahara
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A072, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65553
https://doi.org/10.1115/ICONE28-65553
View Paper titled, Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads
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Topics: Buckling, Reactor vessels, Failure, Design, Accidents, Deformation, Earthquakes, Fukushima nuclear disaster, Japan, 2011, High temperature, Nuclear reactor accidents
Proceedings Papers

Application of Level 2 PSA in the Design of Cavity Injection System for Nuclear Power Plant

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Wentao Zhu, Wenjing Li
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82095
https://doi.org/10.1115/ICONE26-82095
View Paper titled, Application of Level 2 PSA in the Design of Cavity Injection System for Nuclear Power Plant
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Topics: Cavities, Design, Nuclear power stations, Vessels, Accidents, Decision making, Safety, Fukushima nuclear disaster, Japan, 2011, Nuclear reactor accidents, Probabilistic safety assessment
Proceedings Papers

Research on Optimization of Ingestion Emergency Planning Zone Sizing

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Mengxi Wang, Na Xue, Xinjian Liu
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81285
https://doi.org/10.1115/ICONE26-81285
View Paper titled, Research on Optimization of Ingestion Emergency Planning Zone Sizing
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Topics: Emergency management, Optimization, Food products, Chain, Radioisotopes, Emergency preparedness, Plumes (Fluid dynamics), Contamination, Nuclear power stations, Simulation
Proceedings Papers

Study on Factors Influencing the Diffusion and Migration of Radionuclide Offshore in Nuclear Power Plant Accidents

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Li Zichao, Zhou Tao, Qin Xuemeng, Amir Haider, Li Bing, Chen Juan
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A026, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81865
https://doi.org/10.1115/ICONE26-81865
View Paper titled, Study on Factors Influencing the Diffusion and Migration of Radionuclide Offshore in Nuclear Power Plant Accidents
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Topics: Diffusion (Physics), Nuclear reactor accidents, Ocean engineering, Radioisotopes, Sedimentation, Simulation, Turbulent diffusion, Accidents, Decision making, Emergencies
Proceedings Papers

Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly

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Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A012, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66444
https://doi.org/10.1115/ICONE25-66444
View Paper titled, Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly
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Topics: Fuels, Manufacturing, Pressurized water reactors, Boron, Cycles, Nuclear reactors, Safety, Accidents, High temperature, Ceramics
Proceedings Papers

In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches

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Pei Shen, Wenzhong Zhou
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A017, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67176
https://doi.org/10.1115/ICONE25-67176
View Paper titled, In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches
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Topics: Experimental methods, Explosions, Steam, Vessels, Coolants, Heat transfer, Reactor vessels, Accident management, Accidents, Containment
Proceedings Papers

A Method for Online Calibration of MAAP Simulations in a Severe Accident Management System Database

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Weifeng Xu, Fangqing Yang, Peng Chen, Yehong Liao
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A006, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66431
https://doi.org/10.1115/ICONE25-66431
View Paper titled, A Method for Online Calibration of MAAP Simulations in a Severe Accident Management System Database
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Topics: Accident management, Calibration, Databases, Simulation, Accidents, Failure, Uncertainty, Containment, Emergencies, Nuclear reactor accidents
Proceedings Papers

Scaling Analysis of Passive Heat Exchanger Under Station Blackout Accident

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Liu Yu-sheng, Xu Chao, Zhuang Shao-xin, Li Cong-xin, Zhang Pan
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A021, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66274
https://doi.org/10.1115/ICONE25-66274
View Paper titled, Scaling Analysis of Passive Heat Exchanger Under Station Blackout Accident
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Topics: Accidents, Heat exchangers, Safety, Design, Engineering prototypes, Heat, Test facilities, Nuclear power stations, Cooling, Transients (Dynamics)
Proceedings Papers

Neutronic Analysis of Accident-Tolerant Fuel Assemblies With Silicon Carbide Cladding in Pressurized Water Reactors

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Zhixiong Tan, Jiejin Cai
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A018, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66744
https://doi.org/10.1115/ICONE25-66744
View Paper titled, Neutronic Analysis of Accident-Tolerant Fuel Assemblies With Silicon Carbide Cladding in Pressurized Water Reactors
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Topics: Accidents, Cladding systems (Building), Fuels, Pressurized water reactors, Silicon, Manufacturing, Neutrons, Design, Safety, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Conceptual Formation of Advanced HIS Design Method for Digital I&C + HMIT

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Hidekazu Yoshikawa, Zhanguo Ma, Amjad Nawaz, Ming Yang
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, V001T04A017, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66530
https://doi.org/10.1115/ICONE25-66530
View Paper titled, Conceptual Formation of Advanced HIS Design Method for Digital I&C + HMIT
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Topics: Accidents, Computer simulation, Coolants, Defense industry, Design, Design methodology, Nuclear power stations, Nuclear reactor accidents, Pressurized water reactors, Risk monitoring
Proceedings Papers

Development of Numerical Simulation for Jet Break Up Behavior in Complicated Structure of BWR Lower Plenum (7) Measurement of Fragment Diameter by Image Processing Technique

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Yuki Narushima, Yutaka Abe, Akiko Kaneko, Tetsuya Kanagawa, Hiroyuki Yoshida
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A045, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60623
https://doi.org/10.1115/ICONE24-60623
View Paper titled, Development of Numerical Simulation for Jet Break Up Behavior in Complicated Structure of BWR Lower Plenum (7) Measurement of Fragment Diameter by Image Processing Technique
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Topics: Boiling water reactors, Computer simulation, Image processing, Flow (Dynamics), Accidents, Filters, Fluids, Fukushima nuclear disaster, Japan, 2011, Log normal distribution, Nozzles
Proceedings Papers

Evaluation of Retardation Effect of Cesium Ions Through Groundwater Unsaturated Zone

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Takenori Ozutsumi, Yuichi Niibori, Taiji Chida
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T11A014, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60979
https://doi.org/10.1115/ICONE24-60979
View Paper titled, Evaluation of Retardation Effect of Cesium Ions Through Groundwater Unsaturated Zone
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Topics: Groundwater, Ions, Decontamination, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Nuclear reactor accidents, Sands, Sorption, Strontium
Proceedings Papers

Development of Transient and Safety Analysis Method for ATF With SiC

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Fumie Sebe, Masato Yamada, Yutaka Takeuchi, Kazuo Kakiuchi, Kazunari Okonogi
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A005, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60250
https://doi.org/10.1115/ICONE24-60250
View Paper titled, Development of Transient and Safety Analysis Method for ATF With SiC
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Topics: Safety, Transients (Dynamics), Accidents, Oxidation, Water, Transient analysis, Cladding systems (Building), Fuels, High temperature, Hydrogen
Proceedings Papers

Regulatory Actions That Hinder Development of Effective Risk Reduction Measures by the Nuclear Industry for Enhanced Severe Accident Prevention and Mitigation Measures After Fukushima

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Sunil Nijhawan
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A005, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60700
https://doi.org/10.1115/ICONE24-60700
View Paper titled, Regulatory Actions That Hinder Development of Effective Risk Reduction Measures by the Nuclear Industry for Enhanced Severe Accident Prevention and Mitigation Measures After Fukushima
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Topics: Fukushima nuclear disaster, Japan, 2011, Nuclear industry, Risk reduction, Safety, Accidents, Public utilities, Risk, Silence, Damage, Emergencies
Proceedings Papers

Numerical Simulation of Hydrogen Dispersion Inside a Compartment Using HYDRAGON Code

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M. Saeed, Yu Jiyang, B. X. Hou, Aniseh A. A. Abdalla, Zhang Chunhui
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A019, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60610
https://doi.org/10.1115/ICONE24-60610
View Paper titled, Numerical Simulation of Hydrogen Dispersion Inside a Compartment Using HYDRAGON Code
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Topics: Computer simulation, Hydrogen, Containment, Nuclear power stations, Accidents, Turbulence, Combustion, Nuclear reactor accidents, Boundary layers, China
Proceedings Papers

Coupled Source Term Estimation Using Both Forward and Backward Method for Nuclear Power Plant Accident

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Sida Sun, Sheng Fang, Yun Liu, Hong Li
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A008, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60176
https://doi.org/10.1115/ICONE24-60176
View Paper titled, Coupled Source Term Estimation Using Both Forward and Backward Method for Nuclear Power Plant Accident
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Topics: Accidents, Emergency response, Nuclear power stations, Nuclear reactor accidents, Nuclear reactors, Uncertainty
Proceedings Papers

Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum: (4) Multi-Channel Experimental Analysis by Detailed Two-Phase Analysis Code TPFIT

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Takayuki Suzuki, Hiroyuki Yoshida, Fumihisa Nagase, Yutaka Abe, Akiko Kaneko
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30154
https://doi.org/10.1115/ICONE22-30154
View Paper titled, Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum: (4) Multi-Channel Experimental Analysis by Detailed Two-Phase Analysis Code TPFIT
Open the PDF for Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum: (4) Multi-Channel Experimental Analysis by Detailed Two-Phase Analysis Code TPFIT in another window
Topics: Boiling water reactors, Computer simulation, Experimental analysis, Simulation, Accidents, Flow (Dynamics), Shapes, Computational fluid dynamics, Evaluation methods, Fukushima nuclear disaster, Japan, 2011